ML20215B073

Assessment of Texas Utils Generating Co As-Built Documentation for Piping & Pipe Supports,Final Rept. W/Util 870520 Design Basis Document Index & Impell Corp 870515 Design Verification of Cable Tray Sys Inaccessible..

ML20215B073
Person / Time
Site:	Comanche Peak
Issue date:	07/02/1986
From:	Bain R, Polachek M, Wigley L STONE & WEBSTER, INC.
To:
Shared Package
ML20215B058	List: ML20215B073 ML20215B166 ML20215B190 ML20215B206 ML20215B224 ML20215B384 ML20215B409 ML20215B422 ML20215B444 ML20215B446 ML20215B485 TXX-6517, Forwards Documents Listed in Encl Wg Counsil & Gs Keeley to Nh Williams of Cygna Energy Svcs,Including Assessment of Texas Utils Generating Co As-Built Documentation for Piping & Pipe Supports
References
NUDOCS 8706170213
Download: ML20215B073 (76)

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Enclosure A j

SWEC Report " Assessment of TUGC0 As-Built Documentation for Piping and Pipe Supports" July 2, 1986 i

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8706170213 870669 PDR ADOCK 05000445 A

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STONE 6 WEBSTER ENGINEERING CORPORATION y.

245 SUMMER SrnEET. BOSTON, massachusetts ADDR E S S AU. CORR ESPONOCNCE TO P.0, BoK 2325. SC970H, M A 01107 W U TELEX 944001 eoaTom 94 0977 OteIGN cEa'[v"w' u. aJ.

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Mr. Larry D. Nace Vice-President, Engineering / Construction July 2, 1986 Texas Utilities Generating Company Comanche Peak Steam Electric Station Farm Road 56 Glen Rose, Texas 76043

Dear Larry:

ASSESSMENT OF TUGC0 AS-BUILT DOCUMENTATION FOR PIPING AND PIPE SUPPORTS COMANCHE PEAK STEAM ELECTRIC STATION During the Nuclear Regulatory Commission (NRC)/ Texas Utilities Generating Company (TUGCO) public meeting held on OctcSer 2 and 3,1985, in Cranbury, Texas, the NRC Staff raised questions about the TUGC0 program and the organizations involved in addressing the requirements in NRC IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Systems.

Subsequent to the above meeting, questions regarding the adequacy of the j

as-built, documentation have been raised during NRC Staff audits of the l' t one & Webster Engineering Corporation (SWEC) stress requalification program effort.

1 In April 1986, TUCCO commissioned a task group to conduct an overall assessment of relevant activities associated with piping and pipe supports at Comanche Peak Steam Electric Station Unit 1.

The purpose of this assessment was to determine whether the existing programs are effective to ensure the adequacy and completeness of the as-built documents used in the stress requalification program being performed by SWEC.

Attachment (1) provides the final report of this arsessment.

Please call me at (617) 589-8170 (Boston) if you have any questions.

Very truly yours,

. Wigley TapkGroupL er

Attachment:

" Assessment of TUGC0 As-Built Documentation for Piping and Pipe Supports," report dated July 2, 1986.

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1 cc:

J.C. Finneran J.E. Krechting l

0.W. Lowe i

T.G. Tyler j

SWEC Internal CC:

W.A. Matson E.J. Sisken P. Dunlop R.K. Westfahl V.A. Hoffman l

E.J. Brabazon D.C. Foster A.W. Chan R.P. Klause C.E. Watters S. Feldman /

R. Ackley i

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ASSESSMENT OF TUGC0 AS-BUILT DOCUMENTATION FOR l

PIPING AND PIPE SUPPORTS E

FINAL REPORT 1

TEXAS UTILITIES GENERATING COMPANY (TUGCO)

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

UNIT 1 1

July 2, 1986 1

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8 Prepared by:

2 h..P. Polac

- Principal Engr - Engr Mechanics Prepared by:

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e. A,,c.1.,. t e en E... e.cM.n1..

Approved by:

S.

igley - Gro a

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TABLE OF CONTENTS 1

Section Description Page I

KEY ABBREVIATIONS / DEFINITIONS

SUMMARY

1

1.0 INTRODUCTION

2 1

2.0 PURPOSE 2

3.0 SCOPE 2

1 4.0 ATTRIBUTES 2

5.0 EXISTING PROGRAMS 3

6.0 DISCUSSION 8

7.0 CONCLUSION

S 13 8.0 RECOMMENDATIONS 14 I-

9.0 REFERENCES

17 Tables 1 - Attributes

'l 2 - Responsibility Matrix Figures 1 - Organizational Interrelationships 2 - Detailed Organizational Interrelationships Attachment 1 - Action Plan I

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KEY ABBREVIATIONS / DEFINITIONS ASME III - Section III of the American Society of Mechanical Engineers Code BRH - Brown & Root Pipe Hanger Drawing BRHL - Brr.wn & Root Pipe Hanger Location Drawing BRP - Brown & Root Piping Isometrics g

m CAR - TUGC0 Corrective Action Report CPRT - Comanche Peak Response Team CPSES - Comanche Peak Steam Electric Station DR - Deviation Report ERC - Evaluation Research Corporation f

GHH - Gibbs & Hill Small Bore Pipe Hanger Location Drawing i

HVP - Hardware Validation Program.

Recommended as part of this assess-ment to be performed by TUGC0 to ensure hardware adequacy of safety-related piping systems.

LDL - Line Designation List NCR - Nonconformance Report issued by TUGC0 QA/QC - Quality Assurance / Quality Control SWEC - Stone & Webster Engineering Corporation SRP - Stress Requalification Program performed by SWEC SVP - Supplemental Verification Programs.

Recommended as part of this assessment to be performed by TUGC0 to verify attributes related to safety-related piping systems.

TUGC0 - Texas Utilities Generating Company g

79 NRC IE Bulletin 79-14 for the Seismic Analysis for As-Built 3

Safety-Related Piping Systems CPPP Comanche Peak Project Procedure for SWEC field walkdowns CPPP Comanche Peak Project Procedure for piping and pipe support system engineering walkdown by SWEC i

C'PPP Comanche Peak Project Procedure for the pipe stress / support requalification effort I

1074-15454-HC4

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Safety Significant -

As used in this report (and the ERC program), an identified discrepancy which, if uncorrected, could result in loss of capability of the af-fected system, structure, or component to per-form its intended safety function (no credit is i

taken for reduadancy).

10CFR50 - Title l'0, Part 50 of the Code of Federal Regulations 10CFR50.55e - Section in the Code of Federal Regulations which contains the requirements for the reporting of p,otential issues which could adversely affect the safe operation of the plant.

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Normal Inspection Process -

QA/QC Inspection program' originally per-formed by the installer contracted by TUGC0 to meet the requirements of the Erection Specification, Appendix B to 10CFR50.od/or i

ASME III.

1 Safety-Related Piping System -As used in this report, an all-inclusive term which includes all ASME III piping and pipe supports.

Also includes continuations I

of the code piping after the code class I

break up to the end of the pipe stress ana-lytical model.

Computer-Analyzed -

As used in this report, a term associated j

with small bore piping which reflects the j

type of detailed computer analysis used to analytically qualify the piping.

"oncomputtr-Analyzed -

As used in this report, a term associated I

with small bore piping which reflects the type of standard ' cookbook' or hand-calca-lated analysis used to qualify the piping.

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i Attribute -

As used in this report, a term which refers to the qualitative characteristics of safety-related piping systems.

Large Bore Piping -

Piping systems which are 2.5-inches nominal pipe diameter and greater.

Small Bore Piping -

Piping systems which are less than 2.5-inches nominal pipe diameter.

Stress Requalification Program (SRP) - Requalification of safety-related piping and pipe supports being performed by SWEC.

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Deviat., ion -

As used in this report, a verified failure to meet a li-5 censing c-:mitment, to meet a regulatory requirement, or to propet.s install hardware.

Although this is a term j

defined by ERC, it also is used to represent SWEC observa-i tions for simplicity.

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1074-15454-HC4

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SUMMARY

During the Nuclear Regulatory Comission (NRC)/ Texas Utilities Generating Company (TUGCO) public meeting held on October 2 and 3: J85, in Granbury, Texas, the NRC StaJf raised questions about the TUGCJ program and the organizations involved in addressing the requirements of NRC II Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping Sys-tems.

TUGC0 commissioned a task group to conduct an overall assessment of relevant activities associated with piping and pipe supporta at Comanche Peak Steam Electric Station - Unit 1.

The purpose of this assessment was to determine whether the existing pro-grams are effective to ensure the adequacy and completeness of the as-g built documents used in the stress requalification program (SRP) being E

Performed by Stone. & Webster Engineering Corporation (SWEC).

The assessment process involved the identification of attributes that are required for input to pipe stress analysis and pipe support design.

This included the attributes identified in NRC IE Bulletin 79-14 and other as-built documentation related to the SRP.

The existing programs of TUGCO, SWEC,' and Evaluation Research Cv ;) ration (ERC) were reviewed to determine which key attributes were 64 cessed.

The procedures' that evaluated the adequacy of these attributes s ad the organizational interfaces were also evaluated for completeness and ef-fectiveness.

The assessment identified the following:

There are existing procedures to ensure that all attributes I

identified in IE Bulletin.79-14 are verified.

The assessment further identified that these procedures apply to other as-built documentation used in the SRP.

There are programs in place to ensure that adverse as-built conditions are identified, evaluated for generic implications, and corrected; however, some improvements are recommended.

Modifications of the programmatic interfaces are recommended to improve communication between the involved organizations.

Recommendations are presented by the Task Group that will enhance the overall program.

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1.0 INTRODUCTION

During the Nucitar Regulatory Commission (NRC)/ Texas Utilities Generating Company (TUGCO) public meeting held on October 2 and 3, 1985, in i

Granbury, Texas, the NRC Staff raised questions germane to the attributes i

in IE Bulletin 79-14, Seismic Analysis for As-Built Safety-Related Piping i

Systems, how they were being addressed and verified, and the relationship and interfaces between the organizations involved (TUGCO, Evaluation Re-

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search Corporation (ERC), and Stone & Webster Engineering Corporation I

(SWEC)).

Subsequent to the above meeting, questions regarding the ade-i g

quacy of the as-built documentation have been raised during NRC Staff 5-audits of the SVEC effort.

g TUGC0 commissioned a Task Group of L. S. Wigley (SWEC - Group Leader),

j R. A. Bain (SWEC -

Lead Engineer -

Engineering Mechanics) and-M. P. Polachek (SWEC - Principal Engineer - Engineering Mechanics) to 1

conduct an overall assessment of activities associated with safety-

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related pip'ing systems to address the above concerns.

2.0 PURPOSE The purpose of this assessment was to determine whether the existing pro-grams are effective to ensure the adequacy and completeness of the 4

as-built documents used in the stress requalification program (SRP) being I

performed by SWEC.

3.0 SCOPE i

8 The scope of this assessment includes:

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An identification of as-built attributes critical to the SRP, including those in IE Bulletin 79-14, and the organizations responsible for verification of the attributes.

2.

An evaluation of the programs currently in place at Comauche Peak Steam Electric Station (CPSES) - Unit 1 to verify the attributes.

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An evaluation of the process followed by ERC, TUGCO, and SWEC for the evaluation of as-built discrepancies critical to the SRP, including the interface among the ERC, SWEC, and TUGC0 programs and the applicable procedures used in the process.

g provides 'the action plan used by the Task Group for gather-E ing and evaluating the information necesary to conduct this assessment.

4.0 ATTRIBUTES Attributes associated with SWEC's SRP are listed in Table 1.. All at-tributes identified in IE Bulletin 79-14 are included in this list.

Documents which are used to record the attributes also are identified in Table 1.

The primary documents are American Society of Mechanical Engi-neers (ASME) control drawings for piping (BRPs) and hangers (BRHs), and 1074-15454-HC4 2

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d hanger locations (BRELs for large bore piping and GHHs or BRHLs for small 5

bore piping).

Other drawings or documents used include the line designa-tion list (LDL) for insulation, structural drawings for fire walls, and penetration schedule for penetration seals.

It is important to reinforce at the outset that the purpose of this as-sessment. was not to inspect the attributes directly, but to determine:

whether programs are in place to inspect the attributes; that the pro-l grams are effective; that the results are included in the stress requali-fication program (SRP); that root cause, trends, and generic implications are addressed; and that corrective action is taken, if appropriate.

Section 5.0 describes the programs of the involved organizations, while g

Section 6.0 discusses the adequacy and completeness of the programs and g

the attributes each verifies.

5.0 EXISTING PROGRAMS 9

5.1 TEXAS UTILITIES GENERATING COMPANY (TUGCO) 8 TUGC0 developed a program for as-built piping verification to meet the general intent of IE Bulletin 79-14 requirements.

Specifically, the TUGC0 procedure (CP-EI-4.5-1) required a phys. cal walkdown of piping sys-tems in addition to the normal inspection process- (described below).

8 This as-built program verified the follouing l

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. Piping dimensions, elevations, and directional changes 8

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Support and valve orientation 3.

Sleeve clearance 4.

Equipment orientation 5.

Support mark numbers 6.

Support and valve location 7.

Support type 8.

General support configuration 9.

Clearance between the pipe and support The above ' TUGC0 procedure applied to all safety-related large bore and computer-analyzed small bore piping and pipe supports.

Other attributes not included in the above TUGC0 as-built procedure were addressed in accordance with the normal inspection process.

The normal inspection process, as used in this report, consists of the activities required to meet the ASME III code, Appendix S to Title 10, Part 50 of the Code of Fedtral Regulations (10CFR50), and/or the contractor specifi-cation.

Also included in this term are the quality control procedures and construction procedures developed to meet these requirements.

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example, embedments were designed and installed in accordance with 3

Comanche Peak Specification No. 2323-SS-30, Structural Embedments.

The specification provided for a normal inspection program.

No special walk-down was required.

/alve weights were addressed in accordance with the Valve Weighing Pro-gram, Comanche. Peak Procedure No. CP-EI-2.2-1.

The procedure provided for physical weighing of a representative sample of generic types of

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valves and operators.

The procedure further provided for an engineering

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evaluation if the valve was not available for weighing or if additional j

information was required.

Pipe attachments are typically shown on the BRH for lugs or trunnions.

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Verification of this attribute was also dependent on the normal inspec-i tion process.

l Table 1 lists other attributes related to safety-related piping systems which were not addressed in the TUGC0 As-Built Program.

Typically, these attributes were verified in accordance with the nonnal inspection pro-cess.

Comanche Peak Specification No. 2323-11S-100 identified the re-g quirements for. piping and support erection.

This normal inspection M

process was also used for the noncomputer-analyzed small bore piping ex-cluded from the TUGC0 As-Built Program.

l In addition to the above programs, TUGC0 is responsible for the process-ing of Comanche Peak Response Team (CPRT) Deviation Reports /Out-of-Scope Observations in accordance with Comanche Peak Procedure No. CP-QP-16.3.

J This procedure provides TUGC0 with a mechanism to d ~.zment, on noncon-fonnance reports (NCRs), relevant ERC findings (discu.ised below) or any i

other organizatioss' (e.g., SWEC) relevant findings.

Additior ally, TUGC0 evaluates NCRs for potential reportability under 10CFRSO.S5e in ac.ordance with Comanche Peak Procedure Nos. CP-QAP-16.1, ContrL1 of Nonconforming Items, and NEO-CS-1, Evaluation of and Reporting of items / events under 10CFR21 and 10CFR50.55(e).

NCRs dispositioned use-as-is are evaluated by SWEC to verify the acceptability of the change to the design document.

Generic corrective action and root cause are addrest.ed in accordance with Comanche Peak Procedure No. CP-QP-17.0, Cor-rective Action.

5.2 STONE & WEBSTER ENGINEERING CORPORATION (SWEC)

TUGC0 has contracted SWEC to perform a stress requalification effort for g

the safety-related piping and pipe supports on CPSES.

As part of this 35e effort, SWEC has performed thret walkdowns to review existing TUGC0 docu-ments being used in the SRP.

Two walkdowns were performed in accordance with Comanche Peak Project Procedure CPPP-5 and one in accordance with CPPP-8.

Any deviations identified durinr these walkdowns have been or are being forwarded to TUGCO.

The two CPPP-5 valkdowns were sample inspections performed to verify that the exieting documentation was adequate to initiate the SRP with an ac-ceptable risk such that the analysis would not have to be redone upon completion of the ERC Program.

Valve location, hanger location, hanger 1074-15454-HC4 4

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function, and mlve and support orientation were the attributes verified.

These attribub e were selected since they have the greatest potential for impact on pipe stress analysis.

The first walkdown axamined a sample of large bore Class 2, and 3 piping systems.

A sample of the small bore I

noncomputer-analyzed piping systems which were not included in the TUGC0 As-Built Program was addressed in the second walkdown.

The CPPP-8 walkdown was performed by experienced pipe stress and support engineers on a sample of large bore stress problems to review physical relationships and critical configurations which could impact conclusions I

regarding overall piping system design and acceptance.

The objectives of this walkdown were as follows:

1.

To determine whether there were technical configuration issues, other than exist'ing technical findings from previous reviews, l

which should be evaluated relative to the functional behavior of the system, and 8

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For experienced SWEC personnel to become familiar with the physical aspects of the design and determine whether additional I

refinements of design inputs, guidelines, or procedures were necessary for the SRP.

t The walkdowns were based on a sample size of stress problems consistent I

with the ERC program (see below).

In addition to these walkdowns, SWEC has committed, in the Pipe Stress /

Support Requalification Procedure (CPPP-6), to a final walkdown for

i. '.e a ra nc e s.

This walkdown will ensure that any clearance violations exist between piping systems and nearby strt.ctures will be satisfactorily resolved based on the movements from the SRP.

5.3 EVALUATION RESEARCH CORPORATION (ERC)

ERC has developed a program to determine tue adequacy of the CPSES con-struction Quality Assurance / Quality Control (QA/QC) program and the ade-quacy of the installed hardware.

ERC was assigned this responsibility by the Comanche Peak Response Team (CPRT).

The CPRT has been charged with responding to and resolving concerns raised by external sources (i.e.,

NRC Staff's Technical Review Team, NRC Staff's Construction Assessment 8

'eam, Cygna Independent Assessment Program) regarding the adequacy of safety related hardware.

Additionally, the CPRT is charged with advising TUGC0 Management as to whether there is reasonable assurance that CPSES I

has been designed and constructed such that it is capable of being oper-ated safely.

To this end, ERC has formulated a program with three main components.

8 The first two address the issues raised by the external sources.

The third component addresses the quality of construction as it relates to all safety-related aspects of the plant.

This effort involves a sample reinspection of hardware that is representative of activities and pro-y; cesses used in the construction of safety-related aspects of the plant.

Also included is the investigation and determination, where possible, of 1074-15454-HC4 5

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the root cause of each identified safety-significant deficiency or ad-verse trend of nonsafety-significant deviations.

The implications from the root cause are analyzed to determine the extent that other construc-tion activities could be deficient for similar reasons.

Generic implica-I, tions, an overview of corrective action, and a collectiv:. evaluation of the deviations are also within the scope of the ERC program.

Pertinent to the SRP are the quality instructions (QIs), listed below, developed by ERC to address the construction adequacy of safety-related piping systems:

QI-19 Reinspection of Small Bore Pipe Supports QI-21 Reinspection of Piping System Bolted Joint / Materials g

QI-25 Reinspection of Large Bore Piping Configur,ation m

QI-20 Reinspection of Small Bore Piping Configuration QI-27 Reinspection of Large Bore Pipe Supports - Rigid

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QI-29 Reinspection of Large Bore Pipe Supports - Nonrigid E

QI-43 Reinspection of Concrete Placement QI-49 Reinspection of Large Bore Piping - Welds / Materials i

QI-51 Reinspection of Pipe Whip Restraints l

I Checklists were developed by ERC in accordance with the procedure for Preparation of Checklists and Data Base Reports (Comanche Project Proce-I dure CPP-7) to identify the attributes to be inspected.

The list of at-i tributes and corresponding QI is prepared by the responsible ERC QA/QC discipline and reviewed and approved by the Lead Discipline Engineer and j

the QA/QC. Engineering Supervisor.

Inspections are then performed by per-sonnel certified to Level II or III in accordance with American National i

Standards Institute (ANSI) N45.2.6, Qualifications of Inspection, Exami-nation and Testing Personnel for the Construction Phase of Nuclear Power Plants; United States Nuclear Regulatory Commission Regulatory Guide 1.58, Qualification cf Nuclear Power Plant Inspection, Examination 3

and Testing Personnel

• and additional requirements set forth in the ERC I

8 procedure for Indoctrination, : Training and Certification of Personnel (CPP-3).

The inspections are based on a sampling plan described in detail in Appendix D of the CPRT Program Plan.

Items not in confstmance are re-corded on Deviation Reports (DRs).

The DRs are evaluated by the ERC's Safety Significance Evaluation Group for safety-significance in accor-dance with the ERC procedure for Safety-Significant Evaluations of Devia-1 tion Reports (CPP-16).

Any item determined to have a potential safety-significant impact results in expanding the inspect 2on sample potentially up to a 100-percent effort for,the affected attribute.

Other pertinent procedures applicable to the ERC program include the following-CPP Preparation of Project Procedures and Quality Instructions CP? Establishing Population CPP Sample Selection 1074-15454-HC4 6

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CPP Evaluations of Adverse Trend Analysis, Safety-Significant Deficiencies, and QA/QC Program Deficiencies CPP Collective Evaluation of the Quality of Construction CPP Collective Evaluation of Construction QA/QC Program j

CPP CPSES Project Corrective Action 1

All DRs are also forwarded to TUGC0 QA in accordance with CPP-10 (Prepa-f.

ration of DRs) for generation of an NCR, if applicable.

5.4

SUMMARY

OF EXISTING PROGRAMS As discussed in further detail in Section 6.0, the attributes applicable j

to the SRP are being addressed by TUGCO, ERC, or SWEC; however, each or-g ganization has different purposes when reviewing the attributes as shown

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by the following:

1.

TUGC0 Normal Inspection process - performed by Brown & Root Quality Control personnel to meet the requirements of 10CFR50, Appendix B, and the ASME III Code.

2.

TUGC0 As-Built Program performed to supplement the normal j

I inspection process and to meet certain requirements of IE Bulletin 79-14.

3.

TUGC0 Specific Quality Control Backfit Type Inspections per-formed due to design changes or generic corrective action programs.

4.

ERC Program performed to determine the quality of construction.

5.

SWEC CPPP-5 Walkdowns - performed to assess the adequacy of key field inputs to the SRP.

6.

SWEC CPPP-8 Walkdown performed to determine the adequacy of the SRP procedures.

f In general, the TUGC0 normal inspection process was supplemented in part by the TUGC0 as-built program.

More recently, ERC sample inspections were also performed to. determine the quality of construction.

The SWEC sample inspections are also recent efforts which were performed to deter-mine the adequacy of the requirements of the SRP procedures.

4 The interface and flow of work between the three organizations, shown in Figure 1, can be divided into six categories:

1.

Initial information developed by TUGC0 which is provided to SWEC and ERC.

2.

Sample inspections by SWEC and ERC.

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Evaluations and recommendations by SWEC and ERC (identification of individual deviations and generic concerns).

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Corrective action by TUGC0 (disposition of individual

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deviations and resolution of generic concerns).

5.

Revision of documents by TUGC0 and transmittal to SWEC for the a

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SRP.

1 6.

Completion of the SRP by SWEC.

The required documents are obtained from TUGC0 by SWEC and ERC for their verification programs.

These documents are also used by SWEC for the

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SRP.

SWEC and ERC use sample techniques to evaluate the TUGC0 documents.

3.

ERC identified deviations are evaluated by ERC for safety significance and adverse trends and, if necessary, are also forwarded to TUGC0 for

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generic corrective action.

SWEC deviations are evaluated by SWEC for 1

impact on the SRP.

SWEC generic concerns are addressed by revising the SRP procedures or by TUGC0 generic corrective action.

All ERC and SWEC individual deviations are forwarded to TUGC0 to initiate an NCR.

1, All TUGC0 NCRs related to safety-related piping systems and dispositioned "use-as-is" are distributed to SWEC and incorporated into the as-built documents to ensure that they are included in the SRP.

Figure 2 shows the interface between ERC and SWEC inspections and evalua-tions and. TUGC0 corrective action in more detail.

Note that Figure 2 includes proposed programs recommended in Section 8.0.

6.0 DISCUSSION A discussion of the attributes and the adequacy of various programs and procedures is presented in this section.

In cases where the final con-1 g

clusions of the ERC sample inspection programs and SWEC walkdown efforts a

have not been completed, the adequacy as discussed in this report is assessed based on draft reports and in process data.

In cases where ERC or SWEC concerns already have been identified, TUGC0 corrective action is addressed as future work even though all or part may be in progress or complete.

6.1 ADEQUACY OF ATTRIBUTES 6.1.1 Adequacy of Attributes Included in the TUGC0 As-Built Program As shown 'in Table 2, the original TUGC0 As-Built Program (described in Section 5.1) addressed several attributes.

Table 2 also identifies the ERC and SWEC procedures that inspect the attributes and the procedures which have currently identified any generic concerns.

Support location and support function are attributes which were included in both the ERC and SWEC CPPP-5 programs.

Pipe run geometry was indi-rectly included by virtue of checking support locations.

No generic con-cerns that could result in TUGC0 generic corrective action have been identified to date.

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Support design was included in the ERC rrogram and the SWEC CPPP-8 pro-gram for general configuration. Although deviations have been identified by both programs, it does not appear that this will result in a generic concern that requires TUGC0 generic corrective action.

'I Although clearance between piping and supports (gaps) was included in the ERC and SWEC CPPP-8 programs, the specified tolerances have been revised as part of the SRP.

The adequacy of this attribute will be addressed by TUGC0 generic corrective action.

Valve identification ar.d orientation were included in the ERC program and

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SWEC CPPP-5 program.

No generic concern has been identified for the het valve identification; however, the orientation has been identified as ayp

/gt generic concern which requires a TUGC0 100-percent reinspection.

This is j

also the c'ase for support orientation.

g Clearances between piping and sleeves were included in the ERC and SWEC CPPP-8 programs; however, the ERC program only addressed this as a general clearance attribute. Sleeve clearance and type were not included as specific attributes.

The CPPP-8 program did identify this to be a g

I generic concern.

As a result, all safety-related piping penetrations fM.09 (including fire walls) will require TUGC0 generic corrective action for Y 6

clearance and type of seal.

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In general, there are generic concerns regarding specific attribites cussed in. Section 6.3, Corrective Action) and generic corrective action [p included in the TUGC0 As-Built Program.

A root cause evaluation (dis-l 3*

7,2 are necessary to resolve the concerns.

6.1.2 Adequacy of.Other Attributes As shown in Table 2, TUGC0 also utilized the normal inspection process to address attributes related to the SRP.

The ERC and SWEC procedures which g

inspected the attribute and the procedures which have identified any 3

generic concerns also are tabulated.

Some examples follow.

Embedments were included in the ERC program.

Since they are not within the scope of the SRP, they were excluded from the SWEC programs.

No ge-neric concerns have been identified by ERC to date; however, while con-ducting a third-party design assessment, CYGNA Engineering Services determined that the normal inspection requirements were incomplete.

Spe-cifically, the minimum separation requirements for welded attachments to embedded plates and the minimum spacing criteria becween loaded Richmond g

inserts and embedded plates were not specified.

These requirements were hg not included in the ERC program.

Generic corre'ctive action by TUGCO is therefore necessary.

Pipe attachments were included in the ERC and SWEC CPPP-8 programs. No generic concerns have been identified.

Valve weights were reviewed as part of the SWEC CPPP-8 program.

Since this attribute is not really related to the quality of construction, it was not included in the ERC program.

The SWEC CPPP-8 program identified n

1074-15454-HC4 9

I a concern regarding the documentation of additional mass as a result of 5

remote operators.

TUGC0 corrective action is necessary.

As listed in Table 2, other attributes related to safety-related piping I

systems were assessed.

The majority of these attributes were addressed by TUGC0 as part of the normal inspection process.

Table 2 also shows the ERC and SWEC programs that address the attribute.

Included also are the programs which have identified concerns to date (e.g.,

expansion joints, tie-back support location, Class 5 continuations, insulation, clamp and support orientation, at.d loose, missing, or damaged hardware).

6.1.3 Summary of Attributes I

In general, the verification of each attribute falls into one of the fol-I lowing categories:

1.

The attribute was originally included in a TUGC0 inspection I

program (normal or as-built) and is verified in both the ERC and SWEC programs.

g 2.

The attribute was originally included in a TUGC0 inspection JWI

. program and is verified in either the ERC program or the SWEC program.

3.

The attribute was not originally included in a TUGC0 inspection program and is verified as part of TUGC0 generic corrective action.

8 3 the first two cases, the SWEC aed/or the ERC programs identify any individual deviation or generic con'cerns to TUGC0 for corrective action.

8 In the third case, missed attributes (i.e., embedments) are identified as part of design adequacy reviews which are conducted by SWEC and other organizations.

These attributes are identified to TUGC0 for generic cor-rective action.

Also, the adequacy of er.ch attribute falls into one of the following:

1.

The SWEC and/or ERC program (s) identified no deviations.

2.

The SWEC and/or ERC program (s) identified deviations which require disposition on an NCR but which do not require generic corrective action.

g 3.

SWEC and/or ERC and/'

other organizations identified devia-M tions and concerns aich require disposition on an NCR and s

which also require generic corrective action.

In summary, there are programs in place to ensure that all attributes related to the SRP, including those identified in IE Bulletin 79-14, are included in a verification program and evaluated for adequacy.

The ade-quacy of the SWEC and ERC evaluation process and TUGC0 corrective action process is discussed in the following sections.

N 1074-15454,-HC4 10 i-

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6.2 ADEQUACY OF EVALUATION PROCESS Each individual deviation is dispositioned as part of the NCR program.

j The NCR process ensures that the particular deviation is corrected either l

i by rework or by technical justification to use-as-is.

Although the pro-cess also includes an evaluation for potential reportability under 10CFR50.55(e), it is unlikely that any one deviation considered by itself would be reportable.

More important is the cumulation of similar devia'-

i tions which could result in a generic concern. An evaluation for poten-i tial reportability of a generic conern is addressed in Section 6.3 as part of corrective action.

The adequacy of the process by which toe 1

deviations are considered together is discussed in this section.

j 1

g The ERC program is designed to verify the adequacy as described in detail l

I 4

in the Comanche Peak Response Team Program.

This program has been evalu-ated by the NRC (Safety Evaluation Report for CPSES, NUREG-0797,

)

Supplement 13).

The Staff concluded that the program provides an overall I~

structure for addressing all existing and future issues and, if properly implemented, will provide important evidence of the construction quality of CPSES and will identify any needed corrective action. The Staff also identified items to be addressed during the implementat, ion phase.

The quality of construction of piping and pipe supports is therefore ad-j I

dressed under the ERC program for those attributn 'n the program.

As i

such, ERC is considered to be adequately verifyicg the as-built informa-tion being used by SWEC in the SRP.

For those attributes not addressed in the ERC program, other programs are verifying their adequacy.

I The SWEC CPPP-5 and 8 walkdowns address all field attributes that affect i

the adequacy of the SRP (embedments are not in the SRP scope). Although the SWEC deviations are not formally evaluated for trends, generic impli-cations, and safety significance similar to the ERC deviations, SWEC does assess the deviations for generic impact on the SRP.

Due to the nature E

of the SWEC programs, the assessment for impact on the SRP is essentially equivalent to a detailed trending, generic implication, and safety-significant evaluation.

Specifically, the SWEC program does require that generic concerns which could impact the SRP are either corrected by TUGC0 8

or corrected by refining or modifying the SRP procedures.

Since trending, generic implications, and safety significance for safety-related piping systems are being performed by ERC for construction quali-ty and by SWEC for design adequacy, there is no need for TUGC.0 to repeat i

these efforts.

It should be noted that this applies only to reinspec-t i

tions of work previously completed.

For ongoing construction and current in process' inspections, TUGCO does have a program for trending, generic l

implications, and safety significance.

This ensures that current trends I

are not improperly influenced by past trends.

ability and dispositioned rework or use-as-is.

The process by whf ch In summary, each individual deviation is reviewed for potential report-individual deviations are evaluated is therefore considered adequate.

3 The process by which deviations are evaluated for trends and generic implications is considered adequate based on acceptance of the ERC pro-gram by the NRC Staff and further supplemented by the SWEC pro 8 ram.

I 1074-15454-HC4 11

I

However, the effectiveness can be improved as described in Recommendations 8.3 and 8.4.

Recommendation 8.3 suggests that SWEC also review the ERC DRs for impact on the SRP.

Recommendation 8.4 suggests that ERC review the SWEC walkdown results to supplement ERC's collective evaluation.

.6. 3 ADEQUACY OF CORRECTIVE ACTION Corrective action is addressed by TUGC0 utilizing two main processes, NCRs and CARS.

As stated above, the NCR proc,ess ensures that each in-dividual deviation is processed to determine whether the deviation is valid.

If the deviation is. valid, an NCR is initiated and a determina-tiou is made as to whether the At4. should be reworked or used as is.

g Siace SWEC evaluates all NCRs associated with safety-related piping 4

systems, and the NCRs are 'further incorporated into the as-built docu-ments, all valid individual deviations related to safety-related piping systems are considered in the SRP.

'1he corrective action report (CAR) is utilized by TUGC0 to address the generic concerns identified by SWEC, ERC, or any other organization.

This program ensures the concern is evaluated for extent, root cause, corrective action, and potential reportability under 10CFR50.55e.

The CAR also is utilized to track the corrective action to closure.

Both ERC and SWEC identify generic concerns to TUGC0 through independent programs.

SWEC generic concerns are initially addressed through TUGCO Engineering, while ERC generic concerns are addressed through TUGC0 Quality Control (QC).

Although TUGC0 QC and Engineering do interface, the process should be better defined to avoid a duplication of efforts.

E Recommendations 8.1 and 8.2 suggest that TUGC0 develop two types of pro-grams to organize any generic corrective action which deals with verifi-cation of specific attributes.

A hardware validation program g

(HVP - Section 8.1) would address items such as loose, missing, damaged, M

or misaligned hardware.

A supplemental verification program (SVP - Sec-seal require-@.7pg./w/F5 tion 8.2) wenil d address other items such as penetration fie-back suppo rtF, and insulation thickness.

The distinction

, )ments.

b ween the two is that the HVP is geared towards tightening, replacing, f or reworking the hardwarc so that there is no change to the as-built AtpeD drawings, while the SVP is geared towards documenting changes to the cur-

)

.fo ydj rent requirements that could affect the SRP.

The two programs could di-71 rectly refer to the NCR.and CAR procedures to ensure that all TUGC0 3

corrective action is appropriately addressed.

In summary,

.a process by which each individual deviation identified by SWEC or ERC.s corrected is adequate. The process by which generic cor-rective action is addressed should be improved so that it will be bet-ter organized and efforts will not be duplicated.

q LJ.

g i

La 1074-15454-HC4 12

t I

7.0 CONCLUSION

S The assessment identified the following:

There are existing procedures to ensure that all attributes identified in IE Bulletin 79-14 are verified.

The assessment further identified that there are existing procedures to ensure that other design inputs related to the SRP are verified.

There are programs in place to ensure that adverse as-built conditions will be identified and corrected; however, some im-provements should be implemented.

Programmatic interfaces shotild be modified to improve communi-(

I cation between the involved organizations.

1 1

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8.0 RECOMfENDATIONS Figures 1 and 2 show the existing and recommended programs in flow chart form.

i 8.1 REC 0&fENDATIONS REGARDING HARDWARE-RELATED CONCERNS ERC and SWEC have and are in the process of identifying hardware-related concerns which normally will require rework to the specified requirements and have no impact on the SRP.

Items such as missing cotter pins, loose r"?

jam nuts, damaged components, misaligned struts or snubbers, and nonpar-l_1 allel clamp ears are examples.

These items should be grouped into a sin-gle verification program entitled hardware validation program (HVP) to improve the corrective action process.

The following additional recom-mendations would then apply:

1.

TUGC0 should define the scope and establish the HVP program, i',I since all concerns are identified to TUGCO.

U 2.

Since the MVP will close ERC issues, ERC is required by program M

(CPP 1) to review the applicable HVP procedure and results.

L1 SVEC should also review the HVP procedure to ensure that SWEC concerns are adequately addressed.

&7 U

3.

The procedure should directly reference the procedures for cor-rective action and potential reportability addressad further in Recommendr. ion 8.6.

This will avoid duplication o:i efferts and organize the process.

4.

Operations personnel should be involved to facilitate the tran-sition from a final as-built system to an operating system.

In addition, programs should be verified to be effective to ensure maintainability of as-built configurations.

Modification of L(

Procedures STA-802-5, Final Acceptance of Station Systems and Equipment, and STA-804-2, Control of Station Areas, should be considered to implement or interface with the HVP.

S.

Scheduling of the HVP should consider the completion of modifi-cations as a result of the SRP.

6.

The HVP should be developed such that components can be cot rected without having to generate individual NCRs.

However, a system to. identify corrected items should be provided.

The followup report should include a quantitative historical record.

analysis for N

8.2 RECOMMENDATIONS REGARDING OTHER CONCERNS ERC an'd SVEC have and are in the process of identifying other concerns which may or may not require rework to the specified requirements and therefore may affect the SRP.

Items such as penetration type and clear-ance, fire wall clearance, insulation thickness and stand-off dimensions, tie-back

supports, valve orientation, certain Class 5 continuation piping, embedments, and expansion joints are examples.

Those items i

1074-15454-HC4 14

i -

'g evaluated by TUGC0 to require a field verification should be grouped into 5

a single program called the supplemental verification program (SVP) to improve the corrective action process.

The following additional recom-mendations would then apply:

1.

TUGC0 should define the scope and establish the SVP program, since all concerns are identified to TUGCO.

2.

Since the SVP will close ERC issues, ERC is required by program to review the applicable SVP procedure (s) and results.

SWEC should also review the SVP procedure (s) to ensure that SWEC concerns are adequately addressed.

l 3.

The procedure (s) should directly reference the procedures for corrective action and potential reportability addressed further in Recommendation 8.6.

This will avoid duplication of efforts and organize the process.

4.

Completion of the SVP and subsequent action should be expedited to minimize potential impacts to the SRP.

5.

An accounting system to identify the corrected items should be provided for historical record.

6.

The Protection and Analysis Group should participate in the resolution of penetration /siceve concerns, since they have pri-1 mary responsibility for the seals.

7.

Resolution of concerns regarding embedments should consider identification of spacing violations ' and overloaded conditions as an initial objective.

Since pipe supports may have to be modified to qualify the embedment, it is advantageous to iden-j tify these cases as early as possible.

8.3 RECOMMENDATIONS REGARDING REVIEW OF ERC DRs FOR IMPACT ON THE SRP SWEC should review the ERC DRs related to safety-related piping systems to ensure that they are evaluated for potential impact on the SRP.

This evaluation should be done to ensure that any potentially ganeric items identified and evaluated to determine whether corrective action is are required.

8.4 RECOMMENDATIONS REGARDING ERC REVIEW OF SWEC WALKDOWN RESULTS ERC should review SWEC walkdown procedures and results to ensure that relevant information is utilized.

Additionally, SWEC walkdowns may iden-(

tify cases where TUGCO/SWEC have already evaluated or corrected a speci-fic concern that overlaps an ERC concern.

8.5 RECOMMENDATIONS REGARDING DISTRIBUTION OF SWEC/ERC RESULTS SWEC should provide ERC the walkdown reports.

Conversely, ERC should provide the piping and pipe support DRs to SWEC.

1074-15454-HC4 15

\\

8.6 RECOMMENDATIONS RfGARDING ROOT CAUSE AND 10CFR50.55(e) EVALUATIONS The root cause of the ERC/SWEC concerns should be addressed prior to ini-tiating the HVP and SVP to prevent recurrence of the concern.

Potential I

10CFR50.55(e) evaluations should be grouped such that all deviations due to the same root cause are addressed once.

This will provide for more meaningful preventive action and more efficient corrective action.

For g

example, the evaluation of an insulation concern for root cause should

'A consider the following:

j 1.

Adequacy of original inspections E

2.

Adequacy of original criteria, such as minimum and maximum thickness requirements 3.

Adequacy of QC inspection plan J

E 4.

Requirements to identify changes to the responsible stress analysis organization g

After determining that one or more of these items represent the root 5

cause, appropriate action can be taken to prevent recurrence of the concern.

Corrective action should also consider that it may be ex-pedient and less costly to proceed directly to a 100 percent E

verification.

8.7 RECOMMENDATIONS REGARDING PLANNING A single TUGC0 focal point (individual) should be responsible for moni-toring all activities associated with completing the safety-related pip-ing systems.

The task should include the following:

1.

Comprehensive scheduling of the SVP, HVP, and ongoing modifica-tions or rework 2.

NCR generation and disposition 3.

Design change generation and disposition 4.

Drawing updates and issue of revisions I

R i

8

\\

1 M -15454-HC4 16

E

9.0 REFERENCES

NRC IE Bulletin 79-14, Seismic Analysis for As-built Safety-Related Pip-ing Systems E

TUGC0 Internal Guidelines for As-built Verification - Unit 1, Reverifica-tion of Strut, Snubber, Spring and Valve Orientatio' ; Subsequent As-built n

Review; NCR/DN Tracking and Closure

~~

TNE-AD-5-2, Processing Non-Conformance Results TNE-DC-7-3, Preparation of Design Drawing by TSMD R

TNE-DC-24-1, Program for As-built Piping Verification TNE-DC-25, Control of Activities for the PSE HFT Results Groups CP-EI-2.2-1, Valve Weighing Program CP-EI-4.0-39, Performance Instruction for PSI HFT Design Change Control Group CP-EI-4.5-1,. General Program for As-built Piping Verification CP-QAP-16.1, Control of Non-Conforming Items I

CP-QP-16.3, Processing CPRT Deviation Reports /Out of Scope Observation CP-QP-17.0, Corrective Action STA-802-5, Final Acceptance of Station Systems and Equipment STA-804-2, Control of Station Areas NED-CS-1, Evaluation of the Reporting of Items / Events under 40CFR27 and 10CFR50.55(e)

I CPP-001 through 023, Comanche Peak Response Team QA/QC Review Team Project Procedure CPPP-5, Comanche Peak Project Procedure for Field Walkdown - Unit 1 CPPP-6, Comanche Peak Project Procedure for Pipe Stress / Support Requal-ification Effort - Unit 1 CPPP-7, Comanche Peak Project Procedure for Design Criteria for Pipe

{

E Stress and Pipe Supports j

l CPPP-8, Comanche Peak Project Procedure for Piping and Support System j

Engineering Walkdown - Unit 1 CPPP-18, Comanche Peak Project Procedure for the Evaluation by SWEC of Deviation Reports Generated by the ERC i

Specification No. 2323-SS-30, Structural Embedments Specification No. 2323-MS-21, Valve Extension Stems Specification No. 2323-MS-46A, Nuclear Safety Class Pipe Hangers and Supports i

Specification No. 2323-HS-100, Piping Erection j

R Specification No. 2323-MS-200, Design Specification for all ASME III Code, Class 2 and 3 Piping

{

h 1074-15454-HC4 17

QI-019, Reinspection of Small Bore Pipe Supports QI-021, Reinspection of Piping System Bolted Joints / Material QI-025, Reinspection of Large Bore Piping Configuration QI-026, Reinspection of Small Bore Piping Configuration QI-027, Inspection Procedures for Large Bore Pipe Supports - Rigid QI-029, Inspection Procedures for Large Bore Pipe Supports - Non-Rigid QI-043, Reinspection of Concrete Placement R

QI-049, Reinspection of Large Bore Piping.- Welds / Material QI-051, Reinspection of Pipe Whip Restraints TUGC0 Letter No. TXX-3597 (to NRC),

IE Bulletin 79-14, dated December 3, 1982 E

TUGC0 Letter No. TXX-4729 (to NRC), Status of As-built Verification Program, dated April 6, 1986 NUREG-0797, Supplement No. 13, Safety Evaluation Report Related to the I

Operation of Comanche Peak Steam and Electric Station, Units 1 and 2 (Docket Nos. 50-445 and 50-446) dated May 1986 a

I E

E 8

8 8

W a

1074-15454-HC4 18

l 8 l

j TABLE 1 ATTRIBUTES 1.

-Pipe run geometry is shown on Brown & Root Piping Drawings (BRP).

2.

Support design is shown on support hanger drawings (BRH).

l E

3.

Support location is shown on large and small bore hanger location drawings (BRHLs and GHHs).

4.

Support function is shown on BRHs.

yg 5.

Support clearances / gaps are shown on BRHs.

4 l

6.

Embedments are shown on structural drawings.

7.

Pipe attachments are shown on BRPs.

8.

Valve and Valve Operator Location j

5 a.

Identification is shown on BRPs.

b.

Orientation is shown on BRPs.

9.

Valve and valve operator weights are controlled by the valve list.

l 1

10.

Clearance between pipe and sleeves are shown on BRPs.

Fire walls are shown on structural drawings, and penetrations are shown on the penetration schedule.

11.

Component type and identification (valves, strainers, expansion joints, flanges, reducers, flex hoses) are shown on BRPs.

12.

Bends / elbows (standard, short radius, 5D, etc) are shown on BRPs.

13.

Branch connection types (ANSI tee, unreinforced tee, reinforced tee, sockolet, weldolet, boss, coupling, half coupling, swagelock) are shown on BRPs.

14.

Branches / intersections (small bore, veuts and drains, instrumenta-tion taps) are shown on BRPs.

15.

Equipment locations and identification are shown on BRPs.

16.

Material type / size / class (including substitutions and specification violations) are shown on BRPs and specification NCRs.

17.

Tie-back supports are shown on small bore hanger drawings (BRHs) and small bore hanger location drawings (GHHs).

18.

Identifications and type of supports are shown on BRHs.

19.

Support welds are shown on BRHs.

1074-15454-HC4 1

.g

20.

Base plates are shown on BRHs.

21.

Integral /nonintegral attachments to pipe are shown on BRHs, except for those abandoned which are shown on the BRPs.

22.

Attachments to support structures are shown on BRHs.

23.

Bill of materials is shown on BRHs.

24.

Class.5 piping installation analyzed with Class 1, 2, and 3 piping is shown on BRHs, BRHLs, and GHHs.

25.

Insulation thickness and type is shown on the LDL.

26. Whip restraints / moment restraints are shown on structural drawings and Brown & Root installation drawings.

27.

Support / clamp orientation is sh'own on BRHs.

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l

ATTACHMENT 1 ACTION PLAN 1.

List all 3ttributes required to fulfill the requirements of NRC IE Bulletin 79-14 and Supplements.

2.

Identify attributes covered under TUGC0 IE Bulletin 79-14 walkdown program which are to include, but not be limited to, the following:

8 a.

Procedures used for project (copy of each, plus description).

b.

Report (s) of original effort.

Final documents resulting from TUGC0 program.

c.

d.

Procedures to ensure that the documentation is kept up to date.

1)

Examples from current SWEC effort.

2)

. Include discussion of how current modifications are controlled / verified.

3.

Verify that attributes required by Item 1 abcre are included in pro-I gram.

If not all-inclusive, discush action taken to

• verify /coglete.

8, Describe the ERC process associated with Issue-Specific Action Plan 4.

VII.c (Construction Reinspection /Decumentation Review Plan).

De-scription is to include, but not be limited to, the following:

a.

List procedures associated with IE Bulletin 79-14 attributes and process directives associated with pipe stress, pipe sup-

ports, piping configuration, and ' concrete population, if_

applicable.

b.

Identify the attributes in the ERC program that are applicable to the SWEC Stress Requalification Program (SRP).

c.

Describe ERC DR program, root cause/ generic implication, and trend analysis.

d.

Determine whether ERC should provide a copy of all DRs associ-ated with the SRP to SWEC.

H e.

Determine whetber ERC, as part of the program, should analyze all DRs that are associated with SWEC.

f.

Compare ERC an'd IE Bulletin 79-14 required attributes.

g.

Determine whether ERC should change / develop a procedure (for-malize process) for d. above.

k g

1 g

e 5.

Describe the SWEC (SRP) Discipline-Specific Action Plan (DSAP IX).

Description is to include, but not be limited to, the fe:; aing:

E a.

List procedures associated with IE Bulletin 79-14 attributes and process directives 'related to pipe stress, pipe supports, and piping configuration.

I b.

Identify all attributes (documents):

1)

That are associated with pipe stress.

2)

That are associated with pipe supports.

c.

Identify what attributes SWEC is using for the SRP.

1)

Identify sources of the above documents.

O Evaluate adequtcy of the above information.

d.

Evaluate document control procedure for TUGCO.

1)

Determine whether ERC is looking at this under a separate ERC Action Plan and review the preliminary results.

I 2)

Evaluate whether the /locuments being sent to SWEC are

]

current.

i e.

Describe walkdowns conducted by SWEC (SRP), to include:

1)

CPPP-5 (2) l 2)

CPPP-8 (1) 3)

CPPP-6 (to be done) 4nd results and implications for :s-built data from these walkdowns.

i f.

Determine if a formalized program should be developed by SWEC to evaluate all DRs received from ERC and NCRs from TUGCO.

j 1)

Include consideration of generic implication, a trend analysis program, and SWEC's need to develop a procedure.

6.

Compare attributes of ERC and SWEC programs to ensure that all at-tributes associated with the SRP are examined.

If not all covered, identify verification program to examine.

7.

Describe the overall integration of the TUGCO, ERC, and SWEC pro-grams associated with the piping and pipe support stress program.

Description is to include, but not be limited to, the following:

a.

All SWEC walkdowns.

What has TUGC0 done as a result of' the walkdown data?

(l 1

i 1074-15454-HC4 s

s 3

b

\\

t e

l t

j Enclosure B NE-8303, " Design Basis Document Index" May 22, 1987 O

e

r[

l

!"!1UELECTRIC Generating Division OFFICEMEMORANDUM NE-8303 To:

Distribution May 22, 1987 C0HANCHE PEAK STEAM ELECTRIC STATION DESIGN BASIS DOCUMENT INDEX l

Please find attached the latest Design Basis Document Index.

Please note I

that revie.;G ro estimated completion dates should be avoided and one should

)

make their best effort to meet the comn itment dates.

4 You are requested to provide updating / missing information to the CPE Projects-Department, attention Mr. B. K. Bhujang, by the 10th of June, 1987.

"l

0. W. Lowe 1

BKB:kr Attachment cc ARMS OL, lA I

f f

Distribution:

R. W. Ackley lL, lA - SWEC d

J. S. Carty lL, lA - SWEC (Boston)

MAy 22 Jgg7 H. J. Cheatheam 1L, lA - Conf. Mgmt.

C. G. Creamer IL, lA "T N E G. U. Deen lL, lA - SWEC (C/S)

EkMNEDHNG SUPPORT 690gp S. L. Ellis lL, lA - Results J. C. Finneran IL, lA R. L. Grubb IL, lA - Impell Kathy Handerhan lL, lA - 1[ Pittsburgh C. R. Hooton IL. lA A.

Husain IL, lA - Dallas R. C.

Iotti lL, lA - EBASCO R. T. Jenkins IL, lA R. P. Klause lL, lA - SWEC - PSE C. R. Levine IL, IA - EBASCO D. A. Lowrie IL, lA F.

W. Madden IL, IA E. E. Margalejo lL, lA - EPM J. L. Martin IL, lA R. L. Moller lL, l A - 1[

J. W. Muffett 1L, lA Jim Narron IL, lA - EBASCO M. A. Niemeyer IL, lA - Ops. Training S. L. Stamm lL, lA - SWEC P.

B. Stevens IL, lA D.

R. Woodlan IL, lA - Dallas Licensing L. C. Yeager IL, lA

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N E.

M U

C.

O.

D..

S.

I T

T T

S S

N N

N A.

I E

E E

B S

M M

M N =

Y P

P P

L N.

O =

L I

I I

A G.

I

=

A U

U U

R I

T =

N Q

Q Q

U S.

C =

A E

E E.

E =

E T

=

C D.

S =

L L

L L

U A

A A

A R

n C

C C

C T

I I

I R

R I

S N

N N

A A

N

/

A A

A E

E A

L H

H H

L L

H I

C C

C C

C C

V E

E E

U U

E I

M M

M N

N M

C S =

S =

A =

I I

S L =

I I

I I

I W

I C =

M E

E T

T S

E N T

R O S

C I

N T T

O A O

N C U T

R E

L T

O M

R A N S T

E O V O I A

G F E I

L R

A E =

S E

N N

E N L =

I N

N A

O N O T

=

V O E

M I

I I

I

=

E I

G T

L T

] =

R T E

A R

E A

=

A L

T L

O D R D.

G R N E

S O

T A

B =

N O G S

A S

A UI P D =

I F

I E

W I

R G E T

S I

E S

N N E D

E T

N G

E O D V

N E

N T V

I Y

I E

G I

N T E C

T M

R E O

C N N

C N

E E M D

U I

E A

I N

E H A

R L G

D A

1 N C N

T E R

I T

8 I

A R

S P E

D N

R G T O

N I

M A

O U

N T T

I P

C R

C T

E A V =

E =

0 0

0 0

0 0

0 R =

2 9

0 1

2 3

4 5

6 0

1 1

1 1

1 1

1

. 7 0

o8 0

0 0

0 0

0 0

N /

E E

E E

E E

S 0

M e2

1. =

M M

M M

M C

g /

D =

D D

D D

D D

D D

a5 B =

B B

B B

B B

B B

P 0 D =

D D

D D

D D

D D

)i{

1IllI

)I.

,1

=

=

=

9 7 -

7 -

p 7.

T

=

9 8 -

8 -

8 8.

G -

C== 3

/

/ -

/ -

/.

/ -

/.

/.

/ -

7. /

2 - /

5 - /

3. /

- /

. /

7. /

5 - /

D = T 2.

1 1

0.

2.

2 -

C = C

/.

/ -

/ -

/.

/ -

/.

/.

/ -

E = A 0. /

6 - /

5 - /

6. /

. /

3. /

1

- /

=

1 0 -

0 -

0.

0.

1

=

=

=

=

=

7.

7 -

7 -

7 7.

7 -

=

8.

8 -

8 - 7 8

8.

8 -

2 = 2

/.

/ -

/ - 8

/

/ -

/.

/.

/ -

- = -

3. /

5 - /

0 - /

2. /

- /

. /

3. /

0 - /

D = T 1

1 1

- 0 2.

1 1

C = C

/

/ -

/ -

1

/

/ -

/

/.

/ -

E = A 0

/

5 - /

4 - /

5

/

- /

. /

3. /

1

- /

=

1 0 -

0 - 4 0.

0.

1

=

- 0

=

=

=

=

7.

7 -

7 -

7 -

7.

7 -

=

8.

8 - 7 8 -

. 7 8 - 7 8. 7 8 -

1

=

1

/

/. 8

/ -

/

8

/ - 8

/.

/. 8

/ -

- = -

1

/

2 - /

6 - /

/

6 - /.

. /

6. /

0 - /

D = T 0.

1

- 2 1

. 5 1

- 3 0. 0 3 -

C

= C

/

/ -

1

/ -

/. 2

/ - 2

/.

/.

1

/ - -

E = A 9

/

2 - /

3 - /

. /

3 - /

/

2. /

9 - /

=

0.

0 - 2 0 -

. 3 0 - 3 0. 2 0 -

=

- 0 0

- 0

. 0

=

2 E

TO N

)

CP S =

(

U =

T =

W A =

E D

T =

I E

S =

V 8

S E

U R

E T

T N

O O

I N

N Y =

E T =

S I

=

U L =

O I

=

H 8 =

G I

=

N X.

S =

I E.

N =

C C

T C

C D

O =

E E

E M

S E

E N

P =

W P

W P

E W

W I

S =

S C

S E

W S

S E =

T R =

N EMU CO.

D..

S.

S I

T T

N S.

N N

S O

A.

E E

I I

B M

M S

T N =

P P

L Y

A N

O =

I A

L C

G.

I

=

I U

R A

I U

I T =

Q Q

U N

L S

C =

E E

T A

P E.

E =

C P

D.

S =

L L

U L

A A

A R

A C

C T

C S

R I

I S

L E

R N

N

/

I O

T A

N A

A L

A R

U E

H H

I H

T P

L C

C V

C N

M C

^

E E

I E

O O

U M

M C

M C

C N

S =

S =

A =

S I

I L =

N I

I I

I I

I C =

NO D

I N

T A

N A

O C

S I

I T

S T

M N

F N

I C

E G

I E

S E

T I

L M S Y

T S

S A

E T L

O Y

E U

C N A

R S

D E =

Q A E N

P L =

L M A

G N

T

=

E P E D

N C

I

=

V S R N

N I

I T =

L I

I O

O C

W A

R T

=

A D U D =

S V

Q D

L T

E

~

B =

P L E T

O I

T D =

M L R U

R N

O U

A H

T O

R P

P W P S

N M

P

=

M A

O R

U Y G E

C N

N E

P R

F O

O S T

M A C A

R I

I E

A E A D

I S

O M T

T R W

V R N M T E A

A U D

I G

O S E

C T I

I T

E T O C

I R

A S D

D A E

C R E E I

E Y A

A E F

A P S S F

R S R

R F V =

E =

0 0

0 0

0 0

0 0

R =

3 7

8 9

0 1

2 3

4 1

1 1

2 2

2 2

2

. 7 0

o8 0

0 0

0 0

0 0

N /

E E

S E

E E

E 0

M e2

1. =

M C

M E

E M

g /

D =

D D

0 D

D D

D D

a 5 B =

B B

8 B

B B

B B

P 0 D =

D D

D D

D D

D D

u

? l" 7 s

s :

s :

s ;

i w.

e.

e.

e.

t-h.s 2:

> l s

s

.s l

R'.:

n s

s u.

m o

8-u s.

s s

s s.

s.

s s

9:

l 8:

8:

9:

l a

s.

s.

s.

s.

a m

~

e e

e s.

m a u s

e s

s s

m s

s s

.s 8 nl!,:.

C: 3 O! l 5: 8' R:

R:.'

R.:

8:

u s. -

s.

s.

s.

s s.

8: g 8:

8: 8' 8:

8: '

8: '

8:

i

~..

~

.. s

. 8 s.-

T T

8'.: R A:

'.: k

>: R R'.: R A.: R

> l R

~

-.s 8 :, -W 4:

o. ~

m.-

g.:

' : R A: R A: R A: R

> : R s

w s

o : 8 l

8

8

.8

8

5 M

M

.M

=

O N

E E

E W

w 8

A 6

M M

g-2 2

2 W

su

~!

8 8

5 W2 1

2-S" I

su a

-w 5

g g

o a "

w=

"8 8

g 2

=W 5

5 5

Ww i

f

>. n

==

l ll 2

a s

a 5

a

!l l

I I

l

']

u u

u 2:

w,

5 5

c c

W:

5 5

5 g.

5:

G:

D ll

• l W:

I 5

E E

E

=

Y Y

l 8

.Y Y

w w

w a

8 8

5 1

w w

w i

M.

M.

4.

==

d B

I w

wo o

g 5

_5 5

• s o

E g

w g.

5 5

5" 5

2 5

-n w

w y

-E 2

~

5 WE l";

9 w

9:

8 o

8-u w

1. w W~

a 3

5

• 9,

~

~

5

-3

=a E

5 w

w u

2 8

Gw

=

8 5

=5

-m a

9 2

50 C

.E "

?"

u.

W d

w

. n gg o

e o

o o

o o

e e

s e

o

~

l g

8 8

8 8

o.

8

~8 8

O CO E s.R E.

E.4 E.

Y t

?

?

w w

w w

=n

?A 8 ll 8

8 8

8 A

8 8

8

0. o o u o

o o

o gg, g;;

o o

=

=

P 9

P.

7 P.

P F.

G 8

S.

8.

8.

8 8

3 = 3

/

/

/.

/.

/.

/.

/.

/

- = -

0. /

8

/

0. /

. /

0. /

6

/

3. /

P. /

D = T 2.

2 2

2.

0 2

2.

C = C

/.

/

/

/

/

/

/

/

E = A 3

/

2

/

3. /

/

3

/

3

/

3

/

2

/

=

G 0

0 0.

0.

0 0.

=

=

=

=

=

7.

7.

7.

7.

7 7

7.

=

8.

8. 7 8

8 8

8. 7 8

7 2 = 2

/.

/

8

/

/

/

/

/

8

/

8

- = -

6. /

5

/

6

/

. /

6. /

0

/

9

/

3

/

D = T 0

1

. 5 0

0 2

0 1

1 8

C = O

/

/

2

/

/

/

/.

/

0

/. 0 E = A 3. /

2

/

3

/

/

3. /

2. /

3. /

2. /

=

0 0. 3 0.

0.

0.

0. 5 0. 5

=

0

. 0

. 0

=

=

=

=

7.

7 7

7 6.

6 6.

=

8. 7 8

7 8. 7 8

7 8. 7 8

7 8

7 1

=

1

/. 8

/

8

/. 8

/

/. 8

/

8

/

8

/

8

- = -

6. /

1

. /

1

. /

/

1

. /

0

/

4. /

7. /

D = T 1

7 3

9 3. 0 3. 0 1

9 2. 0 0. 2 C = C

/.

1

/

1

/

1

/.

/.

1

/

0

/. 3

/. 0 E = A 2

/

1

. /

1

/

. /

1

. /

2. /

2. /

2. /

=

0 2

0 1

0 2

0. 2 1

1 1

1 1

1

=

0 0

0

. 0

. 0

. 0 0

=

~

467 5

T T

T S =

F F

E F

U =

A A

N A

T =

R R

R A =

D D

D D

T

=

E S =

T T

S T

S S

U S

I I

I T

N N

O N

I I

M I

Y =

T

=

I

=

L =

I

=

B =

I

=

X.

S =

E.

N =

C C

C C

C C

C D

O =

E E

E E

E E

E N

P =

W W

W W

W W

W I

S =

S S

S S

S S

S E =

T R =

N.

E.

M.

U.

C.

OD N

N N

O O

O S.

I I

I I

T T

T S

A A

A A

T T

T B.

N N

N N =

E E

E N.

O =

M M

M G.

I

=

U U

U I

T

=

R R

R S

C =

T T

T E

E =

S S

S D

S =

N N

N L

L L

I I

I A

A A

S C

C C

S S

S L

I I

I S

S S

O R

R R

E E

E R

T T

T C

C C

T C

C C

O O

O N

E E

E R

R R

O L

L L

P P

P C

E E

E S =

S =

A =

S L =

I N

I I

I I

I C =

NG I

M S

G E

E N

T D

I N

S Y

R O

S E =

M O

I L =

O T

T M

E T =

O I

A E

M G

I

=

R N

L T

E A

T =

O L

S T

T

=

L M

A Y

S D =

O T

S Y

E B =

R L

S S

D =

T A

N R

N C

I E

R M

O I

W E

U C

G T

O W

I O

N S

D L

E i

P O

D P

E E

O M

k E

M L

R U

T E

I O

R l0 I

T V

A E

T P

S I

K T

T S

T F

S 9

E E

N E

F N

D M

I S

0 O

6 V =

E

=

0 0

0 0

0 0

0 0

R =

5 3

4 5

6 7

8 9

0 3

3 3

3 3

3 3

4

. 7 0

0 0

0 0

0 0

0 o8 N /

E E

E E

E E

E 0

E e2

1. =

E E

E E

E E

g /

D =

D D

D D

D D

D 0

a5 B =

B 8

B 8

B B

B 8

P 0 D =

D D

D D

D D

D

ll l

iliJ_

=

o

=

7 7.

7 P

=

8 8.

8.

8 3 = 3

/

/.

/

/

/.

/

/

/

- = -

2 - /

/

2

/

2

/

/

/

0

/

/

D -

T 0 -

0 0.

2 C = C

/ -

/.

/

/.

/.

/.

/.

/.

E = A 3 - /

. /.

3. /

3. /

/

. /

4

/

. /

=

0 -

0 0.

0

=

=

=

=

=

7 -

7 7

7

=

8 -

8 7

8 7

8.

2 = 2

/ -

/.

/

8

/

8

/.

/.

/

/.

m

- = -

6 - /

/

6

/

6

/

. /

. /

6

/

/

D = T 1

1 5

1

. 5 0.

C = C

/ -

/

/

0

/. 0

/

/

/

/.

E = A 2 - /

/

2. /

2

/

/

/

4

/

/

=

0 -

0. 5 0

5 0.

=

. 0

. 0

=

=

=

=

6 -

6 6.

=

8 - 7 8

7 8.

7.

7 7

7 8.

8 8

1

=

1

/ - 8

/

/. 8

/

8

/.

/

/.

/

- = -

7 - /

. /

7. /

2

/

. /

0

/

3. /

5

/

D T

1

- 5 1

. 5 2. 5 3

2.

1 C

C

/ - 0

/.

/. 0

/. 0

/

/

/.

/

E A

2 - /

/

2. /

2

/

. /

4

/

2

/

4

/

1 1

1 1

1 1

0 0

0

- 0 0

. 0

=

S =

U =

T =

A =

D T =

E S =

SU TO N

Y =

T

=

I

=

L =

I

=

B =

I

=

X.

S =

E N =

C C

C C

D O =

E E

E E

E E

E N.

P =

W W

W P

P W

P I

S =

S S

S C

C S

C E =

T.

R =

N.

E.

M.

U.

CO D

S.

I S.

AB N =

N.

0 =

G.

1

=

I T

=

S C =

E E =

D.

S =

L L

L s

L L

L A

A A

A A

A A

C C

C C

C C

C I

I I

I I

I I

R R

R R

R R

T T

T T

T T

T C

C C

C C

C C~

E E

E E

E E

E L

L L

L L

L L

E E

E E

E E

E S =

S =

A =

S 3

S S

L =

I I

I N

h N

N C =

M E

N T

O S

I Y

T S

C N

E O

Y T

I L

O T

P R

U P

P B

U I

S E

R Z

E =

T R

E L =

S W

E M

T =

I R

E~

1

=

D F

T T,

=

F'

=

E S

D Y

0 =

G E

N M

M S

8 =

A L

A E

E 0 =

T B

T T

N L

I G

S S

O O

T N

Y Y

I V

P I

S S

T U

M C

A W

R E

A Y

G C

O R

T R

T N

I L M E

S T

I I

N E

T Y

R T

J V T N

S U

N W

0 S I

A C

G W

8 Y N

C E

E I

W 4 S U

D N

S L

C C

V =

E =

0 0

0 0

0 0

0 R =

6 1

2 3

4 5

6 7

8 4

5 4

4 4

4 4

4

. 7 0

0 0

0 0

0 0

0 o8 N /

E E

E E

E E

E 0

E E

e2

1. =

E E

E E

E g /

D =

D 0

O D

D 0

D D

a5 B =

B 8

B B

B 8

B B

P 0 D =

G 0

O D

D D

D O

=

=

=

7.

7.

7 7 -

8.

7.

=

8.

8.

8 -

8 -

8 8.

3 o 3

/

/

/.

/

/ -

/ -

/

/

- m -

. /

/

3. /

3

/

6 - /

1

- /

6

/

0

/

D u T 2.

2 0 -

1 0.

3 C = C

/

/

/.

/

/ -

/ -

/

/

E = A

. /

. /

3. /

3. /

3 - /

3 - /

2

/

9. l

=

0 0.

0 -

0 -

0.

0.

=

=

=

=

=

7.

7.

7 -

7 -

8.

7

=

8 8.

8 -

8 -

8 8

2 = 2

/

/

/

/.

/ -

5 - /

9. /

4. /

/ -

/

/

- = -

/

/

9

/

9. /

0 - /

D = T 0

0 2 -

2 -

2.

1 C = C

/

/.

/.

/

/ -

/ -

/.

/

E = A

/

. /

3

/

3. /

2 - /

2 - /

1

. /

9

/

=

0 0

0 -

0 -

0 0

=

=

=

=

=

7.

6 7

7 -

7 -

7.

7.

=

8 8. 7 8. 7 8 - 7 8 - 7 8.

8 1

= 1

/.

/

/. 8

/. 8

/ - 8

/ - 8

/.

/

- = -

/

0

/

6. /

3. /

3 - /

3 - /

0. /

5. /

D = T 3

2. 0 2. 0 2 - 9 2 - 4 3.

2 C = C

/.

/.

/. 3

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h I

Y =

T =

I

=

L =

I

=

I

=

B n

=

X.

S =

E.

N =

~

C D.

O =

E E

E E

E N.

P =

P s

P P

W P

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C E

C C

S C

E =

T R =

N.

EM U.

C.

O S.

D I

p '.* A S.

B N =

L L

L L

N.

O =

A O

A A

G.

I

=

R R

R R

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U U

U U

S.

C =

T T

T T

E E =

C C

C C

D S =

U U

U U

R R

R R

T T

T T

S S

S S

/

/

/

/

M.

L L

L L

I I

I I

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V V

V V

S S

I I

I I

P P

C C

C C

S =

S =

A =

L =

I I

I I

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C =

SN C

N O

I G

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A N

S A

D N

W E

D N

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D N

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U ti F E R T I

H G

R E A S

P M

R U T R D

E =

P I

F C M N S

F A G

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U T

=

S S

U A E U S A D I

=

E N R R G E

S /

T =

G D

O T A

S S

)

=

N I

S P A M T R

I D =

I T

T R

A L O S 8 =

B R

A I

N T R A F S m

6 =

U O

G G C G N

(

T P

I Y

I E

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P T R S P R

I T

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S O E S P C S N N

S E G D

I A E E

V E E

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T N T R

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IC S E A D

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D E

S P P

I O

S N

T R I

S M D S P N

O I

O E E O N E M I

C S F S R C A D

I V =

E =

0 0

0 0

0 0

R =

2 1

9 0

1 2

3 4

5 6

8 9

9 9

9 9

9 9

. 7 0

o8 0

0 0

0 0

0 0

N /

S S

S S

S S

0 C

C g /

D =

D C

C C

C e2

1. =

0 D

D D

D D

D a 5 B =

B 8

8 B

B B

B 8

P 0 D =

D 0

D D

D D

D D

~

=

o

=

7 7.

7 -

F +

=

8 8

8 -

8 6

3 = 3

/

/

/

/ -

/ -

/

/

/

- = -

3. /

1

. /

/

1

- /

1

- /

. /

/

/

D = T 0.

0.

0 -

0 -

C = C

/.

/.

/

/ -

/ -

/

/

E = A 3. /

6. /

. /

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6 - /

/

. /.

/

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=

0 0.

0 -

0 -

=

=

=

=

=

7.

7.

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7 -

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=

8 7

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8 -

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2 = 2

/

8

/.

/

/ -

/ -

/

/

/

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6. /

5

/

/

5 - /

5 - /

/

/

2

/

D = T i

6 1

1 1

1 C = C

/

1

/.

/.

/ -

/ -

/

/.

/

E = A 2. /

5

/

/

5 - /

5 - /

. /

. /

6

/

=

0. 2 0

0 -

0 -

0.

=

0

=

=

=

=

7 7

7 -

7 -

7.

7 7

=

8. 7 8.

8 -

8 -

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8 8

1

=

1

/

8

/.

/.

/ -

/ -

/

/.

/.

- = -

0

/

9

/

/

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/

1

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D T

2. 6 2

1 2 -

0.

0.

1 C

C

/

0

/.

/.

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/.

/.

/.

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1

/

4

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/

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7

/

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0 1

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=

S =

R U =

D T =

I A =

D T

T

=

E F

S =

S A

U RD T

O N

N I

Y =

T =

C C

I

=

I I

L =

R R

I

=

T T

B =

C C

I

=

E E

L X.

S =

L L

L E.

N =

C E

E E

D.

O =

E E

E E

P N.

P =

W P

P P

U U

M I

S =

S C

C C

T T

I E =

T.

R =

N E

)

)

M.

S S

U.

A A

C.

L L

O.

L L

D.

A A

D D

S.

(

(

I S.

G G

S A.

N N

I B.

I I

S N =

L L

L L

R R

Y N

O =

A A

A A

E E

L G

=

R R

R R

E E

A I

TI

=

U U

U U

N N

N S

C =

T T

T T

I I

A E

E =

C C

C C

G G

D S =

U U

U U

N N

L R

R R

R E

E A

T T

T T

C S

S S

S R

R I

/

/

/

/

O O

N L

L L

L T

T A

I I

I I

C C

H V

V V

V A

A C

I I

I I

E E

E C

C C

C R

R M

S =

S =

A =

S S

S I

L =

I N

N N

I I

I C =

S E

K N

N I

A G

L B

N K

E T

I E

P C

V E

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A R

P S

D P

C I

P S

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W U

S Y

E =

1 N

A E

I L

M L =

/

A U

K S

A E

T =

L L

Q A

Y N

T I.

=

L P

S M

L A

S T =

I A

Y

=

F R

R R N N

T S

D =

K O

O O O A

N B =

C F

F F

I E

N D =

A T

T D

O B

S S

S A N

I I

I I

I T

E C

T I

S S

S S D

A C

A A R A

I E

Y B

B I

B P C

A T

R O

M C

C E

O N

N V N U A

O D

G G

G R G P L

E I

I E

I A

E T

S S S S D C

N R

A E

E E E N O

O I

C D

D R D A L

N F

V =

E =

0 0

0 0

0 0

0 R =

3 1

7 8

9 0

1 2

3 4

9 9

9 0

0 0

0 0

. 7 0

o8 0

0 1

1 1

1 1

N /

S S

S S

E E

E 0

C C

C e2

1. =

C N

N M

g /

D =

D D

D D

D 0

D D

a5 B =

B B

8 B

B 8

B B

P 0 D =

L D

D D

D D

D D

~

=

=

=

7 7

7 7.

7 7.

7

=

8.-

8 8.

8. 7 8.

8.

8 3 = 3

/

/ -

/ -

/

/

7 - /

8

/

0

/

/ - 8

/

/

- = -

/

9 - /

7. /

0

/

6

/

D = T 2 -

1 2.

0 2

2 1

3 C = C

/.

/ -

/

/

/

/

1

/

/

.- /

1

/

1

/

2. /

9. /

0

/

E = A

. /

5 - /

4

=

0 -

0 1

1 0 - 5 0

1

=

0

=

=

=

=

7 7.

7.

7.

7 7

=

8.

8. 7

. 6 8

8.

8 8

2 = 2

/.

/. 8

/ - 8

/

/.

/.

/.

/.

6. /

6. /

- /

9. /

5. /

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4

/

1

. /

- = -

D = T 0

1

- 6

. 0 0

2.

1 1

C = C

/

/

/ -

1

/

/.

/ -

/.

/

1 E = A 5

/

3

/

- /

0. /

9

/

/

8. /

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=

0.

0 - 3

- 2 1

0 0.

0

=

- 0 1

=

=

=

=

7.

7.

7 7.

7.

=

8. 7 8

8 8.

8 1

=

1

/

8

/ -

/ -

/

/

/ -

/.

/

- = -

1

/

- /

- /

8. /

4. /

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3. /

4

/

D = T 3

3 2.

2 0

2 C = C

/

0

/ -

/ -

/.

/

/ -

/

/.

E = A 1

. /

/

- /

8

/

7

/

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7. /

=

0 3

0 0

0.

0.

=

0

=

E O

V L

T T

D

)

A O

L V

N T

. W O

)

N

)

P A R

)

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C

)

R

(

P M

W S

W K

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A M

G C 2 A

R

(

2

(

(

N

(

I E

C T

E T

T T

E T

F T

F F

S =

& O W

F A

O A

A U =

N S

A R

N R

R T =

G R

D D

D A =

N S R

D

)

T =

I T

O 7 T

P T

T S =

V N F 3 D

S A

S S

L E N

I

/

1 1

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C 99 S

P N 1 H

W H

H E O E -

N E

M A R C S 3 I

2 G

(

E G

G Y =

T =

I

=

L =

I

=

=

B =

I

=

O X

S =

C E

N =

S D.

O =

A E

E E

E E

E E

N.

P =

S P

P P

P P

P P

I S =

E C

C C

C C

C C

E =

T R =

N EMU.

C.

O D

S.

I S.

A N

S S

S S

S S

S B.

N =

I E

E E

E E

E E

O M

M M

M M

M M

S O =

T T

T T

T T

T T

I

=

C S

S S

S S

S S

I T =

A Y

Y Y

Y Y

Y Y

S.

C =

R S

S S

S S

S S

E.

E u

E D.

S a T

L L

L L

L L

L N

A A

A A

A A

A I

C C

C C

C C

C I

I I

I I

I I

M N

N N

N N

N N

E A

A A

A A

A A

T H

H H

H H

H H

S C

C C

C C

C C

Y E

E E

E E

E E

S M

M M

M M

M M

S =

S =

1 A =

S S

S S

L =

I I

1 N

N I

N M

C =

PM S

U T

D CE M

F A

F E

M E

T E

S T

M D

M S

E N

D E

Y T

E =

A N

T S

S L =

A S

Y T =

N Y

R M

S l

=

O T

S E

E 1,

=

I A

M T

T R

=

T E

M E

M A

S E

D =

A H

E T

A W

Y T

B =

L E

T S

E D

S A

D =

U R

S Y

T E

W T

Y S

S E

N S

S F

I G

O M

E N

A N

P A

R T

O Y

R I

E E

A I

R D

T E

T T

S T

A A

L S M A

N C

I R

L I

E W

E A

L E

U S

N T D

D R

I T

C S

I S

E N

T X

A R

A Y E

O X

U E

I I

M S F

C E

A N

C M

V =

E =

0 0

A 0

O A

0 0

R =

4 1

5 2

3 4

'5 6

7 0

0 0

0 0

0 0

0 1

. 7 1

2 o8 2

2 2

2 2

2 N /

E E

E E

E E

E E

0 M

e2

1. =

M M

M M

M M

M g /

D =

D D

D D

D D

D D

a5 B =

3 B

B B

B S

B B

P 0 D =

D D

D D

D D

D D

=

=

=

7 7.

8.

7.

7 -

8.

8 8 -

=

0 8

8.

8.

8 -

8.

8 8 -

3 0 3

/

/

/.

/

/ -

/

/.

/ -

- o -

8 - /

5. /

5

/

1

/

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8

/

1

. /

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D = T 2 -

2.

0 3

1 1

0.

0 -

C = C

/ -

/

/.

/

/ -

/.

/.

/ -

E = A 8 - /

9

/

3

/

7. /

4 - /

3 f

4. /

3 - /

=

0.

0.

0 0.

0 -

0 0.

0 -

=

=

=

=

=

7.

7.

8 7.

7 -

8.

8.

8 -

=

8.

8 8

8.

8 - 7 8.

8.

8 -

2 = 2

/.

/

/.

/

/ - 8

/.

/.

/ -

- = -

7 - /

8. /

0

/

9

/

0 - /

5. /

9. /

0 - /

D = T 0 -

2.

?

1 3 - 6 0

1 2 -

C = C

/ -

/.

/.

/.

/ -

1

/

/

/ -

E = A 7 - /

8. /

T

. /

6

/

3

/

2. /

2

/

1

- /

=

0 -

0.

O 0

0 5

'i.

0 0 -

=

- 0

=

=

=

=

7 -

7.

7.

7 7 -

7 7.

7 -

=

8 -

8.

8.

8 8 - 7 8

8 8 -

1

=

1

/ -

/.

/.

/.

/. 8

/.

/

/ -

- = -

5. /

6. /

4

/

8. /

5 - /

8. /

1

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D = T 0 -

2 0

0.

1

. 3 0.

3.

0 -

C = C

/ -

/

/.

/.

/ - 2

/.

/.

/ -

E = A 6 - /

6 2. /

5

/

2 - /

2. /

2

/

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=

0 -

0 1

0 0 - 2 1

1 1

=

0

=

)

)

)

C

)

)

2 W

)

L K

E K

W L

K W

M W

M B

E B

G A

J S

J B

T

(

(

(

(

(

(

O O

N T

T T

T T

T T

F F

F F

F F

T S =

A A

A A

D A

A F

U =

R R

R R

E R

R A

T =

D D

D D

R D

D R

A =

R D

T =

T T

T T

E 8 T

T S =

S S

S S

F 7 S

S D

1 1

I 1

S 8 1

1 R

)

N 2 3 W H

H R

H A -

H H

L R E C

N B G

G G

G T N G

G I

(

Y =

T

=

I

=

L =

I

=

B =

I

=

X.

S =

E N =

C D

O =

E E

E E

E E

E E

N P =

P P

P P

W P

P P

I S =

C C

C C

S C

C C

E =

T R =

N EM.

U CO.

D..

S.

I S.

A.

S S

S S

S S

S S

B M

M M

M M

M M

M N =

E E

E E

E E

E E

N.

O =

T T

T T

T T

T T

G I

=

S S

S S

S S

S S

I T =

Y Y

Y Y

Y Y

Y Y

S.

C =

S S

S S

S S

S S

E.

E =

D.

S =

L L

L L

L L

L L

A A

A A

A A

A A

C C

C C

C C

C C

I I

I I

I I

I I

N N

N N

N N

N N

A A

A A

A A

A A

M H

H H

H H

H H

C C

C C

C C

C C

E E

E E

E E

E E

M M

M M

M M

M M

S =

S =

A =

S S

S S

S S

S L =

N N

N N

I N

N N

C =

EG M

A X

E R

O T

O B

S T

R Y

S R

E S

E T

L T

A N

I A

W O

O W

M I

E =

G E

T L

M L =

D N

T A

E E

M T

=

N I

S C

U M T

E I

=

A L

Y I

F E M

S T

T

=

O S

F T

E Y

S

=

M O

I R S T

S Y

D =

U C

M R

O Y S

S B =

U M A

U T S Y

R D =

C E T

E P

A S

I D

A T N

T R R A

E V S A

S L

E E R

E Y

L I

N F I

T F

R S P

Y O

E S A

N E

R G N E

L S G E

A E

A E

M A

N N N

I N

L R C

U C

E I

I L

I E T I

R I

D M B

I B

S V

T M

N I

R X

R E D R

S E

O R U

U U

N E

N H

I C P T

A T

D A S

I C

V =

E =

0 0

0 0

0 0

0 0

R =

5 1

1 2

3 4

5 6

8 1

1 1

1 1

1 1

1 2

. 7 2

2 2

2 2

o8 2

2 2

N /

E E

E E

E E

E E

0 M

e2

1. =

M M

M M

M M

M g /

D =

D D

D D

D D

D D

a5 B =

B B

B B

B B

B B

P 0 D =

D D

D D

D D

D D

I

=

=

=

7 7.

8 -

8 7

7 -

7 -

=

8 8.

8 -

8.

8.

8 -

8 -

3 = 3

/

/.

/ -

/.

/

/.

/ -

/ -

- = -

4 - /

0. /

4 - /

. /

8

/

7. /

3 - /

3 - /

D = T 1

2.

2 -

0.

2.

2 -

2 -

C = C

/ -

/.

/ -

/

/.

/.

/ -

/ -

E = A 8 - /

1

. /

6 - /

/

1

. /

0

/

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3 - /

=

0 -

1 0 -

0 1

0 -

0 -

=

=

=

=

=

7 -

7 7.

7.

7 7 -

7 -.

=

8 -

8 8.

8.

8 8 - 7 8 - 7 2 = 2

/ -

/.

/ -

/.

/.

/

/ - 8

/ - 8

- = -

2 - /

9

/

- /

2. /

5. /

3. /

9 - /

9 - /

D = T 0 -

0 1

2 1

0 - 8 0 - 2 C = C

/ -

/.

/ -

/.

/

/.

/ - 0

/ -

1 E = A 7 - /

0. /

- /

6

/

1

/

0. /

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3 - /

=

0 -

1 0

1 1

0 - 5 0 - 3

=

- 0

- 0

=

=

=

~

7 -

7 8 -

7 7.

7 6 ~

6 -

8 -

8 8 -

8.

8.

8 8 - 6 8 - 6 1

1

/ -

/.

/ -

/

/.

/

/ - 8

/ - 8 2 - /

8. /

2 - /

5

/

9. /

1

/

1

- /

1

- /

D T

2 -

2.

2 -

1 0

0.

3 -

1 3 - 0 C

C

/ -

/.

/ -

/

/

/.

/ - 3

/ - 3 E = A 5 - /

8

/

4 - /

5. /

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C C

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)

5

)

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(

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)

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=

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)

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T T

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=

S S

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L L

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H H

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S =

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M M

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=

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M M

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D 0

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/.

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0.

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1 1

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/.

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(

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T =

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=

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T R =

N.

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U.

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=

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S S

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L L

L L

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C C

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N N

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S =

A =

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] =

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=

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G S

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M M

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D N

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N O

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T Y E A L

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S S S V

S S D W P

C V =

E =

0 0

0 0

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7 1

2 3

5 6

9 1

3 4

3 3

3 3

3 4

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2 2

2 2

2 2

N /

E E

E E

E E

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M M

M M

M M

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D =

D D

0 D

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D D

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B B

8 S

B B

B B

P 0 D =

D D

D D

D D

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=

=

=

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3 = 3

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/

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/

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/.

/.

/.

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/

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1

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/

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/

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/

/

/.

/.

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/

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/

/

/

/

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7.

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D T

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f

=

. 0 0

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S =

T T

T T

T T

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F F

F F

F F

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A A

A A

A A

A =

R R

R R

R R

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D D

D D

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L L

L L

L L

S A

A A

A A

A E

N N

N N

N N

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F F

F F

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E E

E E

E E

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S S

S S

S S

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=

U U

U U

U U

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O O

O O

O O

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=

H H

H H

H H

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G G

G G

G G

G I

=

N N

N N

N N

N O

X.

S =

I I

I I

I I

I C

E.

N =

T T

T T

T T

T S

D O =

S S

S S

S S

S A

N P =

E E

E E

E E

E B

I S =

W W

W W

W W

W E

E =

T R =

N E.

M.

U.

C.

O.

D S.

I S.

A.

S S

S S

S S

S S

S.

M M

M M

M M

M M

N =

E E

E E

E E

E E

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T T

T T

T T

T T

G.

I

=

S S

S S

S S

S S

I T =

Y Y

Y Y

Y Y

Y Y

S C =

S S

S S

S S

S S

E E =

D.

S =

L L

L L

L L

L L

A A

A A

A A

A A

C C

C C

C C

C C

I I

I I

I I

I I

N N

N N

N N

N N

A A

A A

A A

A A

H H

H H

H H

H H

C C

C C

C C

C C

E E

E E

E E

E E

M M

M M

M M

M M

S =

S =

A =

I I

I L =

I I

I I

I I

I I

C =

M ETS M

Y M

E S

E T

M T

S L

E S

Y O

T Y

S R

S S

T Y

G S

N S

M G

N M

M O

E N

I E

E =

E C

L T

I S

T L =

T M

A S

S S

S T =

S E

E V

Y S

E Y

I

=

Y M

T O

S E

C S

T =

S U

S M

C O

=

L Y

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C D =

T O

S R

O R

P A

B =

N V

I P

V D =

A E

T T

E H

L D

L A

C E

T O

N C

E E

T S

T O

A Y

H J

S A

N C

C N

A W

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E L

I W

M R

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A S

N O

C U

Y D

U I

T I

N D

T I

O A

C M

O I

E U

E T

A E

R S

F Q

S N

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O E

A I

A O

R C

B R

S L

G C

V =

E =

0 0

0 0

0 0

0 0

R =

0 1

0 5

8 0

1 4

9 0

5 5

5 6

6 6

6 0

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2 2

2 2

2 2

3 o 8 N /

E E

E E

E E

E E

0 M

e2

1. =

M M

M M

M M

M g /

D =

D 0

D D

0 D

D D

a 5 B =

B 8

B B

8 B

B B

P 0 D =

D D

D D

0 D

D D

I l\\

j 111lll)li1

=

=

=

7 7 -

7 -

F 9 -

F -

F -

7 -

=

8 8 -

8 -

8 8 -

8 -

8 -

8 -

3 = 3

/

/ -

/ -

/

/ -

/ -

/ -

/ -

- = -

1

. /

1

- /

1

- /

4. /

1

- /

1

- /

1

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1

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D = T 0.

0 -

0 -

1 0 -

2 -

0 -

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C = C

/.

/ -

/ -

/

/ -

/

/ -

/ -

E o A 9. /

9 - /

9 - /

8. /

9 - /

8 - /

9 - /

9 - /

=

0.

0 -

0 -

0 0 -

0 -

0 -

0 -

=

=

=

=

=

7 -

7 -

7.

7 -

7 -

=

8 -

8 -

8.

8 -

8 -

2 = 2

/

/ -

/ -

/.

/ -

/ -

/ -

/ -

- = -

. /

1

- /

4 - /

1

/

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7 - /

4 - /

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D = T 2 -

1 3

0 -

1 C = C

/

/ -

/ -

/.

/ -

/ -

/ -

/ -

E = A

/

8 - /

8 - /

7. /

- /

8 - /

8 - /

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=

0 -

0 -

0 0 -

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=

=

=

=

=

7 -

7 -

7 7 -

7 -

=

8 -

8 -

8 8 -

8 -

1

=

1

/

/ -

/ -

/.

/ -

/ -

/ -

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/

6 - /

3 - /

9. /

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2 - /

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D T

2 -

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1 1

1 C

C

/

/ -

/ -

/.

/ -

/ -

/ -

/

E A

/

6 - /

7 - /

6

/

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6 - /

6 - /

)

0 -

0 -

0 0 -

0 -

=

S =

6 5

7 5

7 5

5 6

U =

T =

1 A =

T

=

5 4

5 4

5 4

4 5

S =

S S

S S

S S

S S

E E

E E

E E

E E

T T

T T

T T

f T

O O

O O

O O

0 O

N N

N N

N N

N N

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T =

I

=

L =

I

=

B =

I

=

O O

O O

O O

O O

X.

S =

C C

C C

C C

C C

E.

N =

S S

S S

S S

S S

D.

0 =

A A

A A

A A

A A

N.

0

=

B B

S B

B S

9 S

I S =

E E

E E

E E

E E

E =

T R =

N.

E.

M.

U.

CO D..

S.

I SA S

S S

S S

S S

S B.

M M

M M

M M

M M

N =

E E

E E

E E

E E

N O =

T T

T T

T T

T T

G.

I

=

S S

S S

S S

S S

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Y Y

Y Y

Y Y

Y S.

C =

S S

S S

S S

S S

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E =

D.

S =

L L

L L

L L

L L

A A

A A

A A

A A

C C

C C

C C

C C

I I

I I

I I

I I

N N

N N

N N

N N

A A

A A

A A

A A

H H

H H

H H

H H

C C

C C

C C

C C

E E

E E

E E

E E

M M

M M

M M

M M

S =

S =

A =

L =

I I

I I

I I

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C =

C N

N A

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V I

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T O

T N

A I

A A

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G T

T L

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I N

S A

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Y L

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A A

N N

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N T

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R I

V I

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T U

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T N

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N V

A A

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D L

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C W

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L N

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L C

T C

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E =

0 0

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E E

E E

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M M

M M

M M

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0 =

D D

D D

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8 B

B B

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D D

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/.

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Enclosure C Engineering and Construction Engineering Procedure ECF 1.01, " Organization" Revision 0

{

March 2, 1987 i

g -,,1 r rL I 'IrL 7 / p >atpy f I r

%T /.

f

.o

48-1 4

)

TEXAS UTILITIES ELECTRIC COMPANY ENGINEERING AND CONSTRUCTION ENGINEERING PROCEDURE ECE 1,01 ORGANIZATION i

u L

REVISION:

0 l

ISSUE DATE:

3/2/87 EFFECTIVE DATE:

3/2/87 MMIrv/

CONCURRENCE:

- per Ma er, TU ectric Quality Assurance-k b bbb M 16V 3 /d[& 7 APPROVED:

Director, ComanchebPeak Engineering

(

ENGINEER 7ti9 AND CONSTRUCTION ENCINEERING PROCEDURE ECE 1.01 ORCANIZATION 1.C PURPOSE The purpose of this procedure defines the Comanche Peak Engineering (CPE) organization at Comanche Peak Steam Electric Station (.CPSES) and describes interface control between CPE and Lead Contractors (LC), and between Lead '

Contractors and Other Contractors (OC).

'2.d APPLICABILITY This, procedure applies to CPE and Engineering Lead'Contracters working at CPSES.

)

This procedure replaces Procedure ECE AD 1, Revision 12.

1

3.0 REFERENCES

3.1 NEO 1.01

" Organization of the Nuclear Engineering

{

and Operation Group" 3.2 ECE 1.01 I1 (ECE-AD 1 1)

" Preparation and Review of Engineering Task Descriptions" NOTE The procedure / instruction number in parentheses is the procedure / instruction number per the Procedure ECE AD-3 numbering scheme.

This. number is valid until the procedure / instruction is revised and the new number, per Procedure ECE 1.03, is assigned.

4.0 -DEFINITIONS 4.1 Design Technical and management processes which commence with identification p

of design input and which lead to and include the issuance of design output documents.

ECE 1.01 Rev.

O Date: 3/2/87 Page 1 of 27

y 4

I e i,

,J

!S 4.2 Design Input Those criteria, parameters, bases or other design requirements upon which detailed final design is based.

4.3 Design output Documents such as drawings, specification, calculations and other i

documents defining technical requirements of structures,. systems and components.

4.4 External Design Interface Relati-onship between design groups from different organizations.

4.5 Internal Design Interface 1

Relationship between design groups within the same organization.

4.6 Task.'3escription (TD)

\\

The TD initiated by CPE, by the Lead Contractor or Supporting.

Contractor shall, describe the task in sufficient detail for the contractor to plen-2nd execute the task. The level of details in the i

', ID shall be as per Aeference 3.2.

4.7 Work Instruction (WI) g i hWork Instructions provide the. settel technical information for the implementation of the task description.

WI's include appropriate quantitative or qualitative acceptance criteria for determining that important activities have been satisfactorily accomplished.

4.8 Summary Scope and Schedule (SSS)

The SSS provides an overview of the contractor's plan to execute a task described in a TD and/or WI.

1 61-9 Comanche Peak Engineering (CPE)

't g

The site Engineering Department of the Texas Utilities Electric Company (Ti'EC), Engineering and Construction Division which is assigned the responsibilities and functions defined in Reference 3.1.

s s

t'CE 1.01 Rev.

O Date.: 3/2/87 Page 2 of 27

,1 g

. :h

4.10 Lead Contractor (LC)

The engineering contractor designated in writing as having primary responsibility for work defined by a TD.

4.11 Supporting Contractor (SC)

An engineering contractor providing support to a Lead Contractor for work defined by a TD.

4.12 Other Contractor (OC)

An engineering contractor having a contract directly or indirectly with CPSES.

5.0 RESPONSIBILITIES 5.1 Director, Comanche Peak Engineering The Director, Comanche Peak Engineering has the overall responsibility for the programs and activities of the Comanche Peak Engineering Department and the approval and implementation of Task Lascriptions and Work Instructions.

5.2 Lead Contractor Lead Contractor, Supporting Contractor, and Other Contractor persons of equivalent authority are responsible for.their company's approval and implementation of the TDs and WIs herein defined.

5.3 Section Managers, Comanche Peak Engineering The Section Managers, CPE are responsible for CPE Task Description and' Work Instruction prep ^ ration.

5.4 CPE Engineering Assurance (EA) Systams Manager The EA Systems Manager is responsible for ensuring TD and WI compliance reviews and coordination of interdisciplinary reviews.

6.0 INSTRUCTIONS 6.1 Site Engineering Organization The site engineering organizations (Figure 7.1) for design, engineering, and construction activities at CPSES, consist of CPE and the following Lead Contractors:

ECE 1.01 Rev.

O Date:'3/2/87 Page 3 of 27 1

Stone and Webster Engineering Corp., (SWEC)

(SWEC - Corrective Action Project)

(SWEC Pipe Support Engineering)

Westinghouse (W)

Ebasco (EB)

Impe11-(IM)

Crinnell Fire Protection System Company (GFPS)

Engineering Planning and Management, Inc. (EPM)

Gibbs & Hill (G&H)

\\

A description of each organization's structure, functions, and responsibilities as they relate to CPSES activities is detailed in the following sections of this procedure.

6.2 Comanche Peak Engineering Department t

The Comanche Peak Engineering Department within the Engineering &

Construction Division, is organized into six sections by engineering discipline or support activity (Figure 7.2).

The Director, CPE is responsible for management of the department and reports directly.

to the Vice President, Engineering & Construction.

A brief description of the work scope for each section within CPE follows.

6.2.1. Mechanical Engineering The Mechanical Engineering Section (Figure 7.3), under the direction of the Manager, Mechanical Engineering, conducts programs of discipline activities within a scope ' defined by the Director, CPE.

The programs interface with CPE Sections and other organizations, as necessary.

The programs also implement j

applicable NEO policies and procedures.~

The Mechanical Engineering Unit's Program includes:

Mechanical Design / Systems o

Specification of Mechanical Equipment,' Components, o

Design and Construction Equipment Stress Analysis o

ASHE Section XI Program o

o Applied Mechanics Thermal-Hydraulic Analysis o

Materials / Welding Engineering o

Chemical / Environmental Engineering o

o Fire Protection / Fire Safe Shutdown Nuclear Engineering o

Final Safety Analysis Report (FSAR)/ Technical Specification o

(TS) Coordination ECE 1.01

Rev, O

Date: 3/2/87 Page 4 of 27

t i

i o

Westinghouse Interface Risk and Availability Analysis / Assessment o

Independent Review of Plant Changes o

j Industrial Safety o

o Protective Coatings Preparation of Task Descriptions as required o

The Mechanical Engineering Services Program includes:

Specification / Technical Review / Evaluation o

j Design Basis Documents, Drawings, Calculations o

System Interaction Program I

o o

Commitment Tracking Subcomponent Tagging Program o

Nuclear Operations Defecting Items List o

i Plant Photographic Record o

o Q List Administration I

Preparation of Task Descriptions o

6.2.2 Electrical Engineering The Electrical Engineering Section (Figure 7.4' ) under the direction of the Manager, Electrical Engineering, conducts programs of discipline activities within a ecope defined by the j

Director, CPE, The programs interface with CPE Sections and other organizations, as necessary.

The programs also implement applicable NEO policies and procedures.

The Instrumentation and Control Engineering Unit's Program includes:

i Instrumentation, Controls, and Computer System Hardware, o

Sof tware, materials and services Security System (Computer) o Control Valves, Solenoids, Limit Switches,(includin5 l

o Computer and Microprocessor Based Systems o

ATUS/AMSAC, RVLIS, CCM, ERF, Analog Controls, DRMS, Containment Hydrogen Monitoring)

Main Control Boards, Auxiliary Panels and Associated o

Hardware o

Human Factors Evaluations Tubing and Support Installation Criteria o

Configuration Control of In-Plant Software, Instrument and o

Relay Set Points (Excluding Protective Relays)

Preparation of Task Descriptions, as required o

The Electrical Engineering Unit's Program includes:

ECE 1.01 Rev.

O Date: 3/2/87 Page 5 of 27

i j

4 l

1 1

Equipment Qualification Program and File Maintenance 3

o Fire Safe Shutdown Circuit Analysis i

o Security System (Excluding Computer) o Electrical Systems Analysis and calculation with l

o Coordination, Breaker Settings, Cable Sizing, etc.

Electrical Systems Hardware, Material and Services o

Electrical Hardware Layout and Installation Criteria

{

o Configuration control or Protective Relay Settings j

o Cable and Raceway Schedule

(

o Preparation of Task Descriptions, as required

)

o 6.2.3 Civil Engineering f

The Civil Engineering Section (Figure 7.5) under the direction

{

of the Manager, Civil En5 neering, conducts programs of 1

discipline activities within a scope defined by the Director, CPE.

The programs interface, as necessary, with CPE Sections and other organizations.

The programs also implement applicable NEO Policies and Procedures.

The Civil / Structural Engineering Unit's Program includes-Civil / Structural Design Basis Documents o

Seismic Floor Response Spectra o

Building Structures and Structural Components o

o Concrete Embedments I

o Containment Level o

Ceotechnical and Foundations o

Earth and Rockfill Dams Site Seismicity o

o Hydraulic Structures Computer Assisted Drawing (CAD) Support o

Preparation of Task Description, as required o

The Piping and Support Engineering Unit's Program includes:

o CAD Support o

Piping Stress o

Pipe Supports Component Supports o

Cable Tray Supports o

o Conduit Supports HVAC Supports (including ductwork) o o

Pipe Vhip Restraints o

Moment Restraints o

Jet Impingement Shields Instrumentation Tubing Supports o

Piping & Support System DBD's o

ECE 1.01 Rev.

0

'Ja c e : 3/2/87 Page 6 of 27

j c.-

4 t

l o

Hits Maintenance Preparation of Task Descriptions, as required o

s 6.2.4 Engineering Assurance i

The Engineering Assurance Section (Figure 7.6) under the

(

direction of the Manager, Engineering Assurance, conducts j

programs and activities within a scope defined by the Director, CPE.

The programs interface as necessary with CPE Sections and l

other organizations.

The programs also implement applicable NEO policies and procedures.

The Engineering Assurance Systems Unit's Program includes:

o ECE Procedure Preparation, revision and Maintenance

'Subtier Engineering Contractor Procedures Review-o ECE Procedure compliance with NEO Procedurea and. Quality o

Assurance (QA) Plan Prepares and updates the QA. Plan relative to Comanche Peak o

Engineering Department Task Descrip tion, - review and' processing o

o New Employee Indoctrination Engineering Personnel Training.

o o

Training and Qualification / Certification Administration

(

Historical Training File maintenance o

EC Procedure processing o

Distribution of NEOs for interdisciplinary review o

Responds to Information Requests o

i The Engineering Assurance Evaluations Unit's Program includes:

Technical Evaluation and Engineering Activities study o

o Engineering Activities surveillance Corrective / Preventive Actions to resolve Audit / CAR findings o

o Authorized Approval Index maintenance Design Control Trending Analysis o

Support of EA Activities in Engineering, Projects, o

Construction, Operations and Qt'ulity Ass"rance o

Special Projects The Eng.ineeria ( J.ssurance Regulat,

Compliance Unit's Program 4

includec:

Nuclear Regulatory Commission (NRC) E&C. Division Direct o

Interface coordination and maintenance Regulatory Issue Response as Implementation coordi:.ation o

E&C Historical. commitment Implementation verification.

o ECE 1.01 Rev.

O Date: 3/2/87 Page 7 of.27.

E&C 10CFR50.55(e) Responses and 4.tivities Coordination and o

Operating Experience Reports o

Commitment Tracking System maintenance (when operational) 6.2.5 Engineering Projects The Engineering Projects Section (Figure 7.7) under the direction of the Manager, Engineering Projects, conducts programs of activities within a scope defined by the Director,

CPE, The programs interface, as necessary, with CPE Sections and other organizations.

The programs also implement applicable NEO policies.and procedures.

The Engineering Support Unit's Program includes:

1 o

Correspondence Control i

o Controlled Distribution o

Design Change Control o

Document Control o

ECE Procedures Distribution Engineering Library o

Engineering Records Retention I

o Word Processing o

The Project Engineering Unit's Program includes:

~

Internal Engineering Project Management o

Engineering Studies Management o

Engineering Contractor Studies Management o

Design Modification Management o

Preparation of Task Descriptions, as required o

The Computer Graphics Unit's Program includes:

Intergraph CAD System Hardware, Software and Associated I

o conttacts Management CAD Production Procedures and Standard Method Development o

and Drawing Maintenance Drawing Restoration Program Management o

CAD System 2D and 3D Drawing Technique Engineering o

t Personnel Training Preparation of Task Descriptions, as required o

The Procurement Engineering Unit's Program includes:

Procurement Technical Support o

Vendor Interface Coordination / Quality Assurance o

ECE 1.01 Rev.

O Date: 3/2/87 Page 8 of 27

j i

)

commercial Crade Item Dedication Program development and o

implementation Specification Review, Vendor Drawing and VETIP Project o

Oversight q

i o

Spare Parts Review Preparation of Task Descriptions, as required o

6.2.6 Work Tracking-1 The Engineering Work Tracking Section (Figure 7.8) under the direction of the Manager, Engineering Work Tracking, conducts a j

program of activities within a scope defined by the Director, CPE.

The program interfaces, as necessary, with CPE Sections

]

and other organizations.

The program also implements applicable NEO policies and procedures.

The Engineering Work Tracking Program includes:

j a.

Work Tracking:

Nonconformance Reports (NCRs) o Deficiency Reports (DRs) o Request f ar Information (RFIs) o Technical Information Requests (TIRs) o TU Electric Design Deficiency Reports (TDDRs) o Discrepancy / Issue Resolution Reports (DIRs) o Request for Information Clarification (RFIC) o Design Change Authorizations (DCAs) o Component Modification Cards (CMCs) o b.

Design Modification and Process Package Form Schedule coordination Design Modification, Process Package Form, Test Deficiency.

c.

TUEC Design Deficiency Request and Engineering Change Notice Reports 6.3 Lead Contractors 6.3.1 Stone & Webster Engineering Corporation (SWEC)

6. 3.1.1' Corrective Action Proiect (CAP):

SWEC develops and implements corrective action to document design adequacy for mechanical, electrical, structural, and instrumentation and controls areas.

ECE 1.01 Rev.

O Date: 3/2/87 Page 9 of 27 A

1 i

Concerns to be addressed are derived from Comanche Peak Response Team (CPRT) "Self Initiated" issues, j

" External Sources" issues (TRT, ASLB, NRC, IAP,'etc.),

and additional items identified by SWEC.

SWEC_shall analyze these issues and-determine the generic j

implications in order to ascertain if any additional-design efforts might be deficient.

Based on the analysis of design adequacy, SWEC shall develop and implement a corrective action program to review and upgrade CPSES plant documentation and hardware, as required, to meet CPSSS design safety criteria.

Specific activities are:

Assessing the design basis of the applicable o

disciplines.

This effort shall include development of design criteria and system descriptions in the form of Design Basis Documents.

I Reviewing appropriate calculations against.the o

documented design basis.

l Evaluating key engineering diagrams, drawings, and-o specifications for conformance to design basis

)

documentation.

j

\\

Revising existing and/or generating new o

calculations and key design documents, as required.

Providing sufficient documentation to support the o

conclusion of design adequacy, in the form of Generic Issue Reports.

SWEC is also responsible for general construction completion design activities and technical liaison with the TUEC Startup Test organization as assigned by TUEC.

This includes design development, design changes and licensing support resulting from j

corrective action activities or as assigned by TUEC.

SWEC is responsible for all civil / structural design and engineering activities including embedment load evaluation, CPRT issue resolution, NCR dispositioning, design change implementation, and licensing support.

ECE 1.01 Rev.

O Date: 3/2/87 Page 10 of 27

I 1

q SWEC_is responsible for all~olectrical design and engineering activities and all Instrument and Control

^

design and engineering activities including CPRT issue resolution, NCR dispositioning, design change implemen-

'tation, licensing support, construction support and interface with other. design contractors.

SWEC is responsible for all mechanical design and engineering activities including Comanche Peak-Response Team.(CPRT) issue resolution, NCR dispositioning, design change implementation,.

licensing support, construction support and interface with other design contractors.

j consulting Work CPE issues work to SWEC for miscellaneous engineering activities under a general purchase order, (blanket order) j G.O. CPF-12344 S (DA-79053).

The following are examples of this type of work:

4 Review attachments to Westinghouse Steel a.

b.

Drawing Transmittals

)

c.

Licensing Reviews d.

Steam Generator Upper Lateral Support Beams e.

DCA Reviews f.

System Interaction Program Reviews' g.

Response to SWEC concerns h.

Audits 1.

Design Reviews prepared by others 6.3.1.2 SWEC Pipe Support Engineering (PSE)

J In the area of pipe support qualification, SWEC has been contracted to provide design and engineering services for the qualification =of the structural aspects of piping and pipe supports.

These <;tivities are performed by LWEC personnel in accordance with SWEC program requirements and procedures.

Site issued pipe support design changes are approved by.SWEC.

The specific site interface for these cetivities are detailed in Task Descriptions developed in accordance with.

Reference 3.2.

ECE 1.01 Rev.

O Date: 3/2/87 Page 11 of 27:

6.3.2 Westinghouse (W)

Westinghouse has been contracted to. provide the Nuclear Steam Supply System (NSSS) by conducting engineering design ~ of both.

systems and components, procurement, fabrication and associated s

QA services; provide the. initial fuel supply; and assist in the -

installation, erection, licensing, testing, and operation of' l;

the NSSS.

Ongoing Westinghouse activities include the review l

of' design changes that impact. completed Westinghouse designs, including but not limited.co:

o NSSS' systems designs, Reactor Coolant. System.(RCS). components supports. design, o

Westinghouse supplied steel, o

Westinghouse designed supports, o

Nozzle loads on Westinghouse-supplied equipment, o

o FSAR analyses.

4 Westinghouse performs Class 1 stress. analysis activities at the Westinghouse Generation. Technology Systems Division (GTSD) in Pittsburgh. Technical assistance.is also provided, j

Activities are conducted in accordance with approved program require'ents and procedures. 'Although'a' formal interface m

agreement has been issued, tho' specific site interface for.

these activities are detailed in a Task Description Javeloped j

in accordance with Reference 3.2.

6.3.2.1 NSSS Design Basis Documentation (DBD) i Westinghouse is devel'oping a program to supply ~TUEC-with NSSS Design Basis Documents.

The intent of the DBD package is to establish =the original design basis

.l of the CPSES plants and then to-compare this to the current piant configuration.

6.3.3 EBASCO I

EBASCO is contracted to provide general project and specific technical assistance in the areas of System 1 Interaction-1 Program, cable tray supports. and safety related Trains Az and B and Train C over 2 inch diameter conduit supports, protective.

1

' coatings, and HVAC systems, i

Tasks rebsrding general assistance are specified by formal

~

purchase order and supplements.

These activities, r,anging from.

4 ASLB support to specific jobsite assistance, are used in the ECE 1.01 Rev.

O Date::3/2/87 Page 12 of.27, s

-....,.......i

engineering / construction effort or as design inputs to the established design control programs.

6.'3.3.1 Systems Interaction Program Ebasco is responsible for those activities associated with the completion and maintenance of Unit 1 and Unit 2 System Interaction Program (SIP).

These activities include the identification and evaluation of inter-actions that may result from pipe break events, missiles and seismic induced failures.

In addition.

Ebasco will perform walkdown and analysis services related to other activities as identified by the TUEC

]

Vice President, Engineering and Construction. All these activities will be performed in.accordance with CPE procedures.

The specific site interfaces for these activities are detailed in a Task Description developed in accordance with Reference 3.2.

Ebasco j

will appoint a System Interaction Program Manager (SIPM) who will be responsible for scheduling, and administrative management of the Systema Interaction i

Program.

The SIPM will report to the Ebasco Project Engineering Manager who.in turn vill report to the Ebasco Vice President.

Ebasco _s responsible for providing qualified personnel to perform the assigned activities.

- 1 6.3.3.2 Structural Activities Ebasco is responsible for the structural activities associated with completion and maintenance of the Unit 1 and Unit 2 cable tray hanger systems.

These activi-ties include:

preparation of an initial set of hanger drawings o

representing the intent of design; walkdown and as-builting of each individual o

support and cable tray spans between supports, redlining of individual hanger drawings, o

preparation of "as built" drawings for each o

hanger, and, in Unit 1, of the cable tray spans:

ECE 1.01 Rev.

O Date: 3/2/87 Page 13 of 27 I

~

l l

design verification of the system (hanger and l

o tray) with the exception of the Unit 1 portion of the system within the Safeguard'and Reactor Building, which are responsibility. of IMPELL.

{

Ebasco is also responsible for the performance of any tests required to support the.above activities, resolution of field problems for any new hangers'being designed; resolution of NCR's for specific problems; backfit problems associated with craft and/or inspection, and preparation of footprint load forms (FPL's) utilized for the evaluation of embedded plates to which the hangers attach.

Ebasco is responsible for the structural activities associated with completion and maintenance of the Unit 1 and Unit 2 conduit systems including Trains A and B and Train C conduits over 2 inches in diameter.

These activities are comprised of:

J design verification and reissue of the design o

documents governing the design and installation of the Unit 1 and Unit 2 systems, (these are respectively the S-0910 & S2 0910 documents) design of modified and individually engineered o

supports; walkdown and preparation of conduit isometrics for o

Unit 2 and the Unit 2 conduits within the Unit 1 boundary and common area; design of supports to replace selected UNISTRUT o

member supports of Unit 1; walkdown and isometric preparation of selected o

conduits in Unit 1; common collection of pertinent junction box data; o

design of any new seismic supports; o

o preparation of loads for assessment of embedded plates.

ECE 1.01 Rev.

O Date: 3/2/87 Page 14 of 27

l 6.3.3.3 Tests Ebasco is also responsible for the performance of any l

test required to support the above activities; resolu-tion of field problems with any. modified or indivi -

i dually designed supports; resolution of NCR's and back fit problems associated with craft and/orz inspec--

j

tion, i

6.3.3.4 Off-Site Activities Work _ associated with the cable. tray and conduit' system activities is performed at the site and at Ebasco home offices. The former is performed under the direction of two supervisory ~ engineers, responsible respectively.

for Unit 1 and Unit 2 activities.

They report-to the Ebasco Project Engineering Manager.

The latter is performed by Ebasco personnel.using Ebasco procedures prepared in accordance with the contract program requirements.

Scheduling and administrative manage-ment are provided by the Ebasco Project Manager, New j

York Office who reports to the Project Engineering Manager of Ebasco on site.

6.3.3.5 Personnel The site activities are performed by Ebasco personnel and personnel from other companies.

Personnel, however, perform work under direct Ebasco supervision, utilizing CPE or Ebasco. project specific procedures as applicable.

Scheduling and administrative management as well as technical direction are'provided by the Ebasco Project Engineering Manager who reports to the Ebasco Vice President.

6.3.3.6 Protective Coatings Ebasco provides program development 'and maintenance i

field inspection and documentation, engineering and technical support and document review for~all i

protective coatings at CPSES.

Protective coatings are-here defined as specialized coatings required to minimize the potential for radioactive contamination in addition to provide the required corrosion

'4 protection.

In this'Ebasco is also responsible for the coatings paper flow' group which develops.

maintains, statuses and processes-the travelers.

ECE 1.01 Rev.

O Date: 3/2/87 Page 15 of 27:

9

Finally Ebasco is responsible for the development and supplementation of pre and post operational testing and surveillance program for protective coatings.

The protective coatings work is under the direction of a supervisor who will report to the Ebasco Project Engineering Manager.

6.3.3.7 QA Interface 1

.To provide QA interface, to track critical path items, and to track and update resolution to-SDAR's, NCR's,-

]

TDDR's, RFI's, and CAR's, Ebasco has established a site quality analysis team which is directed by a supervisor reporting to the Ebasco Project Engineering q

Manager.

-)

6.3.3.8 HVAC Systems EBASCO is responsible for HVAC' systems and duct and i

duct support structural adequacy verification.

These activities include:

HVAC systems' engineering / design including site l

o

support, HVAC duct and duct support As-Builting o

o CAD drawing preparation, HVAC duct and duct support structural design o

verification and site support.

6.3.4 Impell Impell Corporation is contracted to provide technical assistance in the areas of cable tray. supports and non-safety related (Train C) conduit supports (2" and smaller diameter),

fire protection (FP), seismic and environmental equipment qualification (EQ), HVAC supports, Cable Slack evaluation and Fire Protection.

6.3.4.1 Unit 1 Cable Trav Unit 1 Cable Tray activities consist of.a technical review of cable tray supports in Reactor and Safeguard-buildings of Unit 1:

ECE 1.01 Rev.

O Date: 3/2/87 Page 16 of 27

1 The support evaluation criteria, methodologies and a.

procedures developed by G&H, CPE and Ebasco were reviewed by Impell.

Impell subsequently developed criteria, methodology and procedures consistent with the G6H, CPE and Ebasco criteria documents, b.

Perform technical review in accordance with the Impell developed criteria, methodology and procedures on as built documents resulting in a single support drawing which is developed by Ebasco personnel, c.

Included in this technical review is the preparation of footprint loads (FPL's) utilized for

-j the evaluation of embedded plates to which the hangers attach.

d.

Results of the technical review are recorded in the form of individual as-built cable tray hanger druings in the Safeguard and Reactor buildings approved by Impe11.

i 1

e.

Impell is also responsible for resolution of field problems associated with new supports or trays, resolution of NCRs for specific attributes and any backfit problems identified by QC or Impell's review of Construction Work Packages.

6.3.4.2 Unit 1 & 2 Train C Conduit Supports 1

The Unit 1 & 2 Train C conduit support (less than or equal to 2 diameter) consist of:

The support evaluation criteria provided by C6H a.

and the results of the target evaluations performed by Ebasco are reviewed and new methodology criteria and procedures for evaluation of supports are developed by Impell; b.

Implementation of the new criteria and procedures by Impa11; Design change on supports not meeting the I

c.

criteria developed is performed by Impell; d.

Design of several non typical Unit 2 Train C conduit supports by Impell; ECE 1.01 Rev.

O Date: 3/2/87 Page 17 of 27 k

e_

\\g

=

i L

Footprint loads developed by.Impell for Train C e.

~

supports welded to embedded plates are transmitted 'to the SWEC SEG; group for plate y

qualification; j

i f.

The results of rework (c) and~ design (d) are j

transmitted to craf t-by Impell for support

-J construction and rework, 1

6.3.4.3 Support Activities

-)

ai Fire Protection Program-The Impell Fire Protection' Program consist of four main areas: Design Engineering,

. Construction / Production Support,LPenetration g

Seals, and Spacial Proj ects. Group.

l The Impell Design Engineering Group is responsible for identifying and closing out

{

existing licensing commitments,-review of.

J incoming licensing commitments, updating the

{

Fire Hazards Analysis and Final Safety Analysis j

Report, NFPA Code Compliance (except for-f suppression systems), evaluating emergency.

lighting and communications requirements, and review and disposition of NCRs, DRs, DCAs, and TDRs.

The Impell Construction / Production Support. Group is responsible for the TU Electric /Grinnell interface for. plant. review, NFPA code compliance for suppression systems, disposition of Grinnell i

NCR's, technical support for the new treated water supply system design effort, outlying building construction' support, interface with American Nuclear Insurers-(ANI) and supporting capital improvement projects and' constructicn j

proj ec ts,

i The Impell Penetration Seal Group is responsible-

' for determination of seal design requirements,:

updating the Desi n Basis Document for 6

penetration seals, providing input of the Fire i

Hazards Analysis, Interdiscipline Design Reviews, supporting the Stone and Webster Engineering t,

A ECE 1.01 Rev.

O Date: 3/2/87:

Page 18 of-27

i Corporation (SWEC) stress analysis efforts,. third party verification of penetration seal' installations, quarterly design submittals to ANI, maintenance of specification 2323 MS 38F for penetrat. ion seals, and approval of vendor (BISCO) fabrication drawings.

l The Impell Special Projects Group is responsible for the preparation of.the NRC Fire Protection I

audit, licensing interface, and lead of the Fire Protection Task Force on site.

b.

Equipment Qualification (EQ)

The Impell Equipment Qualification Group. consists of two main areas:

IX) Documentation section:and EQ Program section.

The Impell EQ Documentation Section'is composed.

of 5 groups responsible for the ongoing support activities of the Seismic and Environmental Equipment Qualification efforts to support construction and operations and for development of upgraded Seismic and Environmental Qualifications packages.

Site support activities include review of DCAs, DRs, and IDRs, upgrade of the EQ files and EQ packages, mechanical cycling requirements, review of vendor documentation,-

support for the HVAC design verification effort, qualified life determinations, establishuent of auditable documentation of the plant construction relating to equipment qualification and coordination of the SUEC EQ walkdown effort.

EQ packages upgrade activities include implementation of upgrade environmental checklists and seismic summary packages, identification and resolution of documentation discrepancies and incorporation of revised qualification parameters.

The Impell EQ Program Section is responsible for the establishment and implementation of the" programmatic aspects of the Equipment Qualification Program.

This includes development-of the EQ Database, development of'the Design ECE 1.01 Rev.

O Date: 3/2/87 Page 19 of 27

~ -

s.

Basis Document identifying Environmental parameters for EQ,.the development'of the EQ Masterlist, support.to licensing on issues such

.j as harsh versus mild environment, coordination-l with operations and maintenance relating to EQ issues development of the EQ Program Manual, development of EQ Training modules for CPSES use and development of the.TUEC Procedures necessary.

to maintain the completed Impe11 Program.

c.

Cable Slack Program The cable slack program is' designed to assure adequate cable slack exists'for conduit, cable tray, and equipment transitions..The work:is.

performed in accordance with Impell project instructions and Quality Assurance' manual in support of.the SWEC program.

6.3.5 Grinnell Fire Protection Systems Company

~

Grinnell Fire Protection Systems Company has been contracted to provide design, material, tools, labor, supervision and all

'i other items (except those specifically provided by others)

. required for the supply, fabrication, ; installation and testing of the fire protection systems.for Unit I and Unit II.

Current Grinnell Fire Protection Systems efforts include the items listed above along with inspection,. documentation, qus.' y. assurance / control, final as built drawings and hydrau-lic calculations.

Grinnell Fire Protection Systems provides technical assistance to TUEC when required.

All work activities are conducted within TUEC approved programs and procedures.

Crinnell Fire Protection Systems interfaces with CPE, Sub Contracts Administration, Building Management and TUEC QA/QC, Grinnell Fire Protection Systems quality assurance-and quality control responsibilities are ' audited.and monitored by TUEC Corporate Quality Assurance and Grinnell Fire Protection)

Systems Corporate Quality Assurance.

Grinnell Fire Protection Systems work is further outlined in contracts CP 0702, CP 0740 and subsequent supplements'to these contracts.

ECE 1.01 Rev.

O

~

Date: 3/2/87.

Page 20 of 27

l 1

l

/

l Crinnell Fire Protection Systems works under the direction of Sub-Contracts Administration in accordance with the above contracts.

Grinnell Fire Protection Systems design is based on specifications MS 98, MS 38C, MS 38E and MS 73A in i

conjunction with flow disgrams (M-225 series) and the fire hazard Analysis (DBD SY-1).

6.3.6 Engineering, Planning and Management, Inc. (EPM)

EPM is contracted to provide specific engineering and licensin5 assistance in the _ area of fire safe shutdown analysis (FSSA),

and engineering assistance in the utilization of the cable and.

raceway schedule (CARDS), plant data (PDS), and fire protection data systems (FPDS).

Tasks regarding these services.are specified in formal purchase orders and supplements.

EPM is responsible for those activities-associated with the completion and maintenance of the Unit 1 and Unit 2 Ff*; Safe Shutdown Analyses (FSSA).

These activities include:

the engineering evaluations and calculations to define a o

baseline of systems, components, and related design documents that are the basis for demonstrating and maintaining fire protection compliance against the requirements set forth in 10CFR50, Appendix R; I

the development of procedures and work instructions to o

administer the performance of the engineering evaluations; the fire protection licensing engineering support for o

future NRC audit (s) and compliance against NRC Ceneric Letter 86-10; the engineering support to ongoing Fire Hazards Analysis o

(FRA) activities performed by Impe11; the development and maintenance of a computer sof tware o

database to store and administer the baseline of systems and components of the FSSA; the performance of impact assessments of the effect of fire o

scenarios on the configuration baseline of systems and components; the determination of the adequacy of the installed and/or o

proposed raceway fire protection coatings (thermolag);

ECE 1.01 Rev.

O Date: 3/2/87 Page 21 of 27

t 4

the determination of required operational requirements for o

systems and components based on the impact assessments, including development of operational guidelines; the determination of regulatory deviations required and the o

adequacy of existing deviations; the documentation of the final results of the impact o

assessments.

EU' is also responsible for providing maintenance, validation, and control of the 10CFR 50 baseline database, including the induction of the FHA data into a common fire protection compli -

ance database.

EPM is responsible for providing FSSA design input to Impell and SWEC in support of their activities and in accordance with their Lead Contractor responsibilities.

EPM is also responsible for assisting CPE and SWEC in the utilization of the engineering computer data bases for the cable and raceway schedule (CARDS) and relatsd FSSA activities (FPDS and PDS), including: software and data validation, sof tware and data administration procedures, and training.

All the above activities will be performed in accordance with EPM /QA procedures in accordance with specific site interface procedures.

6 6.3.7 Cibbs & Hill (G&H)

C&H has been contracted to provide general, project and specific technical assistance to Procurement Engineering in the area of vendor document review.

Site activities will be performed in conformance with Comanche Peak Engineering procedures.

6.4 Comanche Peak Engineering Fire Protection Program The objective of the Comanche Peak Fire Protection Program is to assist TUEC in the evaluation,. definition and justification of the minimum set of plant systems and equipment required to achieve a safe hot standby condition and subsequent cold shutdown condition following a control room or cable spreading room fire.

The program includes operational and analytical evaluations of the Comanche Peak Plant relative to the assumptions and requirements of the Fire Protection Program.

Thermal hydraulic analysis of plant ECE 1.01 Rev.

O Date: 3/2/87 Page 22 of 27 34

m response to reactor trip and subsequent operator actions to achieve hot standby and cold shutdown is analyted using the TREAT computer code.

The analysis is used as the basis for the development of operational guidance for operators to control the plant following'the initiating fire, and'to achieve cold. shutdown conditions.

Program deliverables include an analysis basis document and an operational basis document.

6.5 Interface control Responsibilities 6.5.1 Comanche Peak Engineering Responsibilities CPE is responsible for:

Review and approval of TDs initiated by LC.in accordance a.

o with Reference 3.2.

b.

Developing TD as per Reference 3.2, if applicable.

Designating a Lead Contractor, in writing, for each c.

approved TD initiated by CPE or by LC.

d.

Engineering Management, Design Control, Administration of engineering and. design work performed in accordance with approved TD for CPSES.

j Ensuring that all engineeri,ng work performed for CPSES is e.

completed in accordance with approved engineering schedules.

f.

Providing administrative. support to. the LC in the fulfillment of document control activities as specified in CPE Procedures.

g.

Ensuring that the LC's are controlling the interface between other contractors involved with design, engineering, and construction of CPSES' activities to maintain design continuity.

h.

Monitoring the LC's performance and adherence to the approved TD.

i.

Ensuring adherence to regulatory requirements. in design,.

i engineering, and construction.of CPSES.

J.

Coordination and overview of contractor's resolution of engineering and construction quality deficiencies as identified by the TU QA, CPE Engineering Assurance and/or the NRC.

ECE 1.01 Rev.

O Date: 3/2/87 Page 23 of 27

6.6 Lead Contractor Responsibilities LC is responsible for; Developing TDs and applicable Work Instructions (WI) for all new a.

tasks, and existing tasks as required by CPE to clarify.the assignments or to reassign portions of the work among other contractors, b.

Obtaining approval from CPE on all TD, WI and Summary Scope '

Schedules (SSS) before initiating, Establishing procedures for documentation control with other c.

contractors and with supporting contractors, if applicable, as well as within LC organization.

d.

Developing project procedures / instructions to control.the design interfaces between contractors.

NOTE These procedures are approved by all interfacing contractors and by the Director, Comanche Peak Engineering.

Developing project procedures and/or instructions referenced in e.

the Task Description and/or Work Instruction for concurrence by

CPE, f.

Developing interface control (internal / external) and lines of communication, g.

Developing a monitoring system for the execution of the task to assure compliance with appropriate procedures, regulatory require-ments and approved TD/WI/SSS.

h.

Establishing Training Programs and requirements for maintenance of training records.

6.7 Interface Control 1

6.7.1 External 6.7.1.1 Identification of Interface Each Lead Contractor identifies, in writing, the-external interfaces between organizations (contractors ECE 1.01 Rev.

O Date: 3/2/87 Page 24 of 27-s.

and/or CPE) and includes organizations.providirJ

-criteria, designs, specifications and technical direction.

Included are those organizations required i

to receive Design Output from the Lead ~ Contractor or provide design input to the Lead Contractor.

6.7.1.2 Responsibilities l

Each Lead Contractor defines and documents in suff-icient detail, the responsibilities to cover' the preparation, review;and approval ~ of documents ~

involving all major events as defined in TD/WI/SSS.

Responsibilities are set forth in the " Interface Responsibility Matrices" of the TDs.

'6.7.1.3 Lines of Communication-LC establishes systematic methods for communicating with Supporting Contractors for all changes during the execution-of the TD.

These. documents identify the' positions and titles of key-personnel in the communication channels and their. responsibilities for -

decision making, for resolution of problems, - for providing and reviewing information, and ' eaking necessary action within the TD scope ~.

6.7.1.4 Documentation CPE and LC document interface' controls are addressed' by CPE in appropriate procedures associated with.TDs.

LC interface establishedi hrough these procedures t

also controls the flow of information~between-contractors. These procedures-are signed by all interfacing contractors and approved by.the. Director, Comanche Peak Engineering. Information transmitted from one contractor to another is identified and issued by authorized persons.

Documentation requesting.or providing information 'or requesting action is controlled by a system'which' assures the.

completion and acknowledgement by all interfacing contractors. This documentation is' maintained ~as s' i

record, 1

ECE 1.01 Rev.

O Date: 3/2/87 Page 25 of 27-

v L

6.7.2 Internal 6.7.2.1 Identification of Interface Each Lead contractor performing the work identifies, in writing, its internal TD/WI/SSS interfaces for managing the flow of task information between organizational units.

6.7.2.2 Responsibilities LC defines for.each. organizational unit the prepara-tion, review, approval, distribution and revision of documents involving task. interfaces.

6.7.2.3 Lines of Communication LC. establishes systematic methods.for communicating needed task information across internal interfaces, including changes to the TD/WI/SSS as work progresses.

6.8 Task Description The TD describes a task in sufficient detail for the contractor to plan and execute the task.

For each TD, a control program is established'and executed in accordance with approved procedures.

The LC defines the organizational structure which is to be implemented and delineates the authority.and-j responsibility of the personc.and organizations involved in performing the activities.

The responsibilities and interfaces among the contributing organizations (contractors),_both i

internal and external, are defined.

Provisions are made in the 1

Work Instruction (WI) for periodic audits, review and evaluation of the effectiveness of the program. in achieving the task objectives.

TD's are developed for all specialized-tasks that need detailed instructions and engineering tasks over 100 man hours.

LC davelops the'TD in accordance'with Reference'3.2 and obtains approval from CPE before initiating the task.

6.8.1 Work Instruction (WI)

WI's are developed for each TD usia( the guidelines stated-ia Reference 3.2.

1 ECE 1.01 Rev.

O Date: 3/2/87' Page 26 of 27

i 6.8.2 Sununary Scope And Schedule (SSS)

The Sununary Scope and Schedule provides-an overview of the contractor's plan to' execute the task described in a TD'and/or VI.

The plan is used to determine work priorities in order to meet the task objectives.

7.0 FIGURES 7.1 Site Engineering Organization Chart l

7.2 Comanche. Peak Engineering Organization Chart 7.3 Mechanical Engineering Section Organization Chart

)

7.4 Electrical Engineering Section Organization Chart 7.5 Civil Engineering Section Organization Chart 7.6 Engineering Assurance Section Organization Chart

{

7.7 Engineering Project Section Organization Chart 7.8 Engineering Work Tracking Section Organization Chart 8.0 ATTACHMENTS 8.A Procedure Matrix 8.B Intent Change Index Form 9.0 QA RECORDS None

....o ECE 1.01 Rev.

O Date: 3/2/87 Page 27 of 27

FIGURE 7.1.

SITE ENGINEERING ORGANIZATION CHARTL i

TU CLCCTRIC VP/C & C DIR E Cf DR Of COWANCMC PCAE CN GIN C E RIN G j

l I

R l

l 1

s I

l l

l l

l l

l l

STONC & WC85TCR f

CISOS & MILL l

ENGINC E RING CORP.

CBASCO O"" ELL PROJECT WGR, l

Of flC C R Vic t DISTRICT GCNCRAL (cap 3 N CMARGE j

PRC510CNT WANAGCE

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)

f STONC & WCOSTCR WE STINEM OU S C anPCLL CN GIN C C RIN G (NGINEERING CORP.

1 PLANNtNG AND WANAGCWCNT, SITC W ANAS C R 5tfC (PSC)

WANAGCE SNC WANAGER 1

asseomeets som raoviews.o omscem 704 tieosestaneo activities as o* aceto ev int tuse y a smongsameo a coestauctions

..(

E C E ~ l.O l' Rev.0 Date: 3/2/87 Page 7.1

-I of I 4

l

/

FIGURE 7.2 COMANCHE PEAK ENGINEERING ORGANIZATION CHART DIRECTOR OF i

ENGINEERING l

M i

l l

MANAGER OF MANAGER OF MANAGER OF MECHANICAL CIYit ENGINEERING ENGINEERING ENGINEERING ASSURANCE MANAGER 0F MANAGER OF MANAGER ELECTRICAL ENGINEERING OF ENGINEERING PROJECTS WORK TRACKING i

ECE l.Gl Rev. 0 Oct e: 3/2/87 Page 7.2 - I of 1

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h FIGURE 7.3

.y MECHAMiCAL ENGINEERING SECTION ORGANIZATION CHART I

(.

! MANAGER MECHANICAL ENGINEERING W

~

t W. % % -

f' '

MECHANICAL I

MECHANICAL ENGINEERING ENGINEERING SERVICES MANAGER f

(

+

4

\\

Rev.O ECE f.01 D a t e: 3/2/87 Page 7.3 - I or i I

e 1

F;GURE 7.H ELECTRICAL ENGINEERING SECTION ORGANIZATION CHART MANAGER ELECTRICAL ENGINEERING M

i I&C i

ELECTRICAL f

ENGINEERING ENGINEERING MANAGER MANAGER i

)

ECE I.01 Rev. D D a t e: 3/2/87 Page 7.4 - I of l

FIGURE 7.5 CIVIL ENGINEERING SECTION ORGANIZATION CHART i

MANAGER CIVIL ENGINEERING 1

M l

CIVIL PIPING & SUPPORT STRUCTURAL ENGINEERING MANAGER MANAGER i

i i

i l

l l

)

l l

ECE I.01 Rev. D j

0ot e: 3/2/87 Page 7.5 - I of I I

I

4 l

FIGURE 7.5 ENGINEERING ASSURANCE SECTION ORGANIZATION CHART i

l MANAGER ENGINEERING ASSURANCE M

EA EA EA REGUL ATORY SYSTEMS EVALUATIONS COMPLIANCE MANAGER M AP!".GER MANAGER I

l i

l l

i l

ECE l.01 Rev. D Dat e: 3/2/87 i

Page 7.5 - I of I l

l y

l L

FIGURE 7.7 ENGINEERING PROJECTS SECTION ORGANIZATION CHART MANAGER ENGINEERING PROJECTS M

l!

ENGINEERING COMPUTER SUPPORT GRAPHICS MANAGER MANAGER i

i PROJECT PROCUREMENT I

ENGINEERING ENGINEERING MANAGER MANAGER ECE 1.01 Rev.o Date: 3/2/B7 Page 7,7 - I of I

4 i

FIGURE 7.8 ENGINEERING WORK TRACKING SECTION ORGANIZATION CHART MANAGER WORK TRACKING M

l I

SUPERVISING ENGINEER WORK TRACKING l

ECE I.01 Rev.0 Det e: 3/2/87 P a g e 7,8 - I of l

ATTACHMENT 8.A PROCEDURE MATRIX CHANCES IN THE FOLLOWING SECTIONS OF PROCEDURE ECE 1.01 Rev. O MAY AFFECT THE FOLLOWING PROCEDURES / INSTRUCTIONS:

SECTION PROCEDURE / INSTRUCTION IMPACTED 1

6.2 ALL 2

6.3.1.2 ECE 5.05 13, ECE 5.11, ECE 5.11-Il

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3 6.3.2 ECE 5.11 4

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ATTACRMENT 8.B INTENT CHANGE INDEX FORM PROCEDURE NO:

ECE 1.01 REVISION NO.

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f Enclosure D Impell Letter #1M-T-0210-040-238

" Joint Impell/Ebasco Approach Toward Design Verification i

of Inaccessible Attributes i

i May 15, 1987

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I L%PELL CORPORATION i

May 15, 1987 IM-T-0210-040-238 l

TV Electric Comanche Peak Steam Electric Station P.O. Box 1002 Glen Rose, Texas 76043 ATTENTION: Mr. Owen Lowe

SUBJECT:

Joint Impell/Ebasco Approach toward Design Verififcation of Inaccessible Attributes Gentlemen:

Please find attached the " Design Verification of Cable Tray System j

Inaccessible Attributes" position paper.

This doci; ment has been jointly produced by Impell and Ebasco and is the apparcach both contractors use to a

design verify cable tray systems with inaccessible attributes.

This paper has been excerpted from Chapter 6 of the upcoming issue of the " Cable Tray Hanger Design Basis Consolidation Program Project Status Report".

If you have any additional questions, please feel free to call me.

Very truly yours, p

re Kevin C. Warapius Project Manager KCW:SLN: mal Attachment cc: Mr. C.

Mortgat, TERA Mr. S.D. Karpyak, TERA (Site)

Mr. D.J. Kunish, CPRT (Site)

Mr. J.C. Miller, TERA (Site)

Mr. E.

Odar, EBASCO (Site)

Mr. J.'E. Krechting, TV Electric Mr. E.

Alarcon, TV Electric Mr. S.

Harrison, TU Electric Mr. 0.W. Lowe, TV Electric Mr. D.

Reynerson, TV Electric Mr. R.C. Iotti, EBASCO Mr. C. A. Kircher, JBA ARMS,(Site) 300 TRI STATE INTERNATIONAL. SUITE 400

• LINCOLNSHIRE. IL 60015 * (312) 040 2000 L

4 DLSIGN VERIFICATION OF CABLE TRAY SYSTEM INACCESSIBLE ATTRIBUTES I

i 1.0 Introduction 8

This report summarizes the approaches used to design verify f

inaccessible attributes on cable tray systems at Comanche Peak Steam Electric Station.

There are inaccessible design attributes on a significant number of Unit 1 cable tray hanger systems resulting from the presence of fire protection material or from being hidden by other commodities.

On i

Unit 2, fire protection material has_ not yet been installed. As a result, there are few inaccessible design attributes on the Unit 2 cable tray hangers.

A criteria was developed to design verify the cable tray hangers with i

inaccessible attributes.

The qualification approach varies, dependent on the particular attribute.

The approaches which may be.

g used include'

)

An. engineering evaluation using " worst case" conditions.

The

" worst case" conditions have been determined statistically from i

available as-built data or have been determined based on a variation of design parameters.

A review of other design basis documents (e.g. Cable and Raceway Schedule Report No. 30. Reference 1).

A request for additional information (provide attribute accessibility).

4504a 1

e

DESIGN VERIFICATION OF CABLE TRAY SYSTEM INACCESSIBLE ATTRIBUTES The following sections describe the cable tray s9 stem attributes which may be inaccessible and the approaches taken to design verify those attributes.

Figures 1 and 2 illustrate instances of some of these attributes.

2.0 liqldt There are essentially three types of welds which must be. considered in the design verification of cable tray hangers:

fillet, partial penetration, and full penetration welds.

The approaches used to design verify these welds when they are inaccessible are as follows.

(a) Fillet Helds Correction factors are applied to the as-designed connection to reduce the capacity of the weld. These factors were developed to represent the " worst case" weld conditions expected in the field.

The cor% tion factors account 'or the possibility of undersize and underlength weld segment.

The factors may be conservatively applied to the entire connection or may be applied only to the segments which could not be gaged.

These factors have been derived from a sample program of as-built versus as-designed fillet welds (Reference 2).

The correction factors are applied simul'aneously to each_ segment of the as-designed weld.

However, an nstalled weld would. rarely exhibit all worst case conditions simultaneously.

This criteria

^

has been implemented to conservatively bound the potential for installed weld configurations which significantly deviate from the design configuration.

If the corrected weld " fails" design verification, engineering requests that the weld be made accessible.

The actual weld attributes are then recorded and used in design verification.

4504a 2

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DESIGN VERIFICATION OF CABLE TRAY SYSTEM.

j INACCESSIBLE ATTRIBUTES J

The acceptability of this apprbach is proven by comparison of 8

weld stresses based on as-built weld configuration with. the weld I

stresses based on corrected as-designed weld ' configurations of accessible hangers.

.j

-l (b) Partial Penetration Partial penetration welds are typically'used to weld plate. type clamps to the tiers.

The capacity of this clamp type has been established from tests, which simulated the construction conditions using the same weld procedure and groove preparation details.

J Other uses of partial penetration welds'are at cable tray hanger f

post-to-tier and post-to-gusset plate connections. When aLtier l

and post of the same width are butt-joincd. the welded connection may consist of fillet.. welds along the post web and q

two partial penetration welds along the. tier flanges.

The j

fillet welds generally, have sufficient capacit'y to carry the

.]

load.

Similarly, when a gusset plate is welded to a post with a 1

partial penetration weld on one side :often one of the other sides of the gusset plate is' joined with a fillet weld.

The' fillet weld generally has sufficient capacity to carry the load.

a for the joints which do not have sufficient capacity from the fillet welds alone, a study has shown that. design verification can assume a throat thickness equal to one half of the thickness F

~

of the thinnest part joined.

This study is based on ultrasonic examination of a sample of accessible welds of 'the same type.-

(Reference 2).

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DESIGN VERIFICATION OF CABLE TRAY SYSTEM INACCESSIBLE ATTRIBUTES (c)

Full Penetration Helds Full penetration welds are typically used for splicing channel sections.

Since radiography has shown the absence of total 0

penetration, each one of_ these connections will be repaired.

To identify the presence of these welds in posts or tiers hidden by thermolag, thermolag will be removed to the extent necessary to permit ultrasonic or visual examination of the post / tier.

Ultrasonic examination can be used to identify the presence of

{

splice welds in C4 or equivalent channels up to 62 inches in

)

length and in larger channels up to 84 inches in length.

Longer members will have sufficient thermolag removed for visual inspection.

In all cases, these splice welds will be repaired.

3.0 Eember Sizes l

Statistical study of a sample of accessible CTHs shows that it is a

appropriate to use the as-designed member size when the member size is inaccessible.

For inaccessible members, if an "HC" type channel j

is specified the next heavier "C" section is checked, if the section I

properties are less conservative.

4.0 Member Dimensions Member dirrensions were found, within the tolerances specified for design verification, from the as-designed dimensions while utilizing 4504a 4

DESIGN VERIFICATION OF CABLE TRAY SYSTEM INACCESSIBLE ATTRfBjjJ11 H

the as-buielt dimensions 'of the thermolag conservatively.. If the approximation made on the basis of.the thermolag dimensions.resulted 4

in failure of the hanger, thermolag was removed and the actual member dimension verified.

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5.0 Irav Location The tray location is conservatively determined byJconsidering the j

thermolag/thermoblanket outline dimensions and a conservative thickness of the fire protection material. Another acceptable method of determining tray location is thermolag removal.

6.0 Trav Size and Fill Tray size is determined from:

Walkdown of accessible portions of the tray, G&H Cable Schedule 2323-EL-1700, " Report Section 30", and/or tray segment drawing.

These controlled documents provide tray ~ size and cable fill.

If actual tray fill for a particular tray segment cannot be determined, maximum tray fill can be used, thermolag can be i

removed, or the higher tray fill of the two' segments is used.

7.0 Anchoraaes Anchorages are approached in three ways depending on the degree of' inaccessibility.

.1 (a)

For comp 1.etely inaccessible anchorages as-built information was acquired by removing the thermolag or from a record of inspection which documents an ultrasonic test.

If'the thermolag 4504a 5

DESIGN VERIFICATION OF CABLE TRAY SYSTEM INACCESSIBLE ATTRIBUTES i

4 was removed, the IA was removed from the final as-built drawing, but, if a record of inspection document.was used, the IA is still shown on the final as-built drawing.

(b) For partially inaccessible anchorages, dimensions are assumed so as to maximize the stress in the bolts and base angle or base-f plate.

If the anchorage fails on this basis, information is obtained as in (a) above.

1 (c) For partially inaccessible expansion anchors of known diameter but unknown Hilti type (i.e. HKB or HSKB), it is assumed that the type is the lower capacity HKB bolt.

As a result, a minimum number of anchorages require assumptions to be made, because most edge distances and gage lengths for anchorages are i

made accessible or the embedment is determined by ultrasonic testing.

8,0 Itav Clamos i

For inaccessible tray clamps, the design verification program assumes

.i the lower bound clamp allowables as specified in the project instructions.

To accomplish this, the clamp type (multidirectional or transverse) must first be determined.

The clamp type is determined from support function.

For transverse supports, the worst case C-type clamp allowables are used.

For multidirectional clamps, a one bolt connection to the tray is used.

If the clamp fails due.to j

this assumption, it will be made accessible.

9.0 Bolt Hole / Edge Distances A statistical study of bolt hole diameters and edge distances (Reference 3) provides information on the appropriate assumptions to 4504a 6

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l' DESIGN VF,8]flCATION OF-CABLE' TRAY SYSTEM' INACCESSIBLE ATTRIBUTES:

4 be made regarding bolt hole. diameters and edge distances in i

anchorages,. posts, tiers, and clamps.

For tier-members.:this study' has shown, the maximum bolt hole size to be -3/4 inches.. This' is' tte upper bound hole diameter for the S/8 inch bolts used to' connect the clamps to the tier.

The study also shows this hole size to be. the' maximum unused bolt hole' size.

A bolt hole of-this dimension is i

assumed by design verification to occur in the tier. flange at the maximum stress location..If this assumption results in a. tier failure, the tier is.made accessible and the actual location of the -

bolt hole is considered.

Design verification of CTH tier members makes lower bound edge distance assumptions as dictated by a-statistical study (Reference 3) when edge. distances are IA..for.

anchorages, lower bound assumptions for edge distances.(for prying) are made.

Failure to pass the support with these assemptions results in thermolag removal to determine actual' edge distances.

10.0 Plumbness & Levelness Thermolagged support profiles are sufficiently accurate to determine support post plumbness.

If a. thermolagged support profile shows out of plumbnoss, the thermolag is ' removed and the plumbness verified.

Oct of plumbness up to 2* has insignificant impact on-design verification.

Supports-checked by field engineering showed very fewL hangers to be out-of-plumb and then'only by_a fraction of a degree.

I Similarly, levelness can be seen on a thermolagged support.

There has been no indication of unacceptable levelnessIin any field engineering measurements.

Small variations in levelness have insignificant impact on design verification.

3 11.0 Trav Solices The approach relies on walkdown of Unit'1 and 2 to identify:

t

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DESIGN VERIFICATION OF CABLE TRAY SYSTEM ItMCGESSIBLE ATTRIBUTES 4

(a)

Type of splice used.

If the splice type is different from the manufacturer recommended splice, the configuration of splice (shape, plate thickness, number of bolts, flanged) is obtained.

1 (b) Gap between tray segment l

I Once sufficient walkdowns are performed to identify all j

representative splice types, the splice plates will be grouped and i

the gap distribution determined.

Lower bound splice plates representing each group will be tested to determine if the presence of the splice plate decreases the tray capacity.

With the exception of splice plates at transitions between tray sizes, analytical studies predict that the splice plates do not control tray capacities.

If tests show that splice plates weaken the tray j

capacity, then the tray will be qualified with reduced allowables or the splices will be modified.

For hidden transitions, thermolag would be removed to verify if the splice plates are of the type requiring modification.

12.0 Tray Fittinas Capacities of tray segments and tray fittings have been established by the tray manufacturers and/or independent tests conducted at CCL.

For T. J. Cope T-fittings, however, a concern of the acceptability of the welding exists as identified in SDAR 85-50.

For inaccessible T-fittings, thermolag will be removed to determine presence of minimum required welding.

If welding is found deficient, the Tuftttings will be repaired or replaced to restore its capacity.

4504a 8

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DESIGN VERIFICATION'0F CABLE TRAY' SYSTEM INACCESSIBLE ATTRIBUTES 13.0 Base Metal Defects l'

i Analyses of a sample of accessible cable tray hangers, (Reference 4) shows that base metal defects can be ignored in the design verification process.

The referenced study examined mechanical abrasion, weld gouging and weld undercut and found the effects of these conditions to be negligible.

14.0 Tvoe I Modifications (TMF)

Type I modifications (TMF) are construction deviations identified.

during +ha as-bui.it walkdown that will be 'orrected to match the c

as-buiit drawing. There are nine kinds of Type I modifications.. The nature of TMF's is such that they have no adverse effect on design-verification if left unt. ;hed.

Therefore, these deviations hidden by thermolag are of no concern.

The Type I modifications are:

(a) Gaps at anchorages (between the member and concrete). These are I

filled by grouting.

They represent 50% of;all TMF's. Most anchorage base members are accessible, even though the bolts may be IA because of thermolag extending from the post, and are included in TMF's.

(b) Bevel washers, which represent 30% of the TMF's.

The washers were installed upside down.

This condition has no impact on design verification.

(c) Unused bolt holes in concrete representing 1% of TFM's.

This condition has no impact on design verification.

I (d) Incorrect bolt material representing 1% of the TFM's.

Bolt material was A307 instead of A325.

This condition has no impact j

since design verification assumes A307.

i 4504a

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' DESIGN VERIFICATION OF CABLE' TRAY SYSTEM 4

. INACCESSLSLE ATTRIBUTES (e) Unplugged bolt holes in mepbers representing 1% of TMF's.

Th'e -

H I

statistical study on bolt-holes, (Reference 3) showed that.the maximum unused bolt hole. size in tiers is 3/4 inch.

This h'le o

size is assumed in all tier members.

'1 (f) Loose bolts representing 1% of TMF's.

These' bolts are tightened!

as good practice, but if left loose, the system performance would not be affected as demonstrated by the ANCO tests

')

(Reference 5).

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(g) Tray and Clamp gaps - 12% of TMF's' - There are instances where '

)

the combined gap between the tray and the tier and tray and 1

clamp exceeds specified limits (generally 3/8").

These.

instances are shimmed to provide an overall " tight" system.- The

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ANCO tests (Reference 5) have shown clamp gaps to have no impact f

on system behavior.,

(h) Heep Holes - Only one instance has been found where'the hole-was missing from a closed section, and there was no impact on design verification.

(i) Hilti Hashers - missing Hilti washers are'added.

There is no impact on design verification-since bearing of the base member against the nut would provide the necessary load transfer.

15.0 References 1.0 Gibbs 16 Hill Cable Schedule 2323-EL-1700 " Report Section 30 -

Raceway Percent Fill'" 12/3/85/

s 2.0 Volume I Book 20 "CTH Held Related Studies" - Sections II thru IV - Later.

4504a 10

.g DESIGN VERIFICATION OF CABLE TRAY SYSTEM INACCESSIBLE ATTRIBUTES L

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3.0 Volume I Book 22 " Statistical Study of Bolt Hole Edge Distances in.CTH's" - Later.

i 4.0 Volume I " Position Paper on Base Metal Defects in Thermalagged i

Cable Tray Hangers" - Later.

5.0 ANCO Report 1806.016, " Final Summary Report, Comanche Peak Cable 1

Tray Tests", Rev. O.

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l Enclosure E Impell Letter #IM-T-0210-040-239 Clarification of Impell CTH Design Verification Criteria / Methods for Resolution of CYGNA Audit Concerns I

May 15, 1987

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IMPELLO e,

CORFORADON May 15,1987 j

IM-T-0210-040-239 i

Texas Utilities Electric Company P.O. Box 1002 Glen Rose, TX 76043 1

j ATTENTION: Mr. 0.W. Lowe l

SUBJECT:

Clarification of Impe11 CTH Design Verification Criteria /

Methods for Resolution of CYGNA Audit Conerns Gentlemen:

Please find attached, a series of position papers which are intended to provide clarification of the Impe11 CTH design verification criteria / methods.

These papers have been prepared in response to concerns raised by CYGNA during their audits of Impell calculations during the past months.

These papers provide discussion of the concern, background for information pertaining to the concern and its resolution, discussion of resolution of the concern, and conclusions including discussion of significance related to the design adequacy of the cable tray hangers.

The specific concerns addressed by the attached papers are:

1.0 Impact of SUPERPIPE Error SP-004 on Evaluation 176-063-02 3

2.0 Seismic Load Combinations.

3.0 Analysis of Welds Connecting Base Angles to Embedded Plates.

4.0 Safety Margin Against Buckling Using AISC Factored A110wables.

5.0 Evaluation of Composite T-Channel Stitch Welds for Torsional Stresses.

6.0 Effects of Thermal Loading on Cable Tray Systems.

7.0 Member Substitution in Impe11 Support Calculation CTH-1-13197

' 8.0 Lateral Bracing of Tier Members in Impe11 Support Calculation CTH-1-1227, 9.0 Effect of Measurement Tolerances used for Collection of As-built Data.

10.0 Criteria for Single Angle Design.

300 TRI STATE INTERNATION AL, SUITE 400

• LINCOLNSHIRE. IL 60015 * (312)940 2000 AEC'O MKl 201987

Le May 15 1987 IM-T-0E10-040-239

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Page Two a

The information provided in these papers should be sufficient to facilitate CYGNA's review and resolve their audit concerns.

Please call me if you have any questions.

Very truly yours, g

/"ee-

.wvin C. Warapius Project Manager KCW:GRA:td1 Attachments cc:

Mr. L.D. Nace Mr. J. Muffett (w/att.)

Mr. S.W. Harrison (w/att. )

Mr. E. Alarcon Mr. D.M. Reynerson Mr. E. Odar (Ebasco) Site (w/att.)

l Mr. J. Padalino-(Ebasco) (w/att. )

ARMS (Site) (w/att. )

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I IMP,EL(@

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