ML20236E693

Rev 2 to Engineering Organization & Operating Procedures, TVA Employee Concerns Special Program

ML20236E693
Person / Time
Site:	Sequoyah
Issue date:	10/17/1987
From:	Leslie J, Walters R TENNESSEE VALLEY AUTHORITY
To:
Shared Package
ML20236E191	List: ML20236E186 ML20236E237 ML20236E273 ML20236E282 ML20236E287 ML20236E291 ML20236E294 ML20236E298 ML20236E304 ML20236E309 ML20236E325 ML20236E329 ML20236E350 ML20236E496 ML20236E516 ML20236E613 ML20236E618 ML20236E649 ML20236E657 ML20236E672 ML20236E675 ML20236E693
References
20400, NUDOCS 8710290317
Download: ML20236E693 (186)

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{{#Wiki_filter:- _-. _ _ 1 TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 I SPECIAL PROGRAM REPORT TYPE: SUBCATEGORY REPORT FOR REVISION NUMBER: 2' ENGINEERING TITLE: . ENGINEERING ORGANIZATION AND Page 1 of S1 OPERATING PROCEDURES REASON FOR REVISION: 1 1. Revised to incorporate SRP and TAS comments, and BFN and BLN corrective actions. 2. Revised to incorporate SRP and TAS comments and add Attachment C -(References). PREPARATION PREPARED lBY-$YA $ Wb ># /o-/74 7 1 SIGN DATE V REVIEWS -C IEH COMMITTEE-JY N/l]!b] '/ ' o. ~ SIGN URE // ~ ~ OATE TAS: SIGNATURE DATE CONCURRENCES CEG-H SRP: SIGNATURE DATE SIGNATURE" DATE APPROVED BY: ECSP MANAGER DATE MANAGER OF NUCLEAR P0HER DATE CONCURRENCE (FINAL REPORT ONLY) SRP Secretary's signature denotes SRP concurrences are in files.

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 [. SPECIAL PROGRAM REVISION NUMBER: 2 ). Page ES-1 of 2 k l EXECUTIVE

SUMMARY

4 Subcategory Report 20400 summarizes and evaluates the results of 27 element evaluations prepared as part of the Engineering _ category of the Employee The element evaluations cover the subcategory l Concern Special Program. l Engineering Organization and Operating Procedures and address the 36 employee l concerns that cite perceived deficiencies and inadequacies in the TVA 1 engineering-organizational structure or operating procedures (design process), as well as the cuality of the output documentation. The employee concerns identified 123 issues, which are addressed in the element evaluations and which are related to TVA's four nuclear plant sites. The evaluation team examined the 123 issues raiseo by employee' concerns and-evaluated their relevance to applicable regulations, requirements, and accepted industry standards. The team found that 72 issues required no i corrective action and that 51 were problems of which TVA was already aware and Only one new corrective action was required was in the process of resolving. and that was to resolve a peripheral finding identified during the ECTG evaluations. This report identified deficiencies in TVA's organizational structure in that responsibilities for nuclear activities were divided among several departments Design change procedures and that reported to separate managerial structures. . procedures to control' vendor documents were not f ollowed, were sometimes cumbersome and lengthy, and sometimes did not provide information or instructions to accomplish tasks as they should be 'done. Also, design reviews were not always conducted when needed, nor were they sufficient to identify i design specifics that should have been changed. The substantiated issues indicate the need f or increased and continued management: attention to the engineering design processes and for increased Division of Nuclear Engineering (DNE) involvement in plant modifications. Engineering Assurance (EA) auditing will provide some assurance of compliance with.various practices by providing feedback to management on engineering Monitoring of the engineering products on a day-to-day basis is i perf ormance. the responsibility of engineering line management. The latest DNE procedures ] are augmented by site-specific procedures that, when properly f ollowed, ~ I provide a means to mitigate many of the engineering design process problems of Management attention should also be directed to provide adequate the past. staffing to allow careful review and checking of the engineering work and the design documents as they evolve. The organizational changes that have been made, especially to strengthen the Branch Chiefs' technical review responsibilities and the Quality Assurance and EA organization, provide a reasonable means to monitor the engineering design process and adherence to procedures. A review of TVA nuclear performance plans (NPPs) at the corporate level and for the Sequoyah (SQN), Browns Ferry (BFN), and Watts Bar (WBN) nuclear 28110-R25(10/15/87)

i TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVlSION NUMBER: 2 Page ES-2 of 2 l \\ l plant sites reveals that TVA recognized problems and deficiencies in the nuclear organizational structure and in the engineering operational procedures. Currently, there is no site-specific NPP for the Bellefonte plant, which is several years away from completion of design and construction. The NPPs describe the deficiencies and the corrective acticas at the corporate level and at the plant sites for SQN, BFN, and WBN. Of significance are the consolidation of all engineering design functions into a single organization with a single set of nuclear engineering department procedures (NEPs) and the strengthening of the quality assurance (QA) These procedures are to be augmented by plant-specific engineering program. procedures. The corrective actions described, when fully implemented, should help to resolve the identified problems and help to prevent their recurrence. The collective significance of the findings is that if the organizational and procedural changes had not been implemented, the mismatch between the plant configuration and the engineering drawings and other documents could have i persisted and could have resulted in an engineering design or plant operating error. The grouped evaluation at the subcategory level d-id not find an.y new or broader issues requiring attention. The causes identified and other evaluation results are being reexamined from a wider perspective during the Engineering category evaluation. 9;, - 1 4 2811D-R23 (10/15/87) 3

1 Preface, Glossary.'and' List'of Acronyms, for'ECTG Subcategory Reports I HISTORY OF REVISION ~ HEV -NUMBER PAGES REVISED REASON FOR CURRENT-REVISION - - - = ji 3 i To clarify that one or more _ attachments will help the reader. ) ' find where's particular concern is evaluated f i ~ q . j i S i I 9 L l

-TVA EMPLOYEE CONCERNS . REPORT NUMBER: '20h00-SPECIAL PROGRAM FRONT MATTER REY: '3 PAGE l'0F viii-3 o Preface This subcategory report is one of a series of reports prepared for the - Employee Concerns Special Program (ECSP) of the Tennessee Valley Authority (TVA).,'The'ECSP and the organization which carried out the program, the Employee. Concerns Task Group (ECTG), were established by TVA's. Manager of . Nuclear Power.to evaluate and report on those Office of_ Nuclear Power (ONP)_ 1 employee concerns filed before February 1.-1986. Concerns _ flied after that. 1 date are handled by the ongoing ONP Employee Concerns Program (ECP). The ECSP. addressed over 5800' employee concerns. Each of the; concerns lwas s' formal, written' description of a circumstance or circumstances that an-l employee thought was. unsafe, unjust._ inefficient, or inappropriate. ' The' mission'of the Employee Concerns Special Program was to-thoroughly investigate all issues presented in the concerns and to report the results of-those' investigations'in a form accessible to.ONP employees,.the NRC, and the general public. The resvits of these investigations are communicated. by four levels'of ECSP reports: element,. subcategory, category, and. final.- Element reports, the lowest reporting level will be published only.for- . those concerns _directly affecting.the restart of Sequoyah' Nuclear Plant's-reactor unit.2. An element consists of one or more closely related issues. 'An issue is a potential problem identified by ECTG during the 1 evaluation' process as having been raised,in one or more concerns.. For 1 ' efficient handling, what appeared to be.similar concerns were grouped into elements early in the program, but. issue definitions emerged from the evaluation process itself. Consequently, some elements did include only one issue, but often the ECTG evaluation found more than one. issue per element. Subcategory reports summari'ze the evilurtion of a number'of elements. 1" However, the subcategory report does more than collect element level evaluations. The subcategory level overview of element findint,s leads to an integration of information that cannot take place at the element level. -) This integration of information reveals the extent to which problems . overlap more than one element and will therefore require corrective action j for' underlying causes not fully apparent at the element level. J To make the subcategory reports easier to understand, three items have 'een b placed at the front of each report: a preface, a glossary of the terminology unique to ECSP reports, and a list of acronyms. Additionally, at the end of each subcategory report will be a Subcategory Summary Table that includes the concern numbers; identifies other subcategories that share a concern; designates nuclear safety-related. safety significant, or non-safety related concerns; designates generic 4 applicability; and briefly states each concern. Either the Subcategory Summary Table or another attachment or a combination of the two will enable the reader to find the report section or sections in which the issue raised by the concern is evaluated.

E .) TVA EMPLOYEE CONCdRNS . REPORT NUMBER: 20400' p' SPECIAL PROGRAM PRONT MATTER REY: 2 PAGE'il 0F vill .The subcategories are themselves summarized in a series of eight category reports. Each category report reviews the major findings and collective-significance of the-subcategory reports in one of the following areas: ) management and personnel relations Industrial safety U l L . construction { material control l-operations quality assurance / quality control-i welding engineering 1 A separate report on employee concerns-dealing with specific contentions of intimidation, harassment, and wrongdoing will be released by the TVA Office j of the Inspector General. i .1 Just as the subcategory reports integrate the information collected at the I element level, the category reports integrate the information assembled.in l all the subcategory reports within the category, addressing particularly i' the underlying causes of those problems that run across more than'one subcategory. l 'A final report will integrate and assess the information collected by all 1 of the lower level reports prepared for the ECSP, including the Inspector General's report. I For more detail on the methods by which ECTG employee concerns were evaluated and reported, consult the Tennessee Valley Authority Employee Concerns Tast Group Program Manual. The Manual spells out the program's l l' objectives, scope, organization, and responsibilities. It also specifies l the. procedures that were followed in the investigation, reporting, and l closecut of the issues raised by employee concerns. t.- i l I i i l ) I L 1 l L.__m___

_7 q 4 I 1 o 1 ITA EMPLOYEE CONCERNS ' REPORT-NUMBER: ~20400' SPECIAL PROGRAM l FRONT KATTER REV: 2- -l ~ PAGE'111 0F vill ECSP GLOSSARY OF REPORT TERMS * 'l classification ~of' evaluated issues the evaluation of an issue leads to one of l I

the-following determinations-1 i

' Class A: : Issue cannot-be verified as factual .i Class B: Issue is factually accurate, but what is described is not a-problem (i.e., not a condition requ' icing corrective action)- C1'ss C: Issue is factual and identifies a problem, but corrective action a for the problem was initiated bstore the evaluation of the issue was undertaken -l ~ o Class D:- Issue is factual and presents a problem for which corrective-1 action has been, or is being. taken as a result of an' evaluation-q Class E: A problem, requiring corrective. action, which was not' identified by an employee concern, but' was ' revealed during the ECTG -evaluation of an issue raised by an employee concern. collective significance an analysis which determines the importance and consequences of the-findings in a particular ECSP report by putting those findings in the proper perspective. ' concern (see " employee concern") corrective action steps taken to fix specific deficiencies or discrepancies revealed by a negative finding and, when necessary, to correct causes in order to prevent recurrence. ~ criterion (plural: criteria) a basis for defining a performance, behavior, or quality which ONP imposes on itself (see also " requirement"). element or element _ report an optional level of ECSP report, below the . subcategory level, that deals with one or more issues, employee concern-a formal, written description of a circumstance or circumstances that an employee thinks unsafe, bnjust, inefficient or 1 [ inappropriate; usually documented on a K-form or a form equivalent to the l K-form. 4 e

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 l' .SPECIAL PROGRAM l FRONT MATTER REV: 2 l l L PAGE iv 0F vill l-evaluator (s) the individual (s) assigned the responsibility to assess a specific grouping of' employee concerns. i 1 findings includes both statements of fact and the judgments made about those facts during the evaluation process; negative findings require corrective action. issue a potential problem, as interpreted by'the ECTG during the evaluation process, raised in one or more concerns. I K-form (see " employee concern") requirement a standctd of performance, behavior, or quality on which an evaluation judgment or decision may be based, root cause the underlying reason for a problem. ' Terms essential to the program but which require' detailed definition have been defined in the ECTG Procedure Manual (e.g., generic, specific, nuclear . safety-related, unreviewed safety-significant question). t + I t. (

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM FRONT MATTER REY: 2 PAGE v 0F vill Acronyms AI Administrative Instruction AISC American Institute of Steel Construction ALARA As Low As Reasonably Achievable ANS American Nuclear Society ANSI American National Standards Institute ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials AWS American Welding Society BFN Browns Ferry Nuclear Plant BLN Bellefonte Nuclear Plant CAQ Condition Adverse to Quality CAR Corrective Action Report CATD Corrective Action Tracting Document CCTS Corporate Commitment Tracting System CEG-H Category Evaluation Group Head l CFR Code of Federal Regulations CI Concerned Individual CMTR Certified Material Test Report COC Certificate of Conformance/ Compliance DCE Design Change Request DNC Division of Nuclear Construction (see also NU CON) 9 m

9 TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 I SPECIAL PROGRAM FRONT MATTER REY: 2 PAGE vi 0F vill .1 DNE Division of Nuclear Engineering .DNQA' Division of Nuclear Quality Assurance DNT Division of Nuclear Training DOE Department of Energy. DP0 Division Personnel Officer DR Discrepancy Report or Deviation Report ECN Engineering Change Notice - ECP Employee Concerns Program i ECP-SR Employee Concerns Program-Site Representative ECSP Employee Concerns Special Program ] - ECTG-Employee Concerns Tast Group EEOC Equal Employment Opportunity Commission l EQ Environmental Qualification EMRT Emergency Medical Response Team EN DES Engineering Design ERT Employee Response Team or Emergency Response Team FCR Field Change Request FSAR < Final Safety Analysis Report FY Fiscal Year GET General Employee Training HCI Hazard Control Instruction g, HVAC Heating, Ventilating, Air Conditioning i II Installation Instruction INPO . Institute of Nuclear Power Operations IRN Inspection Rejection Notice i_---,-----------a-

I ^

f TVA EMPLOYEE CONCERNS REPORT NUMBER:

20400 SPECIAL PROGRAM FRONT MATTER REVi 2 7 PAGE vil 0F viii ' L/R Labor Relations Staff M&AI Modifications and Additions Instruction MI Maintenance Instruction - MSPB Merit Systems Protection Board MT Magnetic Particle Testing NCR Nonconforming Condition Report NDE Nondestructive Eranination NPP Nuclear Performance Plan NPS Non-plant Specific or Nuclear. Procedures System RQAM Nuclear Quality Assurance Manual 4 NRC Nuclear Regulatory Commission r,. NSB Nuclear Services Branch NSRS Nuclear Saf$ty Review Staff NU CON Division of Nuclear Construction (obsolete abbreviation, see DNC) NUMARC Nuclear Utility Management and Resources Committee OSHA Occupational Safety and Health Administration (or Act) ONP Office of'iluelear Power OWCP Office of Workers Compensation Program PHR Personal History Record b PT Liquid Penetrant Testing" QA Quality Assurance 5, QAP Quality Assurance P;ccedures QC Quality Control QCI Quality Control Instruction .(. .e

. f '.. - li,. ~ _9r g. v> TVA EMPLOYEE COWCERNS i,'.. f REPORT NUMBER:.20400 SPECIAL PROGRAM u-FRONT MATTER REV: 2 - Q. [ PAGE vill 0F viii ( J. QCP . Quality Control. Procedure ~{ QTC Ouality Technology Company j -l RIF - Reduction in Force ) l RT Radiographic Testing SQN Sequoyah Nuclese Plant p- '. 5 [. t SI Surveillance Instruction 4 SOP. Standard Operating Procedure l V SRP-Senior Review Panel SWEC - Stone and Webster Engineering Corporation .g TAS Technical Assistance Staff. e T&L Trades and Labor I, f /- TVA-Tennessee Valley Authority e ~ TVTLC-Tennessee Val y Trades and Labor Council" UT Ultrasonic Testing VT-Visual Testing ,, p. - WBECSP Watts Bar Employee Concern Special Program ( 4' y. WBN Watts Bar Nuclear Plant WR Wort Request or Wohk Rules 'l WP Workplans f:. f t. ,/ t ) _. '} t q, ( y.- k l l-q ( L 1 f ,? s l 4 i L. N: . _ - _ _ _. _a.

~'l% 4 / -TVA' EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 ' i d', - l i Page 2 of 51 " a._. L l \\ \\ k } a 1 -Q CONTENTS l 4 ,/ il >y j 14, j SectioM Paae i ) v s g Eiequ. tive $,im.rsy ES-1 ] Preface n, i 3 t ECSPG1csarycpReportTerms lii i Acronyms v i I fj 1 Introducti$9 3 ,s Dllb 2 Summary cf Issues / Generic Applicability 4 t 3 Evaluttion' Process 7 4 Findings 9 I t '" ;5 Corrective Action 1 ' 35 i 10 Causes (1 40 o s i l r7 Collective Significance 41 V o 'A Glossary N;plement foi'.the Engineering Category 49 j Attachtrang , -l C q l t : a f." A Employee Concerps' for Subcategory 20400 A-1 j i 'l B Summary of Issues, Findings, and Corrective Actions B-1 i ,s for Subcategory 20400 ~) C References C-1 , y,, 1 '} s '\\ TABLES (. Pace S. Table a 1 Classification of Sindings and Corrective Actions, 44 l 2 Findings Sumary 'i 46 4 3 Matrix of Clements, Corrective Actions, and Causes 47 v' f x 'x v v~ i 23iiD-RZ4; \\ (10/15/87) \\ u ~ c

TVA EMPLOYEE CONCERNS REPORT ~~ NUMBER: 20400 SPECIAL PROGRAM: REVISION NUMBER: 2. Page 3 of 51 1. INTRODUCTION' l ~This subcategory report summarizes and evaluates the results of the ECSP . element evaluations prepared under Engineering Subcategory 20400, Engineering Organization and Operating Procedures. The employee concerns provide the basis for th_e element evaluations and are listed by element number in Attachment A. The plant location where the concern was originally identified and.the applicability of the concern to -other TVA nuclear plants are also.shown. .The employee concerns cite perceived deficiencies in TVA's organizational structures, interdepartmental communications, methods of, handling design review, and engineering design processes. The concerns also cite perceived deficiencies in the procedures and other documents that govern the engineering design change and plant modification processes. Between 09/73 and the present time, three different sets.of engineering department procedures have been used to address such requirements as checking, i review. approval, issue and revision of engineering drawings and documentati_on. -The deficiencies ~ described in this subcategory report. relate to complicated and ineffective procedures that resulted in poor review cycles, divided responsibilities, poor test and installation specifications, drawings lacking in engineering detail, poor design review and verifi::ation i requirements, and illegible vendor information. Revision 8 of TVA Topical; Report TVA-TR75-1A, which is the Quality Assurance Program Description for the Design, Construction, and Operation of TVA Nuclear Power Plants, was the revision available when the element evaluations for this subcategory were written. Revision 9 of the Topical. Report has been assessed, Jbut does not alter the findings and. conclusions of these evaluations. The evaluations are summarized in the balance of this report as follows: o Section 2 -- summarizes, by element, the issues stated or implied in the employee concerns and addresses the determination of their generic applicability o. Section 3 -- outlines the process followed for the element and l subcategory evaluations and cites documents reviewed l o Section 4 -- summarizes the findings by element, and identifies those negative findings that must be resolved o. Section 5 -- highlights the corrective actions required for resolution of the negative findir.js cited in Section 4 and relates them to each element and to each plant site 28110-R26 (10/15/87) t I

l TVA EMPLOYEE CONCERNS REPORT ~ NUMBER: 20400 SPECIAL' PROGRAM REVISION NUMBER: 2 L Page 4.of 61' I Section 6 -- identifies.causes of the negative findings ~ o Section 7 - assesses the significance of the negative findings !!l' o Attachment A -- lists, by element, each employee concern. evaluated o' The concern's number is given along with in the subcategory. notation of any other subcategory with which the concern is shared. t and the plant sites to which it could be applicable. The concern is quoted as received by TVA, and is characterized as safety related (SR), safety significant (SS) or not safety related (NO) !^ Attachment B -- contains a summary of the element-level Each issue is listed, by element number and plant, o evaluations. along with its ' corresponding findings and corrective actions.. -The reader may trace.a concern from Attachment A to an issue in Attachment B by using the element number and applicable plant..The f l reader may relate a corrective action description in Attachment B to causes and significance in Table 3 by using the CATD number which appears in Attachment B in parentheses at the end of the corrective action-description. The term " Peripheral finding" in the issue column refers to a finding that occurred during the course of evaluating a concern but These are classified did not stem directly from a employee concern. as "E"-in Tables 1 and 2 of this report Attachment C -- lists the references cited in the text o 2.

SUMMARY

OF ISSUES / GENERIC APPLICABILITY The employee concerns listed in Attachment A for each element and plant have been examined, and the potential problems raised by the concerns have been identified as 123 separate issues. Evaluation of these issues is presented in .i 27 element evaluations. However, some All of the elements were evaluated for the four nuclear plants. of the individual elements were combined with others at certain plants to f acilitate evaluation, review, and preparation of corrective action plans. 204.1, 204.2, and 204.8 had individual element For example, elements evaluations prepared for SQN, while they were combined and addressed under Table 1 of this report element evaluation 204.1 for the other three plants. shows which evaluations addressed each of the elemen3s at each of the plants. } 2.1 Generic Applicability Nine employee concerns, of the total of 36 addressed in this subcategory, are Rather, they are not generically applicable to all four nuclear plants. related to site-specific organizations, components, or situations, and, thus, are. addressed..in the element evaluations only on a site-specific basis. lL i 2811D-R26 (10/15/87) t i

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 5 of 51 Element 204.1. Concern WI-85-047-001 dealt with.the. lack of a timely response .from engineering for instrument set point data for a specific WBN system. Element 204.4. Concerns IN-85-414-003, EX-85-085-002, and IN-85-276-002 dealt with possible shortcomings (e.g., specific instruments not shown on a drawing) in specific WBN engineering drawings. Element 204.5. Concern I-86-114-BFN dealt with an Office of-Engineering (0E) review of the staffing level and adequacy of the training of engineering-personnel at BFN to handle the known BFN workload.' Concern HI-85-077-N02 ' dealt with documentation concerns regarding original procurement specifications for BFN. Concern XX-85-126-001 dealt with changes being made to vendor drawings specific to BLN without prior approval of the vendor. Element 204.6. Concern WBP-85-018-003 dealt with a specific group of engineering change notices (ECNs) for WBN. Concern OE-QMS-5 questioned a decision by the BFN Engineering group management regarding handling of ECN data sheets at BFN per the BFEP procedure. The remaining 27 employee concerns were generically applicable to all four nuclear plants, and they were addressed accordingly.' 2.2 Summary of Issues The issues evaluated under this subcategory are grouped by element, are I summarized below, and apply to all four nuclear plants unless' otherwise noted: 1 o 204.1, Organizational Structure - TVA's organizational structure is unwieldly; there are too many people in the review cycles,' too many procedures, and too much paperwork. WBN field requests for technical information from Engineering are not answered in' a timely manner. o 204.2, System Desian Responsibility - Individual engineers are not knowledgeable of, or responsible for, overall system design. o 204.3, Field versus Desian Office Responsibility - TVA leaves too many technical decisions regarding pipe supports and hangers up to craft personnel. o' 204.4, Desian Document Completeness /Adeouacy - There are deficiencies in engineering drawings. TVA designs are not developed well enough and do not adequately encompass constructibility, maintainability, testability,andoperabilityrequirements. TVA l general construction specifications (G-Specs) are often inadequate, l and drawings do not always show all the details or represent design requirements. 9 i 2811D-R26 (10/15/87) l l \\ \\ L____

-i j TVA EMPLOVEE CONCERNS REPORT NUMBER: 20400 j SPECIAL PROGRAM REVISION NUMBER: 2 Page 6 of 51 o 204.5, Desian Review / Verification - Various engineering documents at i TVA, including vendor calculations and designs, are not f appropriately reviewed under an adequately controlled design process. Second independent technical reviews are not completed, and some reviews are not performed by qualified personnel. There is i inadequate staffing of engineering personnei at BFN, which could . result in insufficient review of engineering documentation; design engineers did not document the original specifications at BFN; and changes were made to BLN vendor _ drawings without vendor approval. o 204.6, ECN Process -' Engineering change notices (ECNs) are not i written with sufficient information and are not properly processed, tracked, or closed out. Consideration is.not given to the impact of the change on other disciplines, documents, and construction work. o 204.7, Vendor Docaents - Vendor manuals in use at the plant sites - are not at the correct revision level, and vendor drawings are of poor quality. 1 l o 204.8. Communication and Interf ace Control - Communication and interf ace control within Engineering, and between Engineering and other organizations, are ineffective. o 204.9, Use of Reverse Prints - Unit 1 prints marked " opposite hand" are being used for unit 2, which makes work more confusing for l engineering and construction personnel. The nine issue summaries above (one for each element) deal with presumed deficiencies in the Engineering organization and the design process and 4 l procedures. More specifically, four of the elements contain issues that are concerned with the overall engineering process (elements 204.1, 204.3, 204.5, and 204.8), three deal with design process and design changes (204.2, 204.6,. and 204.9), and two pertain to design output documentation (204.4 and 204.7). As the.following sections show, five of the issues summarized by element above were found to be valid and require corrective actions (204.1; 204.5, [for BFN l only]; 204.6; 204.7; and 204.8). One of these involves establishing l engineering interfaces and improving organizational procedures, three involve engineering verification procedures and design change control, and one involves quality and dissemination of vendor documentation. 1 Each issue examined within the element evaluations is stated fully in Attachment B, which also lists the corresponding findings and corrective actions that are discussed in Sections 4 and 5 of this' report. l 28110-R26 (10/15/87) l 1

i TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 l Page 7 of 51 3. EVALUATION PROCESS This subcategory report is based on the information contained in the applicable element evaluations prepared to address the specific employee concerns related to the issues summarized in Section 2. The element and subcategory evaluation process are discussed below. The references cited are listed in Attachment C. 3.1 Element Evaluation Process The steps listed below were followed to evaluate issues for each of the element evaluations. a. Defined issues for each element from the employee concerns. Attachment A of this report lists the employee concerns addressed in this subcategory report. b. Reviewed regulatory documents (Refs.1 through 8,15, and 16), industry standards (Ref s. 9 through 14), TVA commitments (Refs.17 through 24), and design criteria (Refs. 121,122, and 123) to develop an understanding of the requirements of engineering organizational structure and operating procedures. I Reviewed available transcript of NRC investigative interview c. (Ref. 209) to gain additional information regarding concerns listed in Attachment A. d. Reviewed TVA documents such as Quality Assurance Programs (Refs. 25 through 40), Nuclear Performance Plans (NPPs) (Refs 41 through 46), Project Manuals (Refs. 47 through 57 and 120), Verification Programs (Refs. 58 through 62), Reports and Standard Practices (Refs. 69 through 105), and TVA Corpo' ate Commitment Tracking System (CCTS) r (Ref.106) to establish the responsibilities and practices related to the issues. Reviewed engineering department procedures (Refs.107 through 118) e. that establish organizational structure, design process, design change interf ace and communication between the design office and the j field, system design responsibilities, TVA practices for compliance I to procedures, vendor design document control, and design review and l verification practices. f. Reviewed results of the program audits (Refsi 135 through 151) to determine practices followed by TVA to comply with procedures. G e 2811D-R26 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 8 of 51 l 1 -l Additiona'l steps listed below were followed to evaluate the specific l element _noted. J l g. For element 204.3, reviewed applicable Conditions Adverse to Quality. (CAQ). documents (Refs. 132,133, and 134) in regards to indication i of equipment supports design input by craft personnel. j h. For element 204.4, reviewed Gene ~ral Construction Specifications (Refs.126 through 129) to assess the completeness-of specifications. j i -1. For. element 204.4, reviewed appropriate number of design drawings.- i related to CAQ reports in the EN DES Data Base (Refs.131), to .i establish the severity of the problems prompting the re-evaluat 4 n of existing procedures in completing the design output documen:s. j. For element 204.4, reviewed an appropriate number of drawings for l completeness of specific technical design details. k. For element 204.5, reviewed equipment procurement packages (Refs.152 through 196) in regards to documentation of-specifications in the procurement packages.' 1. For element 204.6, reviewed Division of Nuclear Engineering Design I Change Control Procedure NEP 6.1 and subsequent clarifications 1 (Refs. 53, 57, and 109), to establish the practices followed in the j control of design change documents (ECN etc.). m. For element 204.6, reviewed NRC staff evaluation of the Design Baseline and Verification Programs (DBVP)'(Refs. 215 and 216) to 1 determine NRC's acceptance requirements for plant modifications and l change control long term program. 1 n. . For element 204.6, reviewed memorandum (Ref. 220) regarding TVA's coninitment of the design change process improvement program. o. For element 204.7, reviewed Engineering Department Procedures (Refs, 88,107,108,109,112, and 116) regarding the review and control of vendor documents, p. For element 204.9, conducted interviews (Refs. 237, 238, and 239) with Engineering, Construction, Craft, and Quality Assurance personnel in regards to the issues. ] l Using the results of the element evaluation process, the issues were evaluated l for the element and the findings and corrective actions were documented. 1 28110-R26 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 9 of 51 3.2 Subcategory Evaluation Process Subsequent to the element evaluation process, the steps listed below were followei to prepare this subcategory report. a. Tabulated all the concerns addressed by this subcategory report in Attachment A. b. Tabulated issues, findings, and corrective actions from the element evaluations in a. plant-by-plant arrangement (see Attachment B). c. Prepared Tables 1, 2, and 3 in this subcategory report to permit comparison and identification of common and unique issues, findings, and corrective actions among the four plants. d. Classified the findings and corrective actions from the element evaluations using the ECSP definitions. e. On the basis of ECSP guidelines, analyzed the collective significance and causes of the findings from the element evaluations. f. Evaluated defined corrective actions to determine if additional actions are required as a result of causes found in step e. g. Provided additional judgment and/or information that may not have been apparent at the element level. 4. FINDINGS The full text of the findings from each of the 27 element evaluations is stated in Attachment B, listed by element number and plant. The findings (including validity of the issues) within each of the elements 'are summarized in the following paragraphs. Minimum discussion is devoted to those. findings for which no corrective action is required, such as cases where the allegations were not substantiated by the evaluation, or cases in which the allegations were found to be true but the consequences are acceptable. 4.1 Element 204.1, Organizational Structure

4.1.1 Issue

TVA's managerial structure is unwieldly and cumbersome, wnich sometimes leads to confusion in the design process. (Addressed as issue "a" for all plants, as s,hown in Attachment B) Findina. To further assess the review cycle for ECNs and DCRs, the evaluation team reviewed EP 4.02 and EP 4.18 (Ref.107), OEP-il (Ref.108), and NEP-6.1 (Ref. 109). A review of TVA audit reports and memoranda (Ref. 135, 216, and 217) discloses audit findings and recommendations which indicate that significant deficiencies existed in TVA's Division of Engineering Design (EN DES) managerial structure in 1984 and 1985. In late 1985, a corporate evaluation by INP0 reported the following finding which TVA accepted (Ref. 213) as valid: 2811D-R26 (10/15/87)

TVA EMPLOYEE CONCERNS . REPORT NUMBER': 20400 SPECIAL PROGRAM ' REVISION NUMBER: 2 'l Page 10 of 51 I . " Responsibility and authority for the various Office of Nuclear Power - I organizations have not been clearly defined or sufficiently 'l communicated. 'As a result, there is confusion in the organization." In the CNPP (Ref. 42) TVA stated that " responsibility ',~or various nuclear - functional areas [ including engineering] was divided among several groups." Investigations by TVA (Ref. 63)'and the Institute _of Nuclear Power Operations (INP0) (Ref. 213) confirm that until 1985 the responsibility for nuclear i i activities was divided among several departments, none of which reported to a single manager. This. issue was valid at the time the concern was raised.

4.1.2 Issue

Paperwork is excessive and passes through too many hands. too.many people are in the review cycle for engineering change notices (ECNs), design change requests (DCRs), and memoranda. j ~ ( Addressed as issue "b" for all plants, as shown in Attachment B) j Finding.- A review of TVA's engineering procedures (Refs. 107,108,' and 109) indicates review cycles for Engineering Change Notichs (ECNs) and. Design j Change Requests (DCRs) that are similar to those used by other engineering firms engaged in the design of nuclear power plants. To evaluate the validity j of the allegation that TVA required too much paperwork and that there were to i i many people in the design change review process, the evaluation team reviewed-investigativereportsissuedbysixgroups(Refs. 93, 75, 63c, 104, 204, 205, 206, 207, 69, 68, and 213). None of these investigations found a design control problem at the plants or at TVA headquarters similar to those alleged. 1 This issue is not valid. - I

4.1.3 Issue

-Too many engineering procedures exist, and they need to be streamlined. ( Addressed as issue "c" for all plants, as shown in Attachments) Finding. In 1981, TVA's NSRS reported (Ref. 63c) that "the f ailure to i consistently implement the EPs appeared to be due to a combination of factors l ... [ including] the large volume of procedures and inadequacies within the procedures." The NSRS recommended that EN DES policy, responsibilities, requirements, and guidance be systematically established in tiers of documents. i I 6. k l 28110-R26 (10/15/87) l i -_ i

TVA EMPLOYEE CONCERHS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 l Page 11 of 51 There were at least 18 volumes of EN DES discipline guides and standards, as well as four volumes of EN DES-EPs. The Engineering Procedures (EPs) were quite detailed and included many policy statements and QA requirements. However, in 06/85 the EPs were replaced by a single " streamlined" volume of OEPs. Most of the Office of Engineering Procedures (0EPs) were in turn replaced by a single volume of Nuclear Engineering Procedure (NEPs) in 07/86. i The OEPs and NEPs were supplemented by site engineering procedures. l This issue was valid at the time the concern was raised.

4.1.4 Issue

There is a lack of timely response to requests for ) engineering information for WBN. (Addressed as issue "h" for WBN l only, as shown in Attachment B. This issue was unique to WBN, and l was not evaluated for the other three plants.) i Finding. This concern is supported by a statement from an ECTG Management and Personnel report (Ref. 97) which states that there have been numerous examples of construct'en production delays resulting from constructibility problems with design drawings, compounded by a lack of adequate or timely response by design engineers. This issue was valid at the time the concern was raised. 4.2 Element 204.2, System Desian Responsibility

4.2.1 Issue

Responsibility and monitoring for overall system design is not assigned to a specific individual who is knowledgeable of all aspects of the system, including interf acing support systems. (Addressed as issue "a" in element evaluation 204.2 for SQN and as I issue "d" in element evaluation 204.1 for WBN, BFN, and BLN, as shown in Attachment B) j Finding. In 1973, EN DES was established and " system design engineers" who j were knowledgeable about the basic elements of the systems were assigned to the pr.ojects. Within EN DES, the assignment of individual responsibility for system design and documentation was defined in the EN DES-EP manual (Ref.107), and very similar position descriptions appear in the Office of Engineering (OE) Organization Manual (Ref.120). These position descriptions indicate that more than one engineer was responsible for the design and documentation of each system. The current NEPs (Ref. 109), which superseded the corresponding OEPs, eliminated the title " system design engineer." However, the function of designing each system by one or several engineers assited by associate s engineers was continued. In 1984, INPO recommended (Ref. 68) assigning the responsibility for specific operatina systems to individual engineers. This recommendation was accepted by lVA, and systems engineering sections have been established at the 28110-R26 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 12 of 51 l constructed plants. The engineers in these sections provide a single contact l point for system history, status, testing, and troubleshooting. l At SQN and BFN when the systems became operational, TVA located a systems engineering section, with individual system engineers, at the site to address l and resolve system problems. i At WBN and BLN, the responsibility for monitoring the complete system design, including interfaces with supporting systems, is assigned to the ONE project engineer and assistant project engineers on the design project. Discipline teams are necessary to design the large, complex systems found in nuclear power plants. DNE staffs each nuclear power. plant design project with a project engineer, assistant project engineer (s), and discipline teams each having a lead discipline engineer, engineers, and associate engineers. This issue is valid in that it is a true statement but it is not a problem.

4.2.2 Issues

With one person handling contract support, another mechanical, another controls, another electrical,etc., i responsibility is fragmented and quality has been affected. (Addressed as issue "b" in element evaluation 204.2 for SQN and as issue "e" in element evaluation 204.1 for WBN, BFN, and BLN, as shown in Attachment B) Findina. In 1981 and 1982, TVA internal memoranda (Refs. 222, 224, and 226) ' documented deficiencies in system design responsibility. However, the authors of the memoranda advocated assigning a scope of responsibility to various individuals working on a system, rather than total system responsibility for { one person. The current NEPs (Ref. 109), which supersede the corresponding 0EPs, govern I ? design control and provide for satisf actory coinpliance with regulatory design' control requirements. They do not require that overall system design control be assigned to one individual. While the actual design details of interfacing j systems is divided among the disciplines, the project engineer and assistant project engineers are responsible for the overall quality and adequacy of i system engineering efforts. There is no evidence that the team design approach used by TVA detrimentally affected the quality of any TVA plant. l l The issue is valid in that it is a true statement. However, after reviewing the concern and considering the systems involved, the evaluation team concluded that it was not possible in the design stage,for individual engineers to be informed about all aspects of their sys' tem (s), and the interfacing support systems. l 4 2811D-R26 (10/15/87) l I ______-____a

L .j . TVA EMPLOVEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 I Page 13 of 51 4.3 Element 204.3,. Field versus Desian Office Responsibility

4. 3.1 -

Issue: TVA leaves too many technical decisions to the discretion of the craf t personnel (e.g., hanger design).. (Addressed as issue "a" 3 in element evaluation 204.3 for SQN, BFN, and-BLN and as issue'"f" ) in element evaluation.204.1 for WBN, as shown in Attachment B). Finding. The evaluation team found that SQN, BFN, BLN and other TVA engineeringprocedures(Refs. 107,108, and 109) are adequate and a circumvented approval process, as described in the issue, should not occur. A review of TVA audit reports (Refs.136 through 139), and discussions with cognizant personnel (Refs. 240 through 243) indicate a problem existed at WBN where procedures (Ref. 107,108,109 and 49) did allow the craf t to make limited adjustments during hanger installation. In 01/85, a WBN (unit 2) field change request study by TVA (Ref. 233) found that about 51 percent of system 62 and system 63 hangers required FCRs. Of these FCRs, almost half were necessary because of drawing problems such as incorrect dimensions. In 05/85, INPO found (Ref. 69) the following deficiericies in field programs - necessary to supply technical guidance to the pipe hanger craftsmen:

1) Work packages were incomplete.

2) Constructibility reviews were not identifying many interferences and design errors, and 3) Field engineers were unavailable to resolve problems.

In 07/85, a Nuclear Safety Review Staff (NSRS) report (Ref. 63e) found that '3 "the 47A050 notes [ associated with the pipe support detail drawings] require frequent changes." Finally, an Employee Concern Task Group (ECTG) report (Ref. 97) found that in an attempt to meet construction production schedules, the FCR process has. occasionally been misapplied. At BLN.the INP0 report (1984) states that'the pipe support installation program in the field is effective in producing pipe supports that meet design requirements with' low rejections at inspection. The issue is valid for WBN, SQN and BFN although TVA procedures do not authorize craft personnel to make design decisions and, engineering approval of field changes has been, and is, required at all TVA nuclear plants. However, the evaluation team found no evidence to support the implication that decisionsbythecraftswereresponsibleforanyprobigms. f l i .. ~ ) 28110-R26 (10/15/87) 4 1

TVA EMPLOVEE CONCERNS REPORT NUMBER: 20400 l 2 6 SPECIAL PROGRAM REVISION-NUMBER: 2-l Page.14 of 51 jl j i 4.4 ~ Element 204.4, Desian Document Completeness - Adeauacy j i

4.4.1 Issue

Engineering (EN DES) inadequately addresses and considers-construction, testing, operation, maintenance, and general industry practices in the design process. -( Addressed 'as-issue 'f a" for all plants, as shown in Attachment B) Finding. TVA engineering procedures that have been in effect since 09/73 (EN DES-EP 4.25, OEP-06, and NEP-3.2) all state that construction, testing, operations, and' maintenance requirements, as well as codes and standards must be considered during the design' process. The evaluation team found that these procedures are adequate for addressing these requirements. If the above listed design considerations were not a'ddressed because of lack of knowledge on the part of_the designers and their supervisors, ro programmatic correction, except perhaps additional training, would have solved the problem.- l t Constructibility problems could have caused adverse economic effects and schedule delays, but they should not have been allowed to compromise the integrity of the safety systems. Prudent-engineering practice would address testing requirements in the design. As a minimum, the design provided should not preclude the addition or J installation of the required testing equipment when needed or during the latter phases of construction when the actual plant configuration becomes l l better known. 1 Prudent engineering practice would also address operations and maintenance There is a tradeoff between the requirements in the design process. preferences of the operations and maintenance personnel, the realities of The plant design design requirements, and consideration of plant' economics. can f avor any of these elements, but usually at the expense of the others. The ' Ideally, the design of the plant properly balances all considerations. design provided should not preclude the addition of any required items when needed, and should allow accessibility to all plant features for maintenance. Utility personnel attend industry meetings and seminars where industry methods are discussed. Methods that work well and have general application eventually become accepted and in time become recognized as a general practice.

However, the situation is always subject to change.

} Practices that approach standardization throughout the industry are usually those that meet applicable codes and standards, and ar'e economically TVA must meet the requirements of industry codes and standards, advantageous. I but is not under a mandatory comitment to follow any other " general practices." For example, INP0-suggested good practices are not mandatory. I i i 28110-R26 (10/15/87)

c TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 ~ ) SPECIAL PROGRAM REVISION NUMBER: 2 .Page 15 of 51 Although specific instances have-been identified at.all nuclear plants where certain aspects of the design process were in error, the evaluation team did-not find pervasive evidence to indicate that the design considerations stated j above had been ignored or neglected. The issue is not valid.

4.4.2 Issue

The TVA General Construction Specifications (G-specs) are often inadequate and incomplete. (Addressed as issue "b" for all j plants, as shown in. Attachment B) Finding. TVA G-Specs have existed since 1939 when they applied to construction of dams and reservoirs. They have since been updated and expanded to be applicable to power plants. Project Construction Specifications are used to augment or modify G-Specs for a specific project or f site application. In 1974, EN DES Procedure 3.04 (Ref.107) was -issued to l govern the preparation and approval of G-Specs for the nuclear' plants. At I that time, the specs were also indexed and formal control was initiated. The G-spec role is to provide the general guidelines for the implementation of the' physical work. The detailed "how to" information'is supplemented in the engineering documents. l The recent Specification Improvement Plan Program [B05 860808 001] is in the. process of generating more complete Engineering Requirements (ER). These ER Specifications with a controlling feature over engineering drawings. specifications will replace the G-Specs on a transitional basis. The evaluation team rev.ewed the 27 G-Specs (Ref. 126) that are applicable to i TVA nuclear power plants for adequacy and completeness. There are several instances of outdated references and in one instance, a minor conflict with another construction document was found; G-Srec 43 contains information on . pipe supports that conflicts with the SQN Construction-issued Modifications and Additions Instruction 11 (M&AI-11). G-Specs are not stand-alone documents. They are general specifications that are intended to be utilized alone with appropriate site-specific i specifications and documents. The evaluation team's review of an appropriate number of G-specs showed that, as general specifications, they are adequate and consister.t with industry practices, f i The issue is not valid.

4.4.3 Issue

Engineering drawings often are inadequate in that they lack ) some technical detail (i.e., weld detail), do not always include or } represent design requirements, or create interferences and cause ) other constructibility problems during installation. (Addressed as issue "c" for all plants, as shown in Attachment B) 1 i 28110-R26 (10/15/87) l lL

I TVA EMPLOVEE CONCERNS REPORT NUMBER: 20400 l SPECI AL PROGRAM REVISION NUMBER: 2 j Page 16 of 51 l 1 Finding. For WBN, the evaluation team reviewed approximately 600 l drawing-related CAQ reports 7 the EN DES CAQ Data Base (Ref.131). Seventy-one CAQ reports (mostly NCRs) were related to the issue that documents do not always include or represent design requirements. INP0 Finding DC.5-1 (Ref. 69) noted that inconsistencies exist between the FSAR and other design documents. Ninety-two CAQ reports, mostly construction NCRs issued after l 1981, were due to engineering drawing deficiencies. j Four deficiencies were also cited in INP0 Watts Bar Evaluation Report (6/85), Finding CC.4-5 (Ref. 69) regarding pipe hanger constructibility. For SQN the evaluation team found instances where design drawings omitted several pipe hanger welds. Another instance involved the use of mixed bolted and welded beam connections. Still another instance involved the investigation of employee concern IN-85-886-N04 (Subcategory Report 22300) that no seismic analysis was performed for local instruments. These and others instances are cited in other SQN element evaluations. Also, Gilbert / Commonwealth Report 2614 (Ref. 91) found that mounting details for instrumentation were inadequate. A review of the 12/01/86 CAQ Data Base Frequency Rep'6rt for SQN revealed that 57 out of the 3,750 CAQ documents listed (1.5 percent) indicated that drawings l were the source of the problem or the at-f ault item. For BFN the evaluation team sampled drawings from various disciplines and the issue that some drawings are incomplete is valid. Out of 55 mechanical i drawings sampled, 5 were found to be incomplete. Out of 35 pipe support drawings, 4 were either incomplete or had minor errors. All 9 of the electrical schematics reviewed were found to be complete. However, it should I be noted that the level of detail or completeness is relative, depending on the reviewer and the time period during which such drawings were generated. For BLN the evaluation team reviewed approximately 400 drawing-related CAQ reports in the EN DES CAQ Data Base (Ref.131). x Fifteen CAQs, mostly construction NCRS, relate to inadequate drawings. i Nineteen CAQ reports were related to the issue that drawings do not always include or represent design requirements. Before 1982, only three NCRs were l written. Twenty-five CAQ reports were identified as constructibility related due to engineering drawing deficiencies. j s The issue that engineering drawings do not always include or represent design requirements is valid, but Jnly to a limited extent. 'In general, the TVA 5 drawings reviewed are adeqiate. In addressing engineering concerns and in instances where technical details became identified as missing or in error, the evaluation team either acknowledged in its element evaluations and subcategory report that corrective 2811D-R26 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUM'ER: 20400 B SPECIAL PROGRAM REVISION NUMBER: 2: Page 17 of 51 processes were in place, or CATDs were. issued to start the corrective action

process.. Specific Engineering inadequacies in this area are addressed in the-other Engineering Subcategory Reports.

4.4.4' Issue: There are conflicts between' TVA drawings and vendor j drawings. ( Addressed as issue "d" f or all' plants, as shown in Attachment.B). . Finding. At WBN, the evaluation. team reviewed the EN DES CAQ Data Base

(Ref.131) and the NPPs (Refs. 42 and 45); 16 CAQ reports have -identified conflicts between TVA and vendor drawings.

l At:SQN, the issue of conflicts between TVA drawings and vendor drawings was. substantiated by TVA-corrective Action report (Ref. 96), and Nuclear Safety. l Review Staff report (Ref. 63). At BFN, the BFNPP (Ref. 46) and the NSRS investigative report (Ref. 63b) did indicate that there were conflicts between TVA drawings.and vendor drawings. At BLN, the evaluation team reviewed the EN DES CAQ Data Base (Ref.131); 14 i CAQ reports.have identified conflicts between TVA and vendor drawings. The issued is valid.

4.4.5 Issue

TVA design not developed well enough to be constructible; { therefore, drawings and acceptance criteria were frequently revised f . late in the project. (Addressed as issue "e" for all plants, as "1 shown in Attachment B) Findina: For WBN, SQN and BFN there are TVA NPPs (Refs. 43,44,45,and46), lNPO reports, and 'NSRS ' investigative reports (Ref. 63), all attesting to _the large number (auantity) and misuse of ECNs and FCRs. It must be recognized that for these three plants the concern pertains to an after-the-f act issue. At BFN audit reports (Refs.143 and 265) and NSRS finding (Ref. 63c) cite ' instances of calculations made after drawing issue, improper documentation of design, insufficient evaluation of design criteria changes and criteria not being reviewed by the NSSS vendor. Revisions to drawing and acceptance criteria, when properly justified, are considered to be an acceptable industry-wide practice regardless of the state of the project at the time. l' The issue is valid for all plants; however, it is not'a problem. I 4 2811D-R26 (10/15/87)

x - I TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page'18 of 51 I

4.4.6 Issue

Locally mounted instruments, ITC 307 and ITC 328, were installed but not specified on the design drawings. (Addressed as . issue "f" for WBN Only, as shown in Attachment B. This issue is unique to WBN, and was not addressed for the other three plants. Finding. TIC-31-307 and TIC-31-328 are air conditioning temperature indicating controllers (TICS) for the personnel access hatch located at elevation 713 feet. The TICS sense the ambient temperature and, using control air, modulate their respective temperature control valves (TCVs) according to 4 a predetermined setpoint. At WBN, most TICS are mounted directly on the -TCVs. However, the above TICS, as well as a few others, were wall-mounted in the vicinity of their respective TCVs. The evaluation team has reviewed WBN drawing 47W915-10, which shows the TCVs but not their respective TICS. The only engineering document that referred to i these TICS is Instrument Index 47B601-31. These TICS were installed according to WBN Engineering Requirement Specification ER-WBN-EEB-001 (Ref. 99). This specification allows Construction to determine the optimum location of the TIC according to certain guidelines and requirements. i The evaluation team found per ER spec ER-WBN-EEB-001', that locally mounted The instruments do not have their exact location specified by DNE. specification allows the installing organization to determine exact location based on certain requirements. The specific TICS addressed in this issue are shown on 47W610-series TVA drawings, along with other locally mounted instruments. The issue is not valid. 4.5 Element 204.5, Desion Review / Verification

4.5.1 Issue

Design drawings, technical specifications, design criteria documents, and pre-op test packages do not receive a second independent technical review as required, but are reviewed primarily for non-technical, editorial details (English, spelling, etc.). ( Addressed as issue "a" for all plants, as shown in Attachment B) Finding. The evaluation team could find no regulatory requirement or TVA commitment for Technical Review (or "second independent review") per se of design drawings, technical specifications, design criteria documents, and preoperational test packages. Technical Reviews, defined by TVA in NEP as " design reviews," are scheduled by the branch chief / lead engineer according to the area selected for review, its nearness to completion, its influence on later designs and whether or not the area is suitable for phased review. Once a technical review is performed it need not be performed for each revision of a document. 2811D-R26 (10/15/87)

p 1 TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 i Page 19 of 51 The " Technical Review" (second independent technical review - called design . review in NEP-5.2) is an evaluation of selected areas, not specific design drawings, technical specifications, design criteria, or pre-op test packages. However, these documents may be involved in such a review. Examples of three Technical Reviews done at WBN and BLN (Ref. 228, 229, and 230) provide evidence that such reviews, when undertaken, check more than just the non-technical editorial aspects. The reviews delve in depth into the technical content of the subject matter. From the items cited by a concerned individual (CI) as not having been submitted for technical review, it appears that the CI is not making reference to Technical Reviews as defined by TVA procedures (e.g., NEP-5.2). It is possible that when the CI referred to " technical review," it could have l meant either: A review of an engineering document by an engineer for o appropriateness of technical content, or A review by various design organizations of design input, design o output', or other engineering documents for technical adequacy With regard to the first category, the evaluation team reviewed sample document packages and found them to have been, by the nature of comments written, reviewed primarily for technical content and secondarily for non-technical editorial details. With regard to the second category, it was observed from a review of documents i that the internal TVA interf ace review system called "squadcheck" bore more technical evaluation comments than non-technical editorial comments. The Technical Reviews observed by the evaluation team revealed in-depth ~ technical evaluations, and not mere non-technical editorial detail reviews as alleged by the CI. The issue is not valid.

4.5.2 Issue

Technical reviews (second independent technical reviews) performed at Knoxville are inadequate. ( Addressed at issue "b" for all plants, as shown in Attachment B) 4 Finding. Design control measures for verification of technical adequacy employed by TVA appear in general to be adequate, based on the evaluation team's review of procedures and documented Technical Reviews noted above. However, some specific shortcomings were noted in the area of calculation i l procedures as discussed in Subcategory Report 24600. I 1 2811D-R26 (10/15/87)

4 '): TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400' SPECIAL PROGRAM REVISION NUMBER: 2 ,i Page 20 of 51 " Technical Reviews" (second independent technical reviews) are'not required' by regulation, TVA procedures, or TVA commitment. It was found that a few such reviews have been performed for TVA plants. The issue is not valid, i

4.5.3 Issue

Technical review-is not performed after the checkers have reviewed pipe support calculations. (Additional information i relative to this issue is addressed in Element Evaluation 220.12. ( Addressed ;as issue "c" for all ~ plants, as shown in Attachment B) Findina. -The Technical Review issue was previously evaluated for Watts Bar (WBN) in element evaluation 220.12, which stated, "The applicable requirements do not mandate any additional check or review to be made after the checker's review. Therefore, the concern is not valid." l i Element evaluation 220.12 stated, "The applicable requirements do not mandate any additional check or review following a review by a checker." q Therefore, the concern is not valid. Peripheral Finding. As a peripheral finding, in reviewing piping bill of material drawings for BFN element evaluation 232.8, 'the evaluation team noted that the same individual' initialed both the "Made" and " Checked" boxes of some of the drawings. This was noted on 11 different bill of material drawings. These drawings include over 40 different sheets (Ref. 203), issued between j 05/68 and 02/73. In some cases, this also occurred on subsequent revisions of some drawing sheets. Allowing the individual who originated the work to check the work is contrary to accepted industry practice and to current TVA practice i and procedures. This lack of independent review increases the possibilities of error. Therefore, the issue is not valid. i

4.5.4 Issue

Calculations are not generally reviewed by technical supervision. (Addressed as issue "d" for all plants, as shown in Attachment B) ' Finding. 10 CFR 50, Appendix B states that the verifying or checking process shall be performed by individuals or groups other than those who performed the original design, but who may be from the same organization. ANSI N45.2.11 requires that calculations shall be identifiable by subject, originator, reviewer, and date. It also states that procedures shall include requirements for review and approval. The ANSI requirements do not stipulate the need for calculations to be reviewed by technical supervision, t. e 2811D-R26 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 21 of 51 Engineering Department procedures were reviewed f or establishment of calculation review and checking practices and responsibilities. TVA calculation procedures incorporate the pertinent requirements of 10 CFR 50, Appendix B and ANSI N45.2.11. The design calculation procedure EN DES-EP 3.03 states that the section supervisor, by signing at the " submitted" block of the calculation cover sheet, attests that the calculations were performed and checked by technically qualified persons. Also the same procedure assures independence of the checker f or the work being reviewed. OEP-10 on " Review" and NFp-3.1 on " Calculations" also identify similar requirements. Review of calculations by technical supervision is neither a regulatory requirement nor a TVA commitment. The issue is not valid.

4.5.5 Issue

TVA independent verification of vendor calculations and designs are either not adequate or not done at all, and design reviews of vendor deigns are not done. (Addressed as issue "e" for all plants, as shown in Attachment B) Finding. When TVA does checking and approving of vendor calculations, the responsible EN DES design group processed them in accordance with EN DES-EP 3.03, OEP-7, NEP-3.1, and NEP-5.2 depending on the time frame in which the work was done. Independent review / design verification is accomplished according to the procedure that initiated it, such as NEP-3.1. DNE procedures require design verifications, as defined in ANSI N45.2.11, on calculations when TVA is respons.ible for doing so, as stipulated in procurement contracts. Design reviews are one method of accomplishing this verifictti on. Design verification is not required on other vendor-supplied inf ormati on. Only interf ace reviews and review for approval are required on the o'ther vendor-supplied inf ormation. In the transcript of NRC investigative interview (Ref. 209), the CI alleges that TVA does not adequately or independently verify vendor calculations or designs. In discussions with Mechanical Engineering Branch (MEB) personnel it was found that when submitted to TVA, vendor calculations do receive an independent review. Additionally these calculations are subjected to a squadcheck review. Evidence of these reviews was observed in calculations identified in Refs. 124, 125, 168, 153, and 225. Per EN DES-EP 4.04 (Ref.107), the Squadcheck Process within EN DES is a systematic interorganizational and/or interorganizational routing process f or the purpose of reviewing a drawing or other design document where a response 28110-R26 (10/15/87)

l TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 22 of 51 is required. The squadcheck process is also used to transmit drawings or other documents from one EN.0ES organization to another to provide inf ormation, in which case a response is not required. OEP-10 and NEP-5.2 address the squadcheck process as interf ace reviews. The TVA QA audits of f our contract packages (Ref s.145 through 148) were examined and they indicated some deficiencies in the vendor design control area. Tne deficiencies were resolved by corrective action taken subsequent to the audits. TVA QA audits are an essential part of ensuring vendor design c ontrol. Review of vendor calculations by TVA is performeo only when reauired by procurement contract. A review of examples of vendor calculations determine that procedure were f ollowed. The issue is not valid.

4.5.6 Issue

TVA does not conduct independent design reviews of its work. (Addressed as issue "f" for all plants, as shown in Attachments) 4 Finding. The definition by TVA in its Topical Report (Ref. 25) of design verification includes design review as an acceptable verification method, as well as alternate calculations and qualification testing. It is mandatory that design verification be accomplished. Design verification is done by the responsible TVA design organization as a normal part of the design process, and to the extent identified by the procedures. The procedures allow design reviews to be employed as a design verification 1 process. l Regarding discussion on the matter of independent design reviews in the transcript of the NRC investigative interview (Ref. 209), internal TVA interface reviews would seem to satisfy the requirements of a design review, except that instead of conducting design review meetings, a review and signoff form is routed with the document under review. When initialed by review participants, the f orm accompanies the document and is retained in the Records Inf ormation Management System (RIMS). The evaluation team observed the interf ace review system at MEB in Knoxville. A TVA policy memorandum (Ref. 235) dated 03/03/87 states that TVA is requiring independent verification for all new or revised calculations. The memorandum i indicates that this require. ment will be incorporated into the NEPs. This verification would be a secoad independent design verification. I A procedural requirement for independent design reviews (checkers) does exist and there is ample evidence than such reviews have been performed. The CI may be alluding to a second indepenoint design verification, discussed in Section 4.5.2 of this report. When TVA tiects to review vendor calculations, that would be a second independent design verification. The ' issue is not valid. 28110-R26 (10/15/87)

TVA EMPLOVEE CONCERNS REPORT: NUMBER: 20400 SPECIAL4 PROGRAM REVISION NUMBER: .2-Page 23 of-51 l

4.5.7 Issue

Design checks and reviews are being performed by technicians ] ("SE". level personnel) in lieu of graduate engineers at i TVA/ Knoxville pipe support group. ( Addressed as issue "g" f or all plants, as shown'in Attachment B) Finding. -10 CFR 50, Appendix B (Ref.1), in conjunction with ANSI N45.2.ll (Ref. 10), requires design checks be carr.ied out by competent individuals or groups who are experienced in the subject activity and who did not perf orm the original design. Hence, whether the checkers are technicians or graduate engineers is not the' controlling f actor. The TVA SQN Generic Concern Task Force conducted two separate investigations relative to concern IN-85-148-001. The results of,the investigations were issued as report GPH-03-37. The conclusion of the first investigation was: "A graduate engineer would not be qualified to check design drawings without piping design experience and training, whether formal or on the j ob. Since only actual experience and knowledge significantly contributes to design quality, the concern to.have checkers be graduate engineers is not valid." 1 The conclusim of the second investigation was: "The concern is substantiated. However, competence in design is achieved j through educati n, training, and experience in various amounts depending 'l upon the.cmplexity of that design. While it is important to safety, pipe support design in general is neither complex nor does it involve a l rapidly changing state-of-the-art. It is, to a laroe extent, standardized at TVA. Much, if not all.of this work can be perf ormed by technical ) personnel without the benefit of an engineering degree. In addition, there is no 'TVA requirement f or design to be checked by a i , degreed engineer. In this respect TVA practice does not conflict with ) industry standard practice." l Even though the issue may accurately identify a f actual situation, it is competency and experience, not the level of f ormal educational training, that qualifies or disqualifies personnel to do design checks or reviews. ._j The issue is not valid.

4.5.8 Issue

Design analysis and verification drocesses are not adequately controlled. ( Addressed as issue "h" f or all plants, as shown in Attachment B i i i l l-2811D-R26 (10/15/87) = _ _ _ _ -

l I TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 j Page 24 of 51 j Finding. Control of design analysis and verification analysis processes to comply with regulatory requirements is described in 10CFR50, Appendix B,

Criterion III, " Design Control." ANSI N45.2 and ANSI N45.2.ll amplify these l

requirements and they are committed to by TVA. These controlling requirements are reiterated in TVA-specific documents such as the Preliminary Safety Analysis Report (PSAR), the Final Safety Analysis Report (FSAR), the TVA Topical Report TVA-TR75-1A, the Sequoyah Quality Assurance Manual, the Office of Engineering Design and Construction Procedures Manual, Interdivisional Quality Assurance Procedures, and the TVA Nuclear Quality Assurance Manual. Procedures addressing the requirements contain the details for accomplishing the necessary controls (as described in the documents referenced). These procedures are found in such documents as the EN DES Procedures Manual (the Red Book EPs), the OE Procedures Manual, and the NEP Procedures Manual). These processes address the letter of the requirements, however, some individual procedures lack sufficient detail. Some examples of this are addressed in subcategory report 24600 on calculations. There was also some evidence to indicate that not all engineering procedures were strictly f oll owed. Therefore, the issue is valid in the area of calculation procedures. Corrective action is addressed in subcategory report 24600. 4,5.9 Issue: Lack of engineering personnel could cause insufficient review of engineering documentation. ( Addressed as issue "1" f or BFN Only, as shown in Attachment B) i Finding. TVA is aware that lack of engineering personnel could cause insufficient review of engineering documentation and is implementing actions to remedy the situation as noted in the BFNPP. They are also aware of the need to provide adequate resources for technical review as a result of an INPO audit finding as reflected in a TVA memo (Ref. 214) of 08/14/86 on responses to the audit. In essence, the audit finding says that the Division of Nuclear Engineering budget does not ensure adequate resources for technical review and l engineer training. j Section II of the Browns Ferry Nuclear Performance Plan (BFNPP) (Ref. 46) l addresses site engineering and acknowledges problems with the Engineering l Organizati on. l There is an implied lack of engineering personnel for, review of engineering d ocumentati on. The BFNPP recognizes this deficiency 'and indicates actions to alleviate this situation. The situation is to be alleviated by reorganizing engineering resources to perf orm the work where it'can be managed and I accomplished more effectively. f The issue is valid. 4.5.10 Issue: TVA changes vendor drawings without vendor approval. l ( Addressed as issue "i" f or BLN Only, as shown in Attachment B) 2811D-R26 (10/15/87) u__-___-

1 i TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 I Page 25 of 51 Finding. At BLN EN DES EP 4.35 (Ref.107) requires that the Contract Engineer determine in consultatic9 with the design engineer and-the Division of 1 Purchasing if vendor approval is required. ] For vendor drawing revisions 06/28/85 and subsequent, procedures OEP-09 and l NEP-4.1, although not as comprehensive as EP-4.35, also allude to coordinating j with the contractor / vendor as required. j l A vendor drawing was " turned over" to TVA when TVA took over control of the pipe support and calculations and assumed engineering responsibility. The " turn over" point was when ITT Grinnell had completed the final design. The contract with ITT is not closed at this point. The drawings even bef ore " turn over" are coordinated for review and squadcheck at.TVA during the design cycle ] and bef ore final design. ) 1 TVA does not change ITT Grinnell pipe support drawings while they are under l Grinnell control without Grinnell's approval. After turnover (final design i approved by TVA and issued by Grinnell) to TVA, they are considered TVA drawings. As TVA drawings, any needed changes are made by TVA as procedures allow. l The issue is not valid. 4.5.11 Issue: Personnel performing documentation review lack adequate training. ( Addressed as issue "j" f or BFN Only, as shown in Attachment B. This issue was unique to BFN, and was not evaluated l f or the other three plants.) Finding. In accordance with the BFNPP, personnel involved in the use of quality-related Nuclear Engineering procedures will be trained by Engineering Assurance (EA) as indicated by the above noted functions. The implication of the BFNPP is that they have not been trained heretofore. The TVA Topical Report (Ref. 25) addresses the requirement for an indoctrination and training program for personnel performing quality related activities and sets forth specific program parameters. " Indoctrination and training practices of Offices of Engineering and Construction are as f ollows: '" Office of Engineering " Office of Engineering personnel performing quality assurance /auality control activities are qualified through indoctrination and/or training. The responsibility for performing quality related activities is assigned only to qualified personnel. "The need for special indoctrination and/or cross training required to l improve or maintain proficiency may be identified by any Office of Engineering division, branch, project, or staff organization. 2811D-R26 (10/15/87) L- -_ ---

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 26 of 51 "The Office of Engineering Personnel Staff develops the training requirements matrix which relates individual cuality assurance training requirements to specific job functions important to safety and develops proposed training program schedules, evaluation techniques, and identification of trainers and course content." The Topical Report f or TVA Quality Assurance Program apolicable to station operations, subsection 17.2.2.3, states that the same thing as applicable during plant operations. Engineering procedures which address training are EN DES-EP 1.16, which is superseded by MSB-EP 63.02, OEP-18, and NEP-1.2. These procedures require training of personnel in engineering procedures appropriate to the individuals area of responsibility. The procedures also require documentation of the training. A QMS audit status log (Ref.144) dated 08/22/86 implies that BFEP training has been conducted; however, it also indicates there is a failure to document some training on Individual Training Records (ITRs). In addition, the log indicates lack of training relative to various engineering branch procedures. As this is a corrective action tracking document, the indication.is that corrective actions have been initiated. Training rosters for 1986 and 1987 were obtained through the BFN jobsite which show training relative to NEPs, including NEP-1.2, NEP-1.6, NEP-4.1, and NEP-5.5. Additional training records were received from TVA Knoxville which indicates engineering procedure training dating to early 1984. Prior to 1984, lack of training records indicates a lack of training relative to engineering procedures. From 1984 to the present, there is ample evidence that training in engineering procedures is taking place. This issue may have been valid at an earlier point in time. 4.5.12 Issue: Design engineers did not document their original procurement specificati ons. ( Addressed as issue "k" f or BFN only, as shown in Attachment B. This issue was unique to BFN, and was not evaluated f or the other three plants.) Findino. As indicated in the BFN FSAR (Ref. 18), General Electric Company (GE) ' procured a great deal of material f or TVA in its contract with TVA f or BFN units 1, 2, and 3. In TVA's BFN 66C31-90744 procurement package (Ref.163) dated 06/17/66, f or equipment, GE procured many items using a TVA procurement specification 9065. 6-A civil procurement specification obtained f or a BFN procurement package (Ref.160) is dated 06/19/67. Electrical specifications referred to in BFN procurement packages (Ref.161) are dated as early as 10/25/65. Mechanical procurement specifications were included in procurement packages (Ref.169) dated as early as 06/14/68. 28110-R26 (10/15/87)

.g---------- 12 + ; + TVA' EMPLOYEE CONCERNS- . REPORT. NUMBER: _.. ;20400- + SPECIAL PROGRAM ~ REVISION-NUMBER: 2. Page 27 of 51 x l g I { 0-b Some mechanical ~ procurement.packagesL(Ref.162). identified specifics in the

form of

attachments, not in procurement specification documents.-

~l i A~ nuclear procurement" package (Ref. :163) dated 06/17/66 includes 'a TVA procurement (specification. Evidence exists that~ some original procurement specifications were documented. 1 I .The issue is not v'al'id. j - 4 4.6 Element ' 204.6, ECN Process J 4'. 6.1 Issue: Engineering Change Notices (ECNs) are closed out.in an 1 untimely manner, without proper status of ECN and affected design - f l . being known.; There is'a lack of adeauate tracking'of EN DES (TVA)' design changes (e.g., ECNs) '( Addressed as issue "a" f or all plants, as shown in Attachment B) ' - 1 } Finding. A ' review of the past and present division-wide engineering i procedures (EN DES-EPs, OEPs,-and NEPs) and site-specific procedures (Refs.. 50,'53, and 57) revealed problems in tracking and closeout of ECNs. L Requirements for. closing ECNs changed from the EN DES-EPs to the'.0EPs to the' . I NEPs. Thus, ECNs were. closed at different stages of the field. implementation: of' the changes.._ TheLNPPs (Refs. 41-46). have acknowledged problems in the past =. l L. m-9 ' with the. design change process and design change control. l3 ln j; ' The evaluation team'had found that the ECN procedures used at all of the four-O TVA nuclear plants have been inadeauate in controlling design changes'in the 1

past., Problems-have been attributed to the lack of coordination between disciplines within the engineering division and'with the site construction

{ organization. Problems have also been attributed 'to the lack.of an adequate-I -tracking and closure procedure which has resulted in the untimely closure of. ECNs. Some ECNs have been closed prematurely 'and others have remained open j for11ong periods of time. i L.L L The issue is valid. J 14.6.2' ~ Issue: Procedure OEP-ll revision eliminated space on the front cover page for identification of other documents and plant areas affected by ECNs. Elimination of this " checklist," which required e consideration and positive action by the ECN preparer and reviewer, 1 i may result in an.affected document or plant area being overlooked. .j (Addressed as issue "b" for all plants, 'as'shown in Attachment B) Finding. The ECN cover sheets in EN DES-EPs 4.02 and 4.52 had nine questions wnich required a positive response of "yes" or "no" (Example: FSAR Drawing Modified? FSAR Test Modified?). These auestions were removed from the cover -r sheet in OEP-ll and expanded into a 28-point' list of considerations in , M* J.M 4. ame---+e4%smae,.-+.www. 2811D-R26 (10/15/87) k'

c TVA EMPLOYEE CONCERNS SPECIAL PROGRAM REPORT NUMBER: 20400 REVISION NUMBER: 2 y o __f Page 28 of 51 , 'of the OEP-R f attachment f or the current.NEP-6. l.An\\ additional consideration wa in OEP-il or NEP-6.1. However, no positive response is requird /d / d A review of the SQN and WBN Project Manuals j: a NEP-3.2, has shown that project procedures a,t both plClarifications and Va responses to a multipage list of considerations for the D ants require positive Criteria. No such positive response'is required in the corresponds esign Modification project procedure. At BLN preparer complete, sign, an,d date the ECN checklist which iproject p>W ng 8FN to NEP 6.1, and circulate the list to all revie s identical to opinion of the ev positive response ~aluation team, and is typical of industry practice, that a wers. It is the design change are' being considered.is reouired to ensure that all possible At WBN and BLN, there is no indication'that a positiv onse will be program when it is issued. change control The statement of theLeoncerned employee that when OEP 11 4.02 and 4.52 the list of."yd and "no" check list of oth superseded EN DES-EPs documents was'no longer on the cover sheet is trueer effected to OEP-11 contained 28 such considerationsThe . to NEP-6.1 require a positive "yes" and "no" re and the subsequent sponse. p; Although the statement of the concerned employee is valid found that the latest procedure and its expanded list of co, the ' evaluation te o decided improvement over its predecessor. nsiderations is a documented phoerly.The majority ( Design Change Reauests (DCRs) are p{/ c

4.6.3 Issue

"q shown in Attachment B)] Addressed as issue "c" for all plants, as hb Finding. initiated by NUC PR, that provides a request to EA design change w to a nuclear plant. generally a' DCRs are not considered design documents.ngineering f or a mo,difica agrees with the DCR, it will issue an ECN which references the DCRIf Engi S.! 6. The issue that Design Change Requests (DCRs) are not prope l Q not fully addressed by the Engineering Evaluation Team becaus involved in only the reviev of DCRs. r y documented was gi M DCRs are the responsibility of the originating organi2ati 6 (The prepara E. and are assessed in elem'nt evaluation 307.04 prepared by TVA (R f i.e., NUC PR), F o 4.6.4 e. 101). Issue: The engineering scope and design activities required for modifications are not adequately identified. "d" for all plants, as shown in Attachment B) (Addressed as issue gg a .m u 7 2811D-R26 (10/15/87) h

,p TVA EMPLOYEE CONCERNS ( SPECIAL PROGRAM REPORT NUMBER: 20400 t' REVISION NUMBER: 2 Page 29 of 51 t Finding.fJhe evaluation team focused on the improvements in communic'ating the. change scope that are expected with thi nW, defining and { i control syptem (Ref. 42). design change 9 i The amoun[of' detail included in the brief ci ange description prov { ECN cover is left to the engineering judgment an on the q rer. informal discussions between engineers from the affected disttline modification group personnel. ant The evaluation team 'found no evidence of provision for communication i change scope between engineering disciplines in its procedure to im e permanent design change control system, which will be based on the PMP i j(} ( The issue is valid. } f' 4.6.6 _ Issue: ) long term) design changes with all discipliys and siteT const ruction. impact of design changes.This results in an inadeouate evaluation of the as shown in Attachment B) ( Addressed as issue "e" for all plants, Finding. For BLN, NSRS reports (Ref. 63c), QMS audit reports (Refs made for an ECN have been incomplete and drawin . 240 and i nges revised for the change were somehow overlooked.

f.,!

At SQN and BLN, the evaluation team found no evidence of procedures or Y. direction for any regular coordination meetings between discipline level engineers and site modifications groups to discuss future design changes}(; In the proposed plant modifications program, all design' activity will be{ .h completed and drawings prepared prior to release of an ECN. h interdisciplint and interdeoartment coordination shou % occur as part of th Necessary t.p. plant modification package (PMP) system prior to the installation of phy e M changes by CWstruction or Modifications. ss SQN, WBN, an(d BFN will establish the Change Control Board hl u Ib js t ;y the Deputy,Sita.03redor, to review all ECNs for tfinal appr(CCB), chaired by W \\ oval.. [ b t For BLN, the evaluation team has suggested that regular publication of a hF kg, standard information form provided by the PMP tracking program to all provide the,needed communication of up-coming design } For all four nuclear plants TVA has acknowledged having a problem with coordinating design changes with all disciplines and between organizations &,s f the past (Ref. 42). Em This issue is valid. 94

n w

1 W r m 2811D-R26 (10/15/87) L r

lf 1 4 y ' !( ,I n 'I TVA E'iPLOYEE CONCERNS REPORT NUMBER: 20400 [ l SPE!1AL PROGRAM REVISION NUMBER: 2 (.t' i Page 30 of 51 1 \\

4.6.6 1ssue

delaying construction activities and causing rework.AW exc (Addressed as issue "f" f or all plants, as 'shown in Attachment B) Finding. Discussions with TVA construction personnel (Refs. 243) confirm that tne nurf er (quantity b cause of delays was s) aid to!be " overlapping" ECNs; i.e., a of EC8s has resulted in construction delays. The worst y several unincorporated ECNs outstanding against it and some of the ECNs affect o?,her ECNs. ,c i ./ a.$ NCRs, FCRs, DCRs, 'etc.. CCNs are preoared in response th some ide ECNs control the design work that is to be d4s not control the volume o'f ECffs issued.perf ormed and delineated on Engineering However, it is recognized that w % the number of FCNs and [CN' exceeds the capability of the tracking devipas, there could be a mismatch in the actual plant configuration and plant ' drryi ngs. This is the situation that led to the formation of the

• Cantiguration Control Group (CCG).

1 j ) / The issue is valid. A 4.6.7 _ Issue: ECNs that were signed off in 1978 by Engineering have not g been implemented as of Novamber 1985. 1 ( Addressed as issue "g" f or 4 WBN only, as shown in Attachment B. This issue was determined to be unique to WBN, and was not evaluated for the other (3) plants. O fijdina: The evaluation team iriterprets this concern as meaning that the [ physical work described in an ECN 'that was closed out in 1978 had not bee ' perf ormed bv Construction by 1985. ' WEN, tic closed eben all engineering design work is completed.ECNs fe plan This has been [] ,the ease.h6er the TN DES-EPs, the OEPs, the NEPs, and WBN Project Procedure .43.02.

i

,/ ,1 a , / The evtJuatiov t6n did not attempt to verify the field implementation of th e1 ./ sheets." Iscead, it focused on evaluating the improvem 3,,200 ECW issued for WBN, and shown as closed in the WBN ECN Log data e L! 9 P! [ i,etticipated ire the perma:Vant design change program (PMP) proposed by s, [ ' ?. (Ref. 220)heact:pe Guidelines (RafiTVA it revising its desion change e INP0Goq 70). 2 p E In the new design change program, which is based on the PtiP, drawings and / O documents revised to incorporate the approved change are held until all have been revised, and then de, issued as one package. The issue-ir7 valid. \\ ^ k I 14Q [ t. \\ r 2811D-R26 (10/15lq)

ng TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 31 of 51 4.7 Element 204.7, Vendor Documents 4

4.7.1 1ssue

Vendor drawings received by the plants from EN DES for as-constructed drawings are of poor quality. (Addressed as issue "a" in element evaluation 204.7 for SQN, BFN, and BLN, and Issue "g" in element evaluation 204.4 for WBN, as shown in Attachment B) Finding. the site are not legible and are of poor quality.The evaluation t In the past, TVA has not had a uniform vendor manual control program to process vendor manual re at the Division of Nuclear Engineering (DNE). problem of illegible drawings by converting the drawings Only a few vendor prints have been put on the CAD syste Since some Vendor prints will be restored on an as-needed basis, with Operations and Enginee determining which drawings are given priority. NQAM. Quality Notice vendor documents are legible and adequately controlled.ID-Q TVA nuclear plant sites and are still in use. Vendor documents of T/A procedures identifying vendor document control did not provide satisf actory com -1 applicable regulatory criteria. and document control is a recognized problem at TVA, and correc are being implemented to correct the problem. i: O The issue is valid. L g".

4.7.2 Issue

Updates of vendor documents (e.g., manuals) are sent to Knoxville or Chattanooga Engineering, but they are not received at the plant in a reasonable time thereafter. (Addressed as issue "b" [ in element evaluation 204.7 for SQN, BFN, and BLN, and issue"h" in E element evaluation 204.4 f or WBN, as shown in Attachment B) W g Finding. The Office of Nuclear Power (0NP) and Office of Construc e could not be assured of receiving the latest revisions to vendor manuals to be F incorporated into their controlled copies in a timely manner. received in Knoxville or Chattanooga. Vendor updates were not sent Revisions to vendor manuals were not distributed in a timely manner. fully implemented. procedures to assure that existing vendor manuals are up to date ha TVA w k S 2811D-R26 (10/15/87) s o

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 32 of 51 Prior to November 1986, TVA procedures and practices did not establish adeouate measures to effectively control the review, approval, and issuance of vendor manuals, vendor design drawings, and changes to these documents. Vendor documents at the jobsite and Knoxville and Chattanooga are not always identical. A TVA memo dated August Nuclear Power Operations (INPO) corporate evaluation was reviewed.14,19 i In this memorandum, TVA management accepts as valid the f ollowing findings regarding vendor manuals, e.g.: " Finding (2.6A-1): Vendor manuals retained by utility off-site organizations are not maintained in a current status. Some vendor manuals retained by corporate document control personnel and engineering personnel contain outdated inf ormation. Additionally, inf ormation in some manuals is not in agreement with that contained in the master copies of vendor manuals maintained at the plant sites." These examples veriff that vendor manuals within TVA are inconsistent. acknowledgment of the validity of these findings and narrative regarding TVA's on-going efforts within TVA relative to vendor manual control validate the issues of this concern. The issue is valid. 4.8 204.8, Communication Control

4.8.1 Issue

There is a lack of effective communication and interf ace 1 control among the branches of EN DES, and between EN DES and other [( divisions. SQN, issue "g(Addressed as issue "a" in element evaluation 204.8 for " in element evaluation 204.1 for WBN, and issue "f" in element evaluation 204.1 f or BFN and BLN, as shown in Attachment B) [g Finding. Criterion III of 10 CFR 50, Appendix B requires design interf ace b a: control and coordination among participating design organizations. of ANSI N45.2.ll also requires interf ace control within and between [ Section 5 organizations perf orming work affecting desio-Quality. Systematic methods for communicating needed design informatic<. across design interfaces is part f of the interf ace control requirement. To meet these interface control G commitments, TVA has issued both upper-and lower-tier administrative instructions and procedures addressing the subject (Refs. y 38, 113, 108 and 109). r [ An independent review of the Office of Engineering Design and Construction (OEDC) in 1978 (Ref. 93) found that " communication among the multiple organizations involved in procurement [was) not controlled for maximum effectiveness." For example, there were f our organizations in contact with the vendors and six TVA groups coordinating with each other c I 7 28110-R26 (10/15/87)

s + 1 l I .TVA EMPLOYEE CONCERNS REPORT NUMBER: l20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 33 of 51 l l on purchases. To better coordinate purchasing objectives, the independent investigating team proposed the formation of an OEDC/ Purchasing / Division of Law steering committee. A f ollowup investigation in 1981 (Ref. 92) found that "overall coordination between i Purchasing and EN DES had improved." In 10/81, TVA's NSRS reported (Ref. 63c) that the interf ace controls in OEDC -were generally adeouate. However, there were inadequacies in the interdivisional quality assurance procedures regarding interf ace . performing reviews, and controlling vendor manuals. responsibilities i In early 1984,. the NRC SALP Board found (Ref. 205) that "... timely f corrective action continues to be a problem when interdivisional coordination is. required f or resolution of issues." The Board also cited TVA for " failure to establish measures to control design interfaces between participating organizations." i 217) disclosed disparities between documented and actual o Responsibilities, authorities, and organizational interf aces identified in l procedures and organization charts for design and design change control were l not revised in a timely manner to delineate organizational interfaces and l lines of communications. filled in a timely manner.-Furthermore, organizational vacancies were not I 1 t Finally, in late 1985, INPO (Ref. 213c) found the following communication and coordination deficiencies: o ... many TVA reorganizations have been implemented without needed policy document revisions, with the result that effective communications and smooth coordination are not occurring."

i

? E " Communications and teamwork between the OE and Nuclear Operations o need improvement, especially at the nuclear plant sites. [ Work changes and misunderstandings) have contributed to mistrust between ( the two organizations and, in some cases, led to duplication of r! eff ort. " p} Based on the above statements made by other investigators, the evaluation team concluded that there were significant emmunication and i,nterface coordination p problems between TVA's nuclear power organizations. t i m l i. U yf 2811D-R26 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 l SPECIAL PROGRAM REVISION NUMBER: 2 Page 34 of 51 Despite the existence of applicable procedures, there were many communication ) and interf ace problems between the engineering branches and between < engineering and the other divisions. Responsibilities, authorities, and ] organizational interf aces identified in procedures and organization charts for design and design change control were not revised in a timely manner to delineate organization interf aces and lines of communications. The issue is valid. l 4.9 Element 204.9, Use of Reverse Prints i

4.9.1 Issue

Unit 1 prints marked " opposite hand" are being used for unit 2, wnich makes work more confusing f or engineers and construction workers. ( Addressed as issue "a" in element evaluation 204.9 f or SQN, BFN, and BLN, and issue "i" in element evaluation 204'.4 f or WBN, as shown in Attachment B) Finding. The evaluation team f ound that the use of. opposite hand drawings f or construction does make work more confusing for engineers and construction workers; however, the evaluation revealed the following: o At WBN, interviews with TVA personnel (Refs. 240, 241, and 242) l indicate that the use of opposite hand drawings has not resulted in ) construction delays or increased costs. I } o At SQN, interviews with engineering, construction, craft, and j Quality Assurance personnel confirm that the use of opposite hand drawings was not cost effective and resulted in rework during l constructi on. Construction worker.s and construction engineers spent considerable hours using light boxes and window panes to trace drawings on the back cf the sheet to get " proper hand" configuration. Errors resulting from the use of these drawings include improper positioning of Unit 2 Reactor Vessel supports and f abrication errors on the Number 3 heater drain tank. J o At BFN, the evaluation team was unable to find evidence, because of the early timeframe of BFN construction, that the use of opposite i hand drawings f or construction and startup caused confusion. o At BLN, interviews with TVA personnel indicate that the use of l. opposite hana drawings has resulted in construction delays and l increased c0sts. t l The use of " opposite hand" drawings has made work more confusing f or l Engineering and Construction personnel, and it has resulted in some rewerk, l increased costs, ar,d schedule delays. However, experienced personnel at all the plants are nov f amiliar with the use of these drawings and indicate that their continued use would present no further difficulty. Therefore, the issue is valid, but it does not represent a problem. 28110-R26 (10/15 /8M

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 35 of 51 4.10 Summary of Subcategory Findinas i The classified findings are summarized in Table 1. Class A and B findings indicate there is no problem and that corrective action is not required. Class C, D, and E findings require corrective actions. The corrective action 1 class, defined in the Glossary Supplement is identified in the table by the ( numeral combined with the finding class. For example, the designation D2 in i Table 1 indicates that the evaluated issue was found to be valid (finding Class D) and that a corrective action involving some type of procedure modification is required (corrective action Class 2). Findings are summarized by classification in Table 2. Table 2 identifies one finding for each issue evaluated. Of the 124 findings identified by a classification in Table 1, 72 require no corrective action. Of the remaining issues, 51 had corrective actions initiated before the ECTG evaluation, and one resulted from a peripheral finding uncovered during the ECTG evaluation. \\ 5. CORRECTIVE ACTIONS TVA's new organizational structure focuses management attention on development of adequate procedures and on training personnel in the use of the procedures. The CNPP charges EA with the responsibility f or training DNE employees in the use of quality-related Nuclear Engineering Procedures. In addition, the independent EA overview authority (audit function) will provide feedback to management on engineering perf ormance. i In general, TVA senior management has identified the need for strengthening its Engineering organization in response to the requirements of nuclear plant design. The Engineering organization is responsible f or the content and Quality of the design documents and for ensuring that they conf orm to sound engineering principles, licensing commitments, and Quality Assurance program requirements. This need for strengthening is based, in part, on deficiencies in design process effectiveness. This need is also partially based on past implementation of the TVA Quality Assurance program. Thus, the need f or strengthening the Engineering organization, as indicated by the NPPs, is accomplished primarily through additional training of the DNE personnel to the. requirements of that program and to basic management principles. DNE Nuclear Engineering Procedure NEP-5.2 and policy memo PM 87-35, "(DNE) - J Project / Branch Responsibilities," dated January 23,1987[ RIMS B01 870123 002), clearly delineate the responsibility,gauthority, and accountability of the Project Engineers and Branch Chiefs. The Project j Engineer is responsible f or work scope, budget, and schedule, and f or ensuring that project work is executed according to plan and in conformance with the I technical direction of the Branch Chiefs and the requirements of the corporate QA program. The Branch Chiefs are responsible f or staffing levels and qualifications of technical personnel on the projects, and for the technical adequacy of the engineering design. The Branch Chiefs are the final technical 4 2811D-R26 (10/15/871 i

TVA EMoLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 36 of 51 i authority within DNE, and have the authority to stop work that does not I conf orm to established requirements. In the past, Branch Chiefs' authority or resources to fully administer technical reviews was limited. Under the restructured organization, the Branch Chief provides engineers and technical direction for the Project Engineer; the Branch Chief also assesses the need for technical reviews, develops a document review and approval matrix, and schedules reviews as required. These programs have been started but have not been fully implemented. The manager of EA reports to the director of DNE on all matters other than I QA. The manager of EA has authority to stop engineering work that does not conf orm to established requirements. In reviewing EA's audits at SQN OF THE DBVP, the evaluation team finds that the methodology and performance have been effective in identifying problems and in implementing corrective actions. Table 2 identifies 52 findings that require corrective action. Since some of the corrective actions apply to more than one plant, only 11 different corrective actions are required to remedy the 52 negative findings. The detailed corrective action descriptions are contained in Attachment B. A condensation of this information by element, with the applicable plant identified in parentheses, f ollows: 5.1 Organizational Structure - Element 204.1 Responsibility f or all nuclear activities has been consolidated within the Office of Nuclear Power; this group is responsible only for nuclear activities. TVA's nuclear headquarters and site personnel have been reorganized. Design and system engineers are being located at the sites to provide engineering support in a timely manner. (All plants) 5.2 Design Review / Verification - Element 204.5 No further corrective action is recuired f or procedures because, in general, the current DNE procedures NEP-5.2 for design review and verification were found to be adeauate on a division-wide basis. However, more emphasis and management attention must be focused on full and complete implementation of these procedures and requirements. Also, management must direct its attention to providing adequate staffing to allow careful review and checking of engineering work and desip documents as they evolve. The conducting of design reviews is further addressed in DNE Policy Memo 87-35 (all plants). At BFN, the organization described in Volume 3 of TVA'I Nuclear Performance Plan, Revision 1 is in place. The perf ormance plan establishes Engineering Assurance (EA) to develoo, issue, maintain, and control nuclear engineering procedures and ensure that the procedures mesh with procedures of other organizations. EA also provides training f or DNE personnel in the use of engineering procedures and provides feedback to management on engineering perf ormance. (BFN) 2811n p?6 (in /15 /97)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 4 SPECIAL PROGRAM REVISION NUMBER: 2 Page 37 of 51 At BFN, a problem identification report (PIR) will be written that addresses the apparent lack of design verification f or some bill of material (BM) i drawings. The sample of BM drawings identified in the CATD will be reviewed, j and the sample will be expanded as necessary to address the PIR and identify those drawings "made" and " checked" by the same individual. The design will be verified per DNE 5.1 or dispositioned by approved methods. A CAQR/PIR is to be written to identify any deficiency f ound. The PIR will be closed after all subject BM drawings are verified, revised and/or dispositioned. (BFN) 5.3 ECN Process - Element 204.6 Corrective actions under this element apply to the f our plants as f ollows: 1 o The concept of consolidated plant modification packages (PMPs) f or l controlling modification.ns at each site is addressed.in the Corporate Nuclear Performance Plan. The specific details f or implementation of the PMPs will be in NEPs 6.3, 6.4, 6.5, 6.6, and 6.7. Implementation of the NEPs is scheduled for December 31, 1987. t Documentation of the final disposition of the CATD will be provided l to ECTG. Actual schedule for implementation of the PMP at each plant will be provided as part of the documentation and final disposition of the CATD (all plants). Implementation of NEP 6.3 will provide corrective action at all plants. A prescoping meeting between Division of Nuclear g Engineering (DNE) and Division of Nuclear Power (NUC PR) oersonnel ] is required before design begins. Review of the design by all involved DNE disciplines is required during and following the design process. (Allplants) The PMP will not contain checklists. However, the PMP process will require that approximately 20 major items of concern be specifically addressed in the modification package. The preparer will not sign each item but will sign the PMP. These items will be reviewed by all involved disciplines before the PMP is issued. (All plants) o The CAP committed to the issuance of DNE procedures NEP-6.3, 6.4, f 6.5, 6.6, and 6.7 to reflect the design control program committed to in the Corporate and SQN Nuclear Perf ormance Plans. TVA letter [L44 870512 802] dated 05/12/87, contains a f ormal commitment by TVA to the NRC to implement the PMP at SQN and also provides a schedule f or doing so. The commitments are listed in the Corporate Commitment Tracking System (CCTS) as Items NC0-0870184001, NCO-0870184002, NCO-0870184003, and NCO-0870184004. Implementati on of the PMP for SQN will begin by December 31, 1987. (SQN) o At WBN, the site process and procedures f or the PMP program will be developed as part of the Design Baseline and Verification Program (DBVP)~ and implemented before unit 1 fuel load. (WBN) ?Q11h.DOA f in /1 R /0%

1 TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 .i SPECIAL PROGRAM REVISION NUMBER: 2 Page 38 of 51 o At BFN, the PMP process has been in place since implementation of BFEP PI 86-03 on June 16, 1987. NEP 6.3 and NEP 6.4 to be' issued in September 1987 and implemented by December 1987 will provide,further - design change control improvement. BFEP PI 86-03 will be revised to l reference NEP 6.3 and.NEP 6.4. (BFN) o ECNs issued after the operating license was issued are being reviewed as part of the DBVP. (BFN,_SQN)- o At BLN, the PMP program has not yet been implemented. An engineering procedure to control the work will be issued by November 30, 1987. Full implementation requires the issuance of DNC l and NSD procedures which will be developed after DNE procedures are devel oped. (BLN) 5.4 Vendor Documents - Element 204.7 There are corrective actions under this element f or f all f our-plants. o Implement Sequoyah Engineering Procedure (SQEP) SQEP-39, " Review and . Approval of Vendor Manuals / Revisions." (SQN) o At WBN, site-specific procedures will be developed to implement the l requirements of ID-QAP-6.2 and related Office of Nuclear Power (0NP) d policies and directives. A specific action plan identifying vendor manuals for safety systems or those affecting safety-related systems will be developed. Existing manuals will be placed under " Conditional Use" status bef ore WBEP DNE review. These manuals will be placed in " controlled" status after WBEP review. Other manuals status with the concurrence of may be placed in "Inf ormation Only"(WBN) all affected site organizations. o' At BFN, Project Instruction (PI) 87-48 is being written and will supersede DNE's portion of Standard Practice BF-2.5 which describes the drawing restoration function. Vendor drawings that are illegible afe also being restored. BFN has had a drawing restoration program in place f or 2 years. (BFN) o The corrective action is to improve the Quality (legibility) and distribution control of vendor documents. Closure of BLN Significant Condition Report (SCR) GENERI 8QO2 and completion of Corporate Ccmmitment Tracking System (CCTS) Commitment NCO-84-0067-006 will satisf actorily resolve these findings. (BLN)- 5.5 Communication and Interf ace Control - Element 204.8 ? The Office of Nuclear Power (0NP) will develop standard procedures t'o control interfaces with support organizations (such as the Division of Purchasing). The ONP also plans to develop five levels of integrated procedures, which, among other things, will establish management interf aces. ( All plants) OQ11n.00A Ii n /1 C / A71

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 ~ Page 39 of 51 5.7 Summary of Subcategory Corrective Actions These corrective actions also appear in Table 3, along with their corresponding finding / corrective action classifications. The table indicates the plant or plants to which a corrective action is applicable by the d Corrective Action Tracking Document (CATD) column where the applicable plant is identified by the CATD number. From the Finding / Corrective Action Classification column of Table 3, it can be L seen that of the 11 corrective actions identified, one indicates a need to restructure at least part of management, two indicate a need to increase management attention to training and staffing, and the remaining eight require improvement in the quality and implementation of engineering procedures. In addition, the CATO column of Table 3 shows that, in most cases, a particular corrective action is applicable to all plants. The corrective action on element 204.5, which involves training and staffing, is the only corrective action applicable to only one plant (the employee concern was unioue to BFN). Finally, Table 3 shows that, of the nine elements in this subcategory, f our reauire no corrective action (namely, 204.2, 204.3, 204.4, and 204.9). The element requiring the largest number of corrective actions is 204.6, ECN Process, which has f our. TVA has developed a series of nuclear performance plans (NPPs) to correct programmatic and management deficiencies that have contributed to the past poor direction and control of TVA's nuclear activities. Volume 1 of the NPP describes the measures that TVA has taken and currently intends to take to improve the corporate-level management of its nuclear activities and to correct the problems that have occurred in this area. Volumes 2, 3, and 4 address, respectively, SQN, BFN, and WBN. There is currently no NPP f or BLN. The three plant-specific NPPs provide an account of the actions TVA is taking to improve its nuclear program. These measures, when completely implemented, should ' resolve the identified problem areas and prevent their recurrence. Engineering organization and procedures, and the specific subtopics addressed in the element evaluat. ions that comprise this subcategory, are addressed in the following sections of the corporate and respective plant nuclear perf ormance plans: Corporate,

Sequoyah, Browns Ferry, Watts Bar, Element Volume 1 Volume 2 Volume 3 Volume 4 204.1 Orgar.izati onal IV and VI II.2.0 III.2.0 VI.1 Structure i

204.2

System Design

VI.C.1 11.1.0 III.2.0 VI.1 Respen ibility 9 ?Q11n.07A ( 10 /14 /n7)

4 TVA EMPLOYEE CONCERNS REPORT NUMBER:- 20400 SPECIAL PROGRAM REVISION NUMBER: 2 .) Page 40 of 51 l i Corporate, Sequ oyah, Browns Ferry, Watts Bar, Element Volume 1 Volume 2-Volume 3 Volume 4 204.3 VI.E.4 II.1 11.1 .VI.1 Design Responsibility - Field vs Office 204.4 VI.E.4 11.2 -11.2 II.2 Design Documentation Completeness 204.5 Design Review. VI.E.4 11.1 11.1 II.2 Process 204.6-VI.C II.2 and III.&- V.7 ' ECN Process and II.3-Scope of Engineering Required f or u Modification 204.7 Vendor VI.E.4 II.2 II.2 and II.2 Documents III.2 204.8 Organization VI II.1 Included VI.1 q I or Operating in 204.1 Procedures 204.9 VI.E.4 II.1 II.1 II.2 Use of Reverse Prints The evaluation team f ound the corrective action plans, as stated in this report, to be acceptable to resolve the findings of the elements of this subcategory, t. 6. CAUSES Table 3.also identifies one or more causes for each negative finding (those requiring corrective action). For each corrective action, the most important cause is identified; however, in many instances, it was felt that the problem '0 90110.09A ( 10 /1 E /Q7)

TVA EMPLOVEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 41 of 51 resulted from a combination of causes, each of which should be identified. In those cases, more than one cause is identified. Whenever direct evidence linked a cause to a problem requiring corrective action, such evidence was taken into account. For the 11 corrective actions described in Table 3, f our causes have been indicated. These are shown in the table and totalled at the end. The most i frequent cause noted is " Inadequate Procedures." Next is " Procedures Not Followed," then " Lack of Management Attention," and " Fragmented j Organi zati on. " These causes reflect management's f ailure to provide a strong l quality assurance program. A strong program should have revealed at an early date that TVA procedures were inadequate in that they were sometimes l cumbersome and lengthy, and sometimes did not provide sufficient information 4 or instructions to accomplish the tasks. Consequently they were not followed l consistently. Bef ore 1984, there was also an apparent lack of training of l engineering personnel in the use of procedures. I 4 The engineering groups at the plants were separated from the central engineering group at TVA's Knoxville offices. This fragmented organization resulted in uncoordinated plant changes and central engineering group drawings that did not match plant drawings. The division-wi'de engineering procedures ) were written to be applicable to the central engineering organization and were l not always directly applicable to the plant organization. These conditions l resulted in inadequate and inappropriate procedures. The " Inadequate Procedures" also led to difficulties in the plant modification process prompting changes in procedures covering the ECN documentation process and to the initiation of the plant modification package (PMP) program. At at least one plant (BFN), there is evidence to indicate that training was inadequate because of an insufficient number of training personnel. At the same plant some documents were originated and checked by the same individual, which is a violation of procedures and prudent engineering practice. It is significant to note that, in the early years of the nuclear industry, there was a lack of understanding of some regulatory requirements and governing documents by TVA and others. One result of this situation was insufficient documentation of the design basis for the early plants. This situation also made later verification of the adequacy of the design difficult. 7. COLLECTIVE SIGNIFICANCE The 36 concerns expressed in the subcategory identified 51 findings that require corrective action. All but one of the needed corrective actions were already in progress at the time of the ECTG evaluation. The corrective actions in progress or completed were initiated in response to the corporate and plant-specific NPPs. One was the result of a peripheral finding identified by the ECTG that required a new corrective action plan (CAP). For the 11 corrective actions identified by the ECTG, corrective action tracking documents (CATDs) have been issued to ensure documentation of completion of CAPS already in place. 28110-R26 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 42 of 51 The negative findings in this subcategory indicate that TVA's management and engineering organizational structure, as well as nuclear engineering design processes, represented a significant programmatic problem when the concerns were expressed. TVA has acknowledged these problems, and has either implemented or outlined corrective actions that should resolve the problems. However, at the time the employee concerns were raised, procedures were in place that, when followed, would have mitigated the problems. The fact that many procedures were not adequately followed is an indication of poor management attention to the practices of the responsible departments. It must be recognized that the purpose of procedures is to provide an orderly design process. The desired end product is a correct design, which is the responsibility of the engineering line management, i.e,. branch chiefs and lead engineers. The collective significance of the findings is that, at the time the concerns were raised, TVA's management structure for the engineering, construction, and operation of its nuclear plants was fragmented. Its divided reporting structure resulted in divided responsibility and poor interdepartmental c ommunic ati on. This disorganization was especially apparent in the control of engineering design changes and of design change documentation. If organizational and procedural changes had not been made, eventually there would have been a significant mismatch between the plant configuration and the enoineer.ing drawings and records, which could have resulted in an engineering design error or plant operating error. The present-day organizational structure and operating procedures, when properly implemented, should mitigate problems such as those experienced in the past. { Of particular significance is the f act that the need for strengthening the TVA Engineering organization in response to the requirements of nuclear plant design has been identified. The Engineering organization is responsible for the content and quality of the design documents and for ensuring that they conform to sound engineering principles, licensing commitments, and Quality Assurance program requirements. This need f or strengthening is based on past deficiencies in design process effectiveness and on poor past performance in . implementation of the TVA Quality Assurance program. Thus, the need for strengthening the Engineering organization, as indicated by the NPPs, is accomplished primarily through additional training of the DNE personnel to the requirements of that program and to basic management principles. DNE Nuclear Engineering Procedure NEP-5.2 and policy memo PM 87-35 clearly delineate the responsibility, authority, and accountability of the Project Engineers and Branch Chiefs. The Project Engineer is responsible for work scope, budget, and schedule, and f or ensuring that project work is executed according to plan and in conformance with the technical direction of the Branch Chiefs and the requirements of the corporate QA program. The Branch' Chiefs are responsible for staffing levels and qualifications of technical personnel on the projects, and for the technical adequacy of the engineering design. The Branch Chiefs are the final technical authority within DNE and have the authority to stop work that does not conform to established requirements. 2811D-R26 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 43 of 51 An independent audit on the effectiveness of the implementation of the total Quality Assurance program is instituted by Engineering management, as a management tool, to additionally ensure that management policy is being enforced. This audit function is provided by the Engineering Assurance (EA) organization, which provides feedback to management on engineering perf ormance. The results of this subcategory evaluation are being combined with the other subcategory reports and reassessed in the Engineering category evaluation. l l t, t 28110-R26 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 f. L SPECIAL PROGRAM REVISION NUMBER: 2 Page 44 of 51 TABLE 1 CLASSIFICATION OF FINDINGS AND CORRECTIVE ACTIONS Finding / Corrective Issue / Action Class

• Element Finding **

SON W8N BFN BLN 204.1 Organization Structure a C7 C7 C7 C7 Requires Excessive b A A A A L Document ati on,. Reviews / c C2 C2 C2 C2 l Approvals, Procedures, d A B B and Response Times; e A A A Design Responsibility; f f or WBN C2 (3) (3) l C2 C2 Communication and Inter-f f or SQN, (4) f ace Control BFN, BLN C2 g WBN only ] C7 h WBN only a B (1) (1) (1) 204.2 System Design Responsibility b 'A (1) (1) (1) 204.3 Design Responsibility a A (1) A A a C7 C7 C7 8 204.4 Design Document Completion b A A A A c C7 C7 C7 8 d C7 C7 C7 8 e C6 C7 C6 8 1 C6 f WBN only i (6) B (6) (6) 204.5 Design Review Process / a A A A A Independent Verification, b A A A A c A A E6 A Policy and Practice Vendor Explanation of classes is on the next page. Defined for each plant in Attachment B. (1) Issue addressed in element evaluation 204.1. l (2) Issue addressed in element evaluation 204.2. (3) Issue addressed in element evaluation 204.3. (4) Issue addressed in element evaluation 204.8. (5) Issue addressed in element evaluation 204.7. (6) Issue addressed in element evaluation 204.9. l 28110-R26 (10/15/87)

?- J - i. DTVA EMPLOYEE CONCERNS REPORT NUMBER:' '20400' . M (*St?'" b+f 'hi -SPECIAL PROGRAM. REVISION NUMBER:.2 Page.45 of 51 7 .. ) i TABLE 1 (Cont'd) Finding / Corrective Issue /- --Action Class

• 1 Element Finding **-

SQN WBN BFN BLN' 204;5 DesignsL and Calculations,. d' A1 A: A A (cnt'd) Changes to. Vendor Designs e A A A-A l f-A A A A g A A 14 A h A-A A A C7 11 f or BFN A i f or BLN C4' j BFN only; B- -k BFN only: 204.6~ ECN Process a1 C2 C2 C2 C2 b A A C2 .A c A' -A A A. d C2 C2~ C2-C2 e C2 C2 .C2 'C2 f A- 'A A A' B g f or BFN C2 g f or WBN ~ 204.7 Vendor Documents a. -C2 7 C2-C2 b C2 7 C2 C2 204.8 Communication and Inter-- a C2 (1) (1) _(1) 'f ace Control 204.9 Use of Reverse Prints a B (7) B B (1) Issue addressed in element evaluation 204.1. (7) Issue addressed in element evaluation 204.4.

• Classification of Findinas and Corrective Actions A.

Issue not valid.

1. Hardware No corrective action required.

2. Procedure B.

Issue valid but consequences acceptable.

3. Documentation No corrective action required.

4. Training

_ C. Issue valid. Corrective action

5. Analysis initiated bef ore ECTG evaluation.

6. Evaluation D.

Issue valid. - Corrective action

7. Other taken as a result of ECTG evaluation.

Peripheral issue uncovered during ECTG E. -evaluation. Corrective action required.

• • Defined f or each plant in Attachment B.

x 28110-R26 (10/15/87)

-) ..n, TVA EMPLOYEE CONCERNS LREPORT. NUMBER: 20400

SPECIAL' PROGRAM

' REVISION NUMBER:- 2 ..Page 46 of.51. d g._ l TABLE 2 -l o ' FINDINGS

SUMMARY

~ Plant .j Classification of Findings SON WBN BFN BLN.

Tot al 15:

15. 13-16~

59; .) A. Issue not.: valid. No corrective action required.- B. Issue valid but consequences acceptable.

2. -

- 4' 6~ 13 No corrective ' action required. C. Issue. valid. Corrective action - ' 12 16 15-8. 51 . initiated before ECTG evaluation.. 0 LD., Issue valid. Corrective' action taken as a. result of ECTG' evaluation. 1 1 . E.' Peripheral issue' 'uncovere'd during ECTG evaluation. Corrective' action required. i Total 29 32 33' 30 124 l t-4 l l L. l' L-t e -em_ nWZ '.* C - ~ ~. A 28110-R26 (10/15/87)

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TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 49 of 51 GLOSSARY SUPPLEMENT FOR THE ENGINEERING CATEGORY Causes of Negative Findings - the causes f or findings that require corrective action are categorized as f ollows: 1. Fraamented organization - Lines of authority, responsibility, and accountability were not clearly defined. 2. Inadeauate cuality (Q) training - Personnel were not fully trained in the procedures established f or design process control and in the maintenance of design documents, including audits. 3. Inadeauate procedures - Design and modification control methods and procedures were deficient in establishing requirements and did not ensure an effective design control program in some areas. 4. Procedures not f ollowed - Existing procedures controlling the design process were not fully adhered to. Inadeouate communications - Communication, coordination, and 5. cooperation were not fully effective in supplying needed information within plants, between plants and organintions (e.g., Engineering, i Construction, Licensing, and Operations). and between interorganizational disciplines and departments. 6. Untimely resolution of issues - Problems were not resolved in a timely manner, and their resolution was not aggressively pursued. 7. Lack of management attention - There was a lack of management attention in ensuring that programs required f or an effective design process were established and implemented. 8. Inadeouate design bases - Design bases were lacking, vague, or incomplete f or design execution and verification and for design change evaluation. 9. Inadeauate calculations - Design calculations were incomplete, used incorrect input or assumptions, or otherwise failed to fully demonstrate compliance with design requirements or support design output documents. 10. Inadeauate as-built reconciliation - Reconciliation of design and licensing documents with plant as-built condition was lacking or incomplete. 28110-R26 (10/15/87) J

m TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL' PROGRAM REVISION NUMBER: 2 Page'50-of 51 l

11. - Lack of design detail - Detail in. design output. documents was I

insufficient to ensure compliance with design requirements. 12. Failure to document engineering judgments - Documentation justifying i engineering judgments used in the design process was lacking or l l inc anplete. ) 1

13. Desion criteria / commitments not met - Design criteria or. licensing commitments were not met.

14. Insufficient verification documentation - Documentation'(Q) was 'i~ insufficient to audit the adequacy of design and installation. 15. Standards not followed - Code or industry standards and practices were not complied with. 16. Engineering error - There were errors or oversights in the assumptions, methodology, or judgments used in the design process. 17. Vendor error - Vendor design or supplied items were deficient f or l the intended purpose. Classification of Corrective Actions - corrective actions are classified as belonging to one or more of the f ollowing groups: l '. Hardware - physical plant changes 2. Procedure - changed or generated a procedure

3. -

Documentation - affected QA records 4. Training - required personnel education - 5. Analysis - required design calculations, etc., to resolve 6. Evaluation - initial corrective action plan indicated a need to evaluate the issue before a definitive plan could be established. Theref ore, all hardware, procedure, etc., changes are not yet known '7. Other - items not listed above Peripheral Finding (Issue) - A negative finding that does not result directly .f rom an employee concern but that was uncovered during the process of evaluating an employee concern. By definition, peripheral findings (issues) reauire corrective action. t 28110-R26 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page 51 of 51 Significance of Corrective Actions - The evaluation team's judgment as to the significance of the corrective actions-listed in Table 3 is indicated in the last three columns of the table. Significance is rated in accordance with the type or types of changes that may be expected to result from the corrective acti on. Changes _ are categorized as: Documentation change (D) - This is a change to any design input or o output document (e.g., drawing,' specification, calculation, or procedure) that does not result in a significant reduction in design margin. Change in design margin (M) - This is a change in design o interpretation (minimum requirement vs actual capability) that results in a significant (outside normal ' limits of expected l accuracy) change in the design margin. All designs include margins to allow for error and unforeseeable events. Changes in design margins are a normal and acceptable part of the design and construction process as long as the final design margins satisfy regulatory requirements and applicable codes and standards. Change of hardware (H) - This is a physical change to an existing o plant structure or component that results from a change in the design basis, or that is required to correct an initially inadequate design or design error, j If the change resulting from the corrective action is judged to be j significant, either an "A" for actual or "P" f or potential is entered into the appropriate column of Table 3. Actual is distinguished from potential because corrective actions are not complete and, consequently, the scope of required changes may not be known. Corrective actions are judged to be significant if the resultant changes affect the overall quality, perf ormance, or margin of a safety-related structure, system, or component. I t, i 1 4 28110-R26 (10/15/87) l 1

r_ .i 1 - TVA EMPLOYEE CONCERNS REPORT NUMBER:. 20400 SPECIAL' PROGRAM. . REVISION' NUMBER: 2 Page A-1 of.8. . ATTACHMENT A-EMPLOYEE CONCERNS FOR. SUBCATEGORY 20400 .! Attachment.A -- lists, by element, each employee concern evaluated in the j ) ' subcategory. - The concern's. number is given-along with notat on of any other i subcategory with which the concern is shared and the~ plant sites to which it could be applicable..The concern is quoted as received by TVA and. characterized by TVA' as-safety related (SR), safety significant (SS), or not safety'related(NO). j e 4 . e f 0107A-R50 (10/15/87) J

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TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page B-1 of 42 ATTACHMENT B

SUMMARY

OF ISSUES, FINDINGS, AND CORRECTIVE ACTIONS FOR SUBCATEGORY 20400 Attachment B -- contains a summary of the element-level evaluations. Each issue is listed, by element number and plant, along with its corresponding findings and corrective actions. The reader may trace a concern from Attachment A to an issue in Attachment B by using the element number and applicable plant. The reader may relate a corrective action description in Attachment B to causes and significance in Table 3 by using the CATD number l which appears in Attachment B in parentheses at the end of the corrective l action description. The term " Peripheral finding" in the issue column refers to a finding that occurred during the course of evaluating a concern but did not stem directly from a employee concern. These are classified as "E" in Tables 1 and 2 of this report. D e L 0107A-R50 (10/15/87)

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g r o ,n p2 e p w otr " ionf. d u s e gr g k rne roik s afsr e N m uo u L df w s B sen s t son nuco I irget i 9 pnrc 4 iou emr 0 I 2 b t t k s t i ern n nroo e Uawc me l E a lllif l l.

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page C-1 of 27 ATTACHMENT C REFERENCES Title 10 of the Code of Federal Regulations, Part 50 (10CFR50), 4 1. Chapter 1, Appendix 8, " Quality Assurance Criteria For Nuclear Power Plants and Fuel Reprocessing Plants;, Criterion III, " Design Control," and Criterion V, " Instructions, Procedures, and Drawings," Criterion XVI, " Corrective Action" Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50), 2. Chapter 1, Appendix B, " Qualification Assurance Criteria for Nuclear Power Plants and Fuel Reprocessing Plants," (as amended, 01/75) Title 10 of the Code of Federal Regulations, Part 50 (10 CFR 50), 3. Section 50.49, " Environmental Qualification of Electrical Eq' ipment f u Important to Safety For Nuclear Power Plants," (01/01/86) i Title 10 of the Code of Federal Regulations, Part 50,10 CFR 50.55, l' 4. " Conditions of Construction Permits," Reporting Criteria for Significant Deficiencies 50.55(e) Regulatory Guide 1.28, " Quality Assurance Program Requirements Design and S. l Construction," R0,'(06/07/72) Regulatory Guide 1.30, " Quality Assurance Requirements for the Installation Inspection, and Testing of Instrumentation and Electric 6. I Equipment" j Regulatory Guide 1.33, " Quality Assurance Program Requirements l 7. (Operations)," R2, (02/78) Regulatory Guide 1.64, " Quality Assurance Requirements for the Design of 8. Nuclear Power Plants," R2, (06/76) t ANSI N45.2-1971, " Quality Assurance Program Requirements for Nuclear 9. l Power Plants" ANSI N45.2.11-1974, " Quality Assurance Requirements for the Design of 3 10. Nuclear Power Plants" L j ANSI N45.2.11-1974, " Quality Assurance Requirements for the Design of [I 11. Nuclear Power Plants," Section 4, " Design Process," Section 7, " Document } Control," and Section 8, " Design Change Control," Section 9, " Corrective Action" Section 5, "Interf ace Control" ) ANSI N45.2.10-1973, " Quality Assurance Terms and Definitions" l i 12. l l i I i 38000-R4 (10/15/87) l l l

i TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVIS10ii NUMBER: 2 Page C-2 of 27 13.- ANSI N45.2.9-1974, " Requirement for Collecting Storage and Maintenance of Quality Assurance Records for Nuclear Power Plants" ANSI N18.7-1976, " Administrative Controls and Quality Assurance for the 14. Operational Phase of Nuclear Power P1 ants"

15. NRC OIE IE Bulletin 79-14, " Seismic Analysis for As-Built Safety-Related g

Piping Systems," R2, (07/18/79) 9 16. NRC Generic Letter 83-28, " Required Actions Based on Generic Implications of Salem ATWS. Events," (07/08/83) 17. Sequoyah Preliminary Safety Analysis Report (P.SAR), (10/15/68) E# 18. SQN Updated Final Safety Analysis Report (UFSAR) through Amendment 3, (04/86) 19. Sequoyah FSAR QA Chapter 17, including the Updated FSAR QA, Chapter 17 through Amendment 3

20. Watts Bar Final Safety Analysis Report (FSAR) updated through g

Jf Amendment 55, (04/15/85) 3 21. Watts Bar Preliminary Safety Analysis Report, (PSAR), (05/18/71) [

22. BFN Fina'l Safety Analysis Report (FSAR) through Amendment 31 (09/25/70),

and Updated Final Safety Analysis Report (UFSAR) through Amendment 4, 1 ?, (08/86) 23. Bellefonte Final Safety Analysis Report (FSAR), through Amendment 27, a ~ (06/20/86) 24. Bellefonte Preliminary Safety Analysis Report (PSAR) througn Amendment 13, (10/10/75) TVA-TR75-1 A, " Quality Assurance Program Description for the Design, 25. Construction, and Operation of TVA Nuclear Power Plants," R8, (04/09/85), i R9 (04/17/86) J

26. TVA Nuclear Quality Assurance Manual (NQAM), (11/14/85)

27. Nuclear Quality Assurance Manual (TVA NQAM), procedures reviewed include ID-QAP-1.3, " Work Control;" and Part V, Section 2.4, " Design Change Control System Using Design Change Supplements" 3

28. Nuclear Quality Assurance Manual (Interim); procedures reviewed include i Part 1, Section 2.3, " Design Control" l 3800D-R4 (10/15/87)

.c 3 i TVA' EMPLOYEE CONCERNS ' REPORT NUMBER: '20400 SPECIAL PROGRAM REVISION'NUMBERi 2 Page C-3 of 27

29. Office of Engineering Design and Construction Quality Assurance. Manual for Design and Construction (0EDC), Volume II; procedures reviewed included EN DES-QAP 2.1, " Design Review"

,,+ 3 4 30. Interdivisional. Quality Assurance Procedures Manual for Nuclear Power h' Plants (IPM); procedures reviewed include ID-QAP-3.2 R1, " Processing 'of Construction Change Notifications (CCNs)," and ID-QAP-3.1 R0, "0EDC Site. S Investigation for Design Purposes" l 31. Quality Assurance Program Requirements Manual for Design, Procurement, i and Construction (PRM); procedures reviewed include 3QPD-1, " Requirements for Specifying Codes and Standards," and 3QPR-1, " Design Control" a P

32..Sequoyah Nuclear Plant-Quality Assurance Manual, (SQN NQAM)

Quality Assurance Procedures.(QAPs) employed-in the review of this { element are from Revision 11 of the SQN NQAM (and prior).. The -QAP is : ~ a SQN-QAP-IV-4.1, R0, " Control of Preoperational' Testing of l 5 Structures, Systems, and Components" N SQN-QAP-111-1.2, R1 " Control of Design Documents" (08/13/71).

33..Sequoyah Nuclear Plant Quality Assurance Manual (SQN QAM), R12, (12/31/75)-

p 34. Sequoyah Nuclear Plant Quality Assurance Manual (SQN 0AM),'Section III, d " Quality Assurance ' Procedures - Design," and Section IV, " Quality E Assurance Procedures - Construction" 35. Sequoyah Nuclear Plant Quality Assurance Manual (SQN-QAM), R12,. N -(12/03/75): Section III, " Quality Assurance Procedures -. Design" 36. Office of Engineering Design'and Construction (0EDC) Quality Assurance m-F Manual, (no revision number), (09/12/75), (TTB 074, 07/14/86) ~ I h' ~TVA Interim Nuclear Quality Assurance Manual (NQAM), (10/21/86) 37. ~ (L16 860619 805): 4 Part I, Section 2.6, " Document Control," R0 (06/18/86) Part V, Section 6.2, (ID-QAP-6.2) " Vendor Manual Control," (12/31/85) 7l' ID-QAP-6.1, RO, " Configuration Drawincj Co'ntrol" (06/18/86) Part I, d, .Section ID-QAP-6.2, R0, " Quality Notice - Vendor Manual Control," g (11/28/86) A P 38. TVA Office of Nuclear Power Quality Assurance Manual (ONP QAM), R1, J. - (10/21/86) 4 i 38000-R4 (10/15/87) a

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVlSION NUMBER: 2-Page C-4 of 27 }

39. TVA Nuclear Quality Assurance Manual (NQAM), Volumes 1 and 2, (10-21-86),

. consisting of a series of Interdivisional Quality Assurance Procedures (ID-QAP's). 40. Browns Ferry Nuclear Plant Construction Quality Assurance Manual (BFN r CQAM)(initialissue 07/24/70)

41. TVA NPP, _ Volume 1, Corporate Nuclear Performance Plan, R2,- (08/13/86) t 42.

TVA Corporate. Nuclear. Performance Plan, Volume 1, 'R4, (03/26/87) .43. TVA'NPP, Volume 2, Sequoyah Nuclear Performance Plan, R1, (07/17/86)

44. Sequoyah Nuclear Performance Plan, Volume 2, Final Concurrence, Chapter II-4, " Maintenance" (L44 860714 800), (07/14/86) g

45. Watts Bar Nuclear Performance Plan, Volume 4, (Draft, 03/13/87), TTB 373, 5

) 05/06/87). - 4 6.. TVA NPP, Volume 3, Browns Ferry Nuclear Performance Plan, (08/86), j p (09/22/86) Sequoyah' Engineering' Project - Project Manual, R0, (09/27/85) 47.

48. TVA~ Office of Engineering, Watts Bar Engineering Project (WBEP), Project' Manual, R1,.(01/09/86)

49. Watts Bar Engineering Project - Project Manual, R1, (01/09/86):

WBEP-EP 43.02, RO, " Engineering Change Notice," (09/27/85) WBEP-EP 43.03, R0, " Field Change Requests," (09/27/85) Project' Manual : WBEP-EP 43.02, R1, WattsBarEngineeringProject,(04/27/87) 50. f " Engineering Change Notices," f

51. Browns Ferry Engineering Project - Project Manual, R4, (09/29/86)

Il ?

52. Browns Ferry Engineering Project (BFEP) Manual, BFEP PI-86-27, R0,

" Vendor Manual Technical Review," (09/24/86) 1 53. Browns Ferry Engineering Project, Project Manual: I E= NEP-3.2 "BFN Variance / Clarifications to NEP-3.2, Design Input" p NEP-6.1 "BFN Variance / Clarifications to NEP-6.1, Change Control" l PI 86-03 " Preparation and Control of Engineering Change Notice 1 Modification Practice" PI 86-14 " Procedure for Evaluating Engineering Change Notices" PI 86-20 " Identification and Assembling of Change Documentation" l 38000-R4 (10/15/87) i

i i TVA EMPLOYEE CONC' ERNS REPORT NUMBER: 20400 SPECIAL PROGRAM-REVISION, NUMBER:. 2' Page C-5 of 27 .I 54. Browns. Ferry Engineering Project Manual, (12/30/86) -1 55. Bellefonte Engineering Project. Manual (BLEPs), R4, (12/31/86) j L 156. Bellefonte Engineering Project, Project Manual: i BLEP-AI-3.2, RO, " Handling of ECNs" BLEP-AI-3.3, R0,." Handling of FCRs" BLEP-AI-3.5, R0, " Handling of-SPRs" l OEP-06, R0, "BLN Variances and Clarifications to OEP-06" OEP-11, R0, "BLN Variances and C1arifications to OEP-11" l i ' 5 7.. Sequoyah Engineering Project, Project Manual: e l NEP-6.1, R2 "SQN Variance / Expansions to NEP-6.1, Change Control '(09/08/86) -l l- 'SQEP-AI-ll R2 " Engineering Change Notices (ECNs)," (02/06/86) i SQEP-AI-ll A R1 " Field Change Requests (FCRs),"'(11/14/85) SQEP-AI-19, (Part III), ~R14 " Plant Modifications: Modifica'tions Requests,"(10/20/86) ,(Part IV), R21 " Plant Modifications: After Licensing," (03/13/87) [ -SQEP 12 R2 " Procedure for Evaluating Engineering Change Notice and } Field Change Notice Documents," (07/23/86) l . SQEP-13, R3 " Procedure for Transitional Design Change Control" l )- (03/05/87) SQEP-36 R1 "Workplan/ Work Request Reviews," (09/08/86) SQEP-13, R2 " Procedure for Transitional Design Change Control" l (12/22/86) SQEP-17, R2 " Procedure for Origination and Categorization of Configuration Drawings (CCDs)" (01/14/87) 58. Sequoyah Nuclear P1 ant Design Baseline and Verification Prdgram, R0, (05/01/86)

59. 'Sequoyah Nuclear Plant, " Design Baseline and Verification Program," R1, (B25 870212 041), (02/12/87) 60.

Watts Bar Nuclear P1 ant, " Design Baseline and Verification Program," R1, -(07/21/86) q I L l 38000-R4 (10/15/87) l c________________

m TVA EMPLOYEE; CONCERNS REPORT NUMBER:- 20400 ~ SPECIAL PROGRAM -REVISION NUMBER: 2 l Page C-6 of.27 i l

61. ;BFN Design Baseline and Verification Program, R0, (07/07/86)

[

62. - Browns Ferry Nuclear Plant Design Baseline and. Verification Program,'R0,

[B22 860714 017], (05/01/86) i e-

63. 'TVA NSRS Reports

-a. R-82-24-WBN,;[GNS 821104'051], (11/04/82)- b. I-85-473-NPS (03/07/86), " Configuration? Control" .R-81-14-0EDC(BLN). (09/29/81), " Major Management Review of OEDC" l c. 1 -[GNS 810930 054]- d.- R-84-32-NPS (01/16/85), " Follow-up report of previously identified : s. 8 items" I-85-110-WBN, Concern IN-85-024-001, (07/11/85)

e.

4 f. -I-83-10-BLN (03/15/83), " Investigation of Employee Concerns - e Regarding Cable Termination Solenoid valves." (TTB-420-1) I-85-788-WBN, (12/18/85) g. l { 64 INP0 Report, " Document Control," (LO44 850816 803), (04/85) / .65. INPOReport,"DocumentControl,"(02/84) 66. INP0 Good Practices Report DE-101, " Configuration Management h-Preliminary," (03/86) INP0 Good Practices Report MA-304, " Control of Vendor Manuals," (09/84) - 67. {

68.. - TVA Report " Recurring Findings, Recommendations, and Good Practices from INP0 Operating Plant Evaluations,"-(05/84) 69.

INP0 Report, " Evaluation of Watts Bar Nuclear Plant, Construction Project," (Final Draft 06/85), -(TTB 1, 03/13/86)

70. 'INP0 Good' Practice 85-013, TS-402, Plant Modification Control Program

-(05/85) g' 7.1. INP0 Report, " Evaluation of Browns Ferry Nuclear Plant," (01/86) 3 N 72. INP0 Report " Evaluation of Browns Ferry Nuclear Plant," Second Draft,

r

.(02/12/87) INP0 Report, " Evaluation of Browns Ferry Nuclear Plant," (02/13/87) 73. INP0 Report " Evaluation of Bellefonte Nuclear Plant," (03/84) 74.

75. TVA BLN "Self-Initiated Evaluation Of INPO Performance Objectives, d

. Summary Report," R3, (02/06/84) 38000-R4 (10/15/87) 6

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page C-7 of 27- ] i I b

76. NRC Inspection Reports 50-327/86-11 and 328/86-11, (L44 860429 173)

-(04/22/86) 77. NRC Policy ' Issue, SECY-86-334 (11/12/86) 78. SON' Administrative Instruction AI-23, R21. " Vendor Manual Control," l e .(11/20/85) 4 ~ 79. SQN Administrative Instruction AI-19, Part IV, R16, " Plant Modifications - L AfterLicensing,"(05/08/86) P 80. SQN Area Plan 1707.03.04, " Vendor Manual Program," (12/21/84) TVA WBN Site Director Policy SDP-1, R2, " Change Control Board," (01/26/87) 81. l L

82. WBN-QCI-1.09, " Disposition-of Engineering Changes," R9, (10/03/86) l N

Division of Nuclear Engineering, Office Instruction DNE-01-3003, Appendix { P 83. D, Overview and General Instructions for Use of the DNE CAQ Data Base, ~ y l (07/01/85)- 84.. TVA Standard DNES-9.01, " Quality. Requirements for Design Documents Furnished by Vendors," R0, (09/08/86) h-D 85. Site Director's Standard Practices: SDSP-2.2 Controlled Documents, R4, (12/17/86) C f SDSP-2.4 ' Source Document Implementation, R3,.(12/23/86) ~ i PreventiveMaintenanceProgram,R0,(02/04/87) l [ SDSP>6.2 SDSP-8.1 Plant Modification / Design Change Approval, R2, (01/07/87) SDSP-8.2 Implementation of Plant Modifications, R4, (01/07/87) SDSP-9.1 Processing Drawing Discrepancies, R2, (09/22/86) TTB 312 e5 SDSP-9.2 Configuration Control Drawings, R1, (05/09/86) TTB-312 4. A SDSP-12.1 Restart Test Program (01/29/87) i h SDSP-12.2 Development of System Test Specifications (02/03/87) 5. j SDSP-15.1 Employee Safety Concern Program (02/03/87) Q SDSP-15.2 Handling of Engineering Reports (ER) from the Office of Engineering (12/23/86) l l l 38000-R4 (10/15/87) E, 3

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page C-8 of 27 i SDSP-15.4 Responses to Regulatory, Inspection, and Auditing Agencies (12/23/86) q SDSP-15.5 Employee Concern Handling Program (01/06/86) SDSP-15.6 Commitment / Action Item Tracking (10/15/86) SDSP-15.7 Periodic Final Safety Analysis Report (FSAR) Updating (09/09/86) SDSP-17.1 Primary Containment Leak Rate Test Requirements (11/25/86) SDSP-17.2 Postmodification Program Test (11/25/86) Fl SDSP-28.1 Plant Performance Monitoring (10/22/85) bi 3 BF-8.3 Plant Modification, R8, (12/23/86) n

86. TVA Standard Practice BF-2.5, " Drawing Control," R0, (03/14/86) 87.

Bellefonte Nuclear Plant -Standard Practices: y o BLA 5.9, R19 Dated 03/06/87, Drawing control Before receipt of an M operating license. o BLA 12.1,.R6, Dated 05/18/87, Initiation of requests for h Modifications. t o BLA 12.2, R19, Dated 11/19/86, Performance of Modifications before i h Licensing. o GLA 16.5, R1, Dated 5/28/86, Methods to t eport Drawing / Equipment i E Discrepancies. 88. BLA 5.2, R9 Vendor Manual Control," (04/24/86) BLN-SDP-1.5.1, R0 " Document Control," (03/30/87) ]" 89. TVA SQN GCTF Investigation Report, " Design Drawings Not Constructible; g Design Criteria Non Existent," R1, (06/01/86) 90. TVA SQN GCTF Investigation Report, "G-Specs Are Inadequate and n Incomplete,"R1,(06/06/86) 91. Gilbert / Commonwealth, Inc., Report No. 2614, " Final Report Technical ~ Review of Sequoyah Nuclear Plant Modification for TVA," (03/03/86) f 92. Theodore Barry & Associates Report, " Review of OEDC Implementation Progress,"(03/81)(TTB250-1)

93. Theodore Barry & Associates Report, " Management Performance Review of l

0EDC,"(12/78)(TTB241-7) 38000-R4 (10/15/87) i 1

,[ TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400~ l SPECIAL' PROGRAM REVISION NUMBER: 2 l Page C-9.of 27 94. Sargent & Lundy Report, " Browns Ferry Nuclear Plant, Nuclear Plant Electrical Calculation Program Assessment," (2 volumes), (07/02/86) 1 (

Reference:

TTB'215) [B43 860710 001] h 95. TVA Employee Concern Special Program Element Evaluation _80501-SQN, ~"EngineeringDocumentQuality,".R4,'(01/07/87) 9 6. : TVA QA Corrective Action. Evaluation SQ-CAR-86-01-004,- (01/04/86) 97. TVA Employee Concerns Special Program Report 71000, R3, Management and Personnel," Productivity,"-(01/30/87); Sections 1.1, 1.3, 4.1,:and 4.3 i

l s

98. Sequoyah Corrective Action Evaluation No.'SQ CAR 86 04021, (04/16/86).

I 19 9.. ER-WBN-EEB-001, R2, (03/15/87), - Instrument and Instrument Line-Installation and Inspection .100. TVA Significant Condition Report SCR GENERI 8602, [B04.860620 006], g (06/20/86) 101. TVA element report 307.04 - SQN, R4, "Workplan Process," (12/19/86)' [. 102. Browns Ferry Design and Analysis Report, Units 1 and 2 (07/13/66) and [ . Unit 3 (07/17/67) 1 103. TVA Employee Concerns Special Program Watts Bar Nuclear Plant, W-Subcategory Report 71700, R3, '?Personne1' Qualifications," (02/19/87) 3 104. Myer Bender (Querytech Associates) and TVA Team Report, " Assessment of c s Engineering Design Control for the Browns Ferry Nuclear Plant," (09/85) 105. BFN 0EDC - QPM-3-73, R1 '106. TVA Corporate Commitment Tracking System (CCTS) k 107. TVA' Division of Engineering Design (EN DES), Engineering Procedures Manual. This evaluation refers to the following: Volume 1, Section 1.0, Category: General j ' Volume 2, Section 3.0, Category: Engineering Volume 3, Section 4.0, Category: Design Volume 4, Section 5.0, Category: Procurement i TVA, EN DES, Engineering Procedures (EP) reviewed were: i h EP 1.14, R10 " Engineering Records - Retention and Storage," [ (05/13/83) EP 1.28, R7 " Control of Documents Affecting Quality," (07/23/84) 38000-R4 (10/15/87) s \\

TVA EMPLOYEE CONCERNS / REPORT. NUMBER: -20400: SPECIAL PROGRAM REVISION NUMBER:n 2 O' > y j.PageC-10of27Q'. $] ce .xv y ,/[ l EP 3.01, R5 " Design Criteria' Documents - Preparation, Revie fand Approval," ' (12/13/82) i;y EP 3.03, R8 1" Design Calculations,"-(04/24/84) !h L EP 3.04, R13' "EN' DES Construction Specifications.- Preparation, i g ' Review, and Approval," (02/14/84) EP 3.10, R7 '" Design: Verification Methods and Performance of t Design, Verifications," (04/25/86)' EP 3.38, R0 " System Description-Documents - Preparation, Review l and Approval'" '(02/16/83) l 3 'EP 3.57, R0 " Design Evaluation," (01/26/84) s EP'4.01, R10 . "S i gnature/ In i t i al s,." f(04/25/85 ) EP 4.02, R16 " Engineering > Change Notice," (07/23/84) [ EP 4.03, R11 '" Field Cnange Requests," (11/21/84) -J EP 4.04, R9 "Squadcheck Process," (04/24/84) ( (!y s-EP 4.07, R1. "As-Constructed Drawings," (08/08/79) EP 4.ll, R1 . " Combined - Design Drawings anfProject StanMa Drawings - Preparation 'and Use," ;(07/7,1/78)- j ).,. EP 4.14, R3 "EN DES Typical Drawings.and St5nderd,Drtaings - f Preparation, Review, Approval, Distribution and-a ) Revision" (08/10/81) EP 4.15, R2 " Project Layout Orawings," (06/09/81) i EP 4.18, R4 " Design Chagge Requests," (05/22/84) [ EP 4.21,-R3 "Revisbn and Voiding EN DES Engineering Drawings,"- g' 1 .(10/18/83) 1' l EP 4.22, R0. " Preliminary Design Changes / Requests (PDCRs) - Handling," (04/13/83) 'L EP 4.25, R8. " Revising:VendorDrawings,Q,04/24/84) "Interf ace. Coordination," .(12/14/81) n} EP 4.35, R1 t EP 4.39, R3' " Routine Distributing 6f Prints'and Microfilm [ Aperture Cards for' Drawings Under TVA Centrol," '(10/18/83) EP 4.52, R1 " Engineering (Change Noticeh, (ECNs) after LicensiNh - ) Handling,"(04/24/84) i EP 5.01, R17 " Purchasing / Transfer Requisitions," (05/23/85) 3 t EP 5.07, R5 " Contract Engineering for Civil Items," (10/13/8'! d EP 5.11,-Rll " Vendor Drawings," (04/24/84) EP 5.14, R4. " Vendor Documents f Handling and Disposition," (03/28/85) e EP 5.15, R4 " Interface Control, NSSS," (04/06/81) l EP 5.20,'R7 "ProcessingProcurementRequests,"(11/05/84) EP 5.26, R6 " Quality Requirements for-Design Documents Furnished byVendors"-(06/09/81)w l EP 5.30, R6 " Standard dormat for the Preparation of Procurement-Specifications," (07/29/83) EP 5.33, R8 " Procurement Quality Assurance " (10/26/84) n / v + 1 l i 3800D-R4 (10/15/87) \\ / i

j o. ig^ t / TVAblPLOVEECONCERNS REPORT NUMBER: 20400 .,! / jSPECIAL PROGRAM -REVISION NUMBER: 2 .Page C-11 of 27 y r p.----- 7 k 108. TVA Office of Engineering (0E) Procedures Manual: ' N l 0EP-06, R0 " Design Input" (04/26/85) y ^ OEP-07, R0 " Calculations" (04/26/85) c OEP-08, R0 " Design Output," (04/26/85) g OEP-09, R0 " Procurement," (04/26/85) 4 fqj OEP-10, R0 " Review," (04/26/85) N 'y 4 OEP-11, R0 " Change Control," (04/26/85) o L!" 0EP-13, R0 " Testing" (04/26/85) OEP-15,. RO. " Interface Control," (04/26/85) 7I OEP-17, R2 L " Corrective Action" (08/30/85) OEP-18, R0 ' " Review" (07/01/86) ~ 109. TVA Division.of, Nuclear Engineering (DNE) Procedures Manual: NEP-1.2, R1 " Calculation.," (01/19/87) NEP-1.3, R0 ' "Re<:ords Control," (07/01/86) 4 NEP-3.1, R0 " Calculations," (07/01/86) NEP-3.2., R0 " Design Input," (07/01/86) .y J NEP-3' 3, R0 " Internal Interf ace Control," (07/01/86) / NEP-4.1, R0, " Procurement," (07/01/86) r 4 NEP-M1.,R0, " Design Output," (07/01/86) a NEP-5.2, RO, " Review," (07/01/86) NEP-5.3, R0 " External Interface Control," (07/01/86) 2 NEP-5.5, RO,

• Engineering Requirements Specifications," (12/31/36)'

i NEP-6.1, R0, " Change Control," (07/01/EG) ) NEP-6.2, RO,; " Design Change Noticec" (02/27/87) NEP-9.1, RG; "CorrectiveAction,"f07/01/86) NEP-9.1, R1, " Corrective Action," (02/20/87) g' NEP-10.3, RO " Testing," (07/01/86) 1-110. Sequoyah Engineering Procedures (SQEPs) Manual j 111. Procedure for DNE Interface with Change Control Board (CCB) SQEP-15, (08/01/86) y 112. Sequoyah Engineering Procedure SQEP-39, Revision 0, " Review and Approval of Vendor Manuals / Revisions," (01/03/87) 113. SQN Plant Procedure SQM2, R19, " Maintenance Management System," (02/27/86) 3 ^ 114. SQN Plant Procedure SQM57, R4, " Preventative Maintenance Program," h. (01/03/86) n 115. Division of EngineeringiDesign, Division-Level Engineering Procedures y Index, EN DES EP Manual Index, Volume 1, Sections 1 through 6,(02/04/85) 4: l l '. s J. } l 3800%R4 (10/15/87) 's

~ r-9 7,, t .f 'y b i < f: 20400 REPORT NUMBER: _ l f .f TVAEMPLOYEEC0htERNS/ REVISION NUMBER: 2 SPECIAL PROGRAM Page C-12 of 27 i. 4 'f l'_ t 014001, "Contrac7/01/85) 116. TVA Off'ce of Engineering Mocedre OEration - Handling bDP),BLN-SDP-3.1.1,R0," Corrective js Adminisf / ) f f 117. $61efonte Site Director Procedur.t. Action for Conditions i 118.iBW)efopte Engineering Procedures (CLEPs) Manua t. 1 88), (05/21/87), 119. EN ' DES SAD Data Base sort on h; ' fyr BLN (Project g l (TTr;-396) (04/26/85) 120. TVA office of Engineering (OE) Organization fpanull, e,i, l Pl ant, 17'. General, Design Criteria No. SQN-DC-V-26.2,' Sequoph N r f q S) " Environmental Qualification to 10CFR50.49," (07/15/& l ) (multiple f 122. Watts Bar Nuclear Plant Design Criter Ic. Manual (5 'vo ume 02/12;86) ' l revisions), (latest issue, [B22 861104 301], 123. BFE[86-18, " Design Criteria /Desig6 Nasis," RO, r (10/27/86) Report No. 6957R, 12d Veddor Calculation, Morrison - Knudsep Company, Inc., ,e j\\ ' R1, (B44 860425 710), (03/31/86) i.),P' equoyah Unit 1 and 2, 125. DNE Calcu!ation, " Diesel Generathe Load And m c f3 (742Bf0827(09),(08/27/86) / j'asfollows: g/ 126. TVA 'deneral Construction' Specifications (G-Specs y n t A,. the Construction of f " General Instrddtions Applying to Major TVA Projects," R0, (02/15/801 2 G-l y. y, # ed Coric, rete," RS, (11/01/85) Pr if ,,f"NainaqdRenorc S-2, Q, 't ) G I;,, } "Formwork for Concrete," O, (02/08/76 o, h ++,, " Rolled Earthfill for Dams and Power Plants," RS, t f g :5., Q11/16/79) i ( a " Masonry,"R1,(GA?b)84) g ~ G-21, or Surf aces," R1, (04/23/79) 4; j " Finishing Concrete'F , M2, " Quality Control for C(construction [ /68) t / G-L7, .j< q p 'V } !i,[t l l< ) i /( I t / 3800D-R4 (10/15/87) ( i 30 .5 < i, ~~%_ ~ s

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page C-13 of 27 " Construction of Piping Systems for Boiling Water Reactor 'G-28, Nuclear Power Plants," R7, (12/30/82) " Fly Ash for Use as an Admixture in Concrete," R1, G-30, -(09/18/80) " Quality Levels of Structural Materials," R0, (08/09/83) G-36, " Installing Insulated Cables Rated Up to 15,000 Volts," G-38, R7, (01/15/86) " Cleaning During Fabrication of Fluid Handling G-39, Components," R9, (09/05/85) " Installing Electrical Conduit Systems and Conduit Boxes," G-40, R9, (01/15/86) " Support and Installation of Piping Systems in Category I G-43, Structures," R8, (08/08/85) " Installation and Initial Operation of EHV Transformers, G-46, Large Power Transformers, and Shunt Reactors," R0, (02/12/75) ~~- i " Installing Electrical Grounding Systems," R1, (07/09/84) G-47, " Torque and Limit Switch Settings for Motor-Operated ) G-50, Valves," R2, (03/14/84) " Grouting)and Dry-Packing of Base Plants and J J G-51, (11/01/85 j " Mechanical (Cadweld) Splices in Reinforcing Bars of i G-52, Category I Concrete Structures," R1, (10/31/79) \\ "ASME Section III and Non-ASME Section III (Including AISC, ANSI /ASME B31.1, and ANSI B31.5) Bolting Material," ^ G-53, RS, (10/10/85) " Surf ace Preparation, Application, and Inspection of G-55, Special Protective Coatings for Nuclear Plants,".. J (08/10/84) " Installation of Condenser Tubes," R0, (01/11/79) G-59, Bellefonte and Future, " Field Routing of Instrument Impulse Lines, Sample Lines, and Control Air Lines," R1, l G-60, (ECB 850211503), (02/14/85) j 38000-R4 (10/15/87) .._.. y.x;e,

TVA EMPLOYEE CONCERNS-REPORT NUMBER: 20400? i SPECIAL PROGRAM REVISION NUMBER: 2 1 Page C-14 of 27-G-64, " Installation of Buried Piping - Civil. Aspects," (R0 in l J work) G-69, " Quality Assurance Requirements for Construction of Radioactive Waste Management Systems," R1, (10/18/84) ll G-73,. " Inspection, Testing, and Documentation Requirements for Fire Protection Systems and Features," R0, (03/16/82) -G-80, " Limited Quality Assurance Requirements for Security Systems," R1 (08/12/83) 127.- Division of Engineering Design, General Construction Specification Index, (12/18/85) 128. TVA General Construction Specification G-27, " Quality Control for Construction of Piping). Systems for Boiling Water Reactor Nuclear Po Pl ants," R0, (12/12/68 1; 129. TVA Gene'ral Construction Specification G-1, " General Requirements Applying to All General Specifications for the Construction of Dams and Reservoirs," (02/63)' b 130. BFN instrument drawings: )' 47W600-21, R8 47W600-25, R9 l 47W600-22, R7 47W600-26, R8 47W600-23 R17 47W600-27, R2 47W600-24, R2 47W600-29, R13 131. EN DES Conditions Adverse to Quality (CAQ), (02/17/87), Key Word Search .i 3 Reports for (TTB-396-2): I ) o ' Des Crit' o 'Dwg' 3 4 o ' Schematic' l o ' Diag' i l o 'As Const' l o ' Spec' j o 'FCR' o ' Accept Crit' o ' Draw' ~ 3 o ' Weld' o 'G Spec' l y o 'ECN' 132. OE Conditions Adverse to Quality (CAQ) Data Base Frequency Report 1D, (02/13/87) 38000-R4 (10/15/87) v

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL-PROGRAM-REVISION NUMBER: 2 Page C-15 of 27 133. "0E Conditions Adverse to Quality (CAQ) Data Base Frequency Report j Browns Ferry - By Identifiers," (04/02/87) 134. TVA BFN Conditions Adverse to Quality (CAQ) Reports. The f ollowing CAQ_ Reports were reviewed and are referenced as applicable: CEB.79-35 re Residual Heat Removal System Not Properly Designed, [CEB791130 016], (11/29/79) CEB 8501 re Cable Tray Supports Calcs Failed to Consider Effects of Additional Load on Floor Support Beams, [B41851211015], (07/29/85) i CEB 8511 re RHR Pipe Suoport Inf ormation Inadequate, [B41850905 027], 1 (09/05/85) 3-CEB 8512 re Core Spray Cooling System Pipe Supports Do Not Meet Movement Requirements, [B41850905 021], (07/29/85) CEB 8516 re Piping Supports - Dead Weight Loads, [B41851029 002], [ (10/18/85) s CEB 8520 re Pipe Supports Not Seismically Qualified, [B41851112 016], C l (11/06/85) k OES8601 re HPCI Supports Were Not Subject to Preservice Examination, l [B22 861030 007], (09/02/86) CEB 8608 re Pipe Support incorrectly Designed, [B41860423 018], f (02/10/86) CEB 8610 re Pipe Supports Shear Stresses Not Checked or Documented, i )f [B41860218 008], (02/10/86) k CEB 8619 re RBCCW Pipe Support Calculations Not Checked, [B41860408 006], (03/31/86) g CEB 8630 re Core Spray Pipe Support Misalignment, [B41860916 002], w Si (08/28/86) RC-259/79032 re RHR System Hanger Nonfunctional Oue to Misapplication, [No RIMS No.], (12/11/79) R0-59/80010 re HPCI Pumo Room Instrument Line Hangers Broken, S [L52 800219 905], (02/27/80) N R0-59/85026 re Cable Tray Supports Not Seismically Qualified, [R42 850730 881], (07/30/85) i i j ) 38000-R4 (10/15/87) i

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page C-16 of 27 R0-59/86007 re Control f or Drive Pipe Supports Not Seismically Qualified, [R42 860321 898], (03/21/86) l 1 R0-96/85017 re Residual Heat Removal Hanger Broken, [R42 850813 901], ) (08/09/85) ] 1 t R0-96/85020 re Core Spray System Pipe Support Not. Installed, [R42 850821931), (08/20/85) R0-96/86007 re RHR Pi.pe Hanger - Fatigue Failure, [R42860725 866], (07/25/86) R0-96/86009 re RHR Pipe Hanger - Fatigue Failure, [R42 861007 955], j (10/07/86) l 1 ~ 135. TVA Audit No. 00D-A-84-0005, " Program Management - Quality Assurance Program and Organization," f or audit conducted 04/09-27/84, l e l [0QA 840524 507] l 4 136. Audit File QMS85-33, Sequoyah Engineering Project May 14-16, 1985 l 137. Audit File 86-24, Sequoyah Engineering Project (SQEP) Civil' Design Project' (CDP), Alternate Analysis Review Program, August 5-8 and 27-29, h 1986 e 138. Audit File 86-27, Nonconf ormance Conditions Disposition, Documentation, th and Control, Watts Bar Engineering Project, September 15-19, 1986 139. Audit File 87-02, Corrective Action and Control of Modifications,- Sequoyah Engineering Project (SQEP) I 140. Audit File 85-23, " Safety Analysis Section of NEB," (04/23/85) j N 141. Audit File 85-27, Electrical Design Activities, (Bellef onte Engineering i Project (BLEP), (05/06/85) j E l 142. Audit File 85-02, Design and Procurement Activities, Bellef onte l ~ A Engineering Project (BLEP), (10/28/85) l v ( 143. Engineering Audit report EAUD-SS-81-8#1, Design Calculation, I [0QA 830624 510), (12/16/81) i d 144. QMS Audit / Surveillance Status Log (1986 Audits), (08/22/86) (TTB 244, l g 02/12/87) l i u 145. TVA QA Vendor Audit Report No. 77V-12, of the Presray Corporation, Pawling, NY, June 14-16, 1977, Contract 76K73-820648, " Seals Between Ice Condenser and Containment Vessel for Reactor Building," (07/22/77) M t i 38000-R4 (10/15/87)

i TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page C-17 of 27 4 1 146. TVA QA Vendor Audit Report No. DED 74V-14, of EDS Nuclear, Incorporated, l San Francisco, Calif ornia, September 30, October 1,1974, Seauoyah and j 1 Watts Bar Nuclear Plants - Contract TV-40899A, (10/25/74) 147. TVA QA Vendor Audit Report 77V-20, of L. I. Metal, Incorporated, Glen j Cove, New York, April 18-21, 1977, Sequoyah Nuclear Plant, "Honeyccmb Cushions f or Pipe Rupture Protection," Contracts 76K71-86996 and 76K72-820345,(06/07/77) 148. TVA QA Vendor Audit Report No. 77V-18, of Johnston Pumps, Glendora, Calif ornia, September 20-22,1977, -Sequoyah Nuclear Plant - Contract l 76K35-820227, "ERCW Screen Wash Pumping Units," (12/01/77) 149. TVA QA Vendor Audit Report No. 87V-26 of Crane-Aloyco, Inc. Romeoville, Illinois, October 21-23, 1986, Contracts 86 PNQ-838934, 83273 -585827, and 86 PCB-371305, (11/12/86), (TTB 382, 05/12/87) 150. TVA QA Vendor Audit Report No. 79V-17 of Penn Ventilator Co., Inc., Philadelphia, Pennsylvania, May 23 June 6-7,1979, Contract 78K83-823993,(Material: Roof Ventilator Fans)=, (TTB 382,05/12/87) l 151. TVA QA Vendor Audit Report No. 85V-119 of Ellis and Watts Co., Cincinnati, Ohio, June 11-13, 1985, Contracts: 84K31-835998, j 85K33-835957, (Material: Ventilators and Dampers), (TTB 382,05/12/87) 152. Contract No. TV-40899A, "TVA Contract f or Personal Services," with EDS g' Nuclear, Inc., San Francisco, Calif ornia, (08/01/74) P 153. Procurement Contract Package, Reference No. 82K62-830892, "High-Crud Cleanup Filters for Sequoyah and Watts Bar Nuclear Plants," vendor calculation, Requisitioner Ref. No. N2M-981/N3M-741, Contract Date: 09/02/82, Perf ormance Date: 06/02/83, squadcheck sheet 3 ME 81 11627-11630, 62-830892/SQN and WBN 154. Procurement Contract 85K36-835400-N4M-920 Letter IMP 005, Cover Letter t s IMPELL to TVA, Souadcheck sheet 85-05936, 835400/BLN IMPELL calculation review of 517-002C, R0, "Backflush Receiving Tank - Code Calculations, [MEB 850226 202], (no date) 155. Procurement Contract 83K36-835400-N4M-920 Letter IMP 042, 8 Cover Letter from IMPELL to TVA squadcheck sheet 85-04037/38, 835400/BLN IMPELL calculation review of 517-006C, R1, " Flow Orifice Plate Sizing he Calculation," [B44 850625 631], (06/18/85) 156. Contract No. TV-40899A, "TVA Contract f or Personal Services," with EDS Nuclear, Inc., San Francisco, Calif ornia, (08/01/74) p 3800D-R4 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 I SPECTAL PROGRAM REVISION NUMBER: 2 Page C-18 of 27 157. Contract No. 839192, " Watts Bar Nuclear Plant Engineering Services f or Thrust Calculations as Reauired by IE Bulletin 85-03," Requisitioner Ref. No. N3M-1495, (09/23/86) with Crane-Aloyco, Inc. Romeoville, Illinois, (TTB 382, 05/12/87) 158. Procurement Contract Package, Contract Reference No. 76K 35-83190, " Air Cooling Units," (Contract date: 09/30/75), includes: TVA Specification 2571, " Safety Feature Equipment Coolers f or Auxiliary Building Watts Bar Nuclear Plant," (No date), (requires calculations) l 159. Procurement Contract Package, Contract Reference No. 77K 35-83246-2, " Fans and Roof Ventilators," (Contract date: 07/20/76), (TTB 394, 05/20/87) includes: TVA specification 2757, " Fans and Roof Ventilators for Reactor, Auxiliary, and Turbine Buildings Watts Bar Nuclear Plant Units 1 and 2," i (no date), (requires calculations) 0 160. Procurement Contract Package, TVA Purchase Contract Reference No. 67C53-91815, " Structural Steel f or Office and Service Buildings," a (Contract'Date: 06/19/67), includes: l Specification 9323, " Structural Steel for Office and Service Buildings at Browns Ferry Nuclear Plant Units 1 and 2" (no date) 161. Procurement Contract Package TVA Reference No. 67C2-91457, "500-KV Power Circuit Breakers," (Contract Date: 05/03/67), References a TVA Standard Specification 54.075 dated 10/25/65 (specification was not included in 3, y package received). i W 162. Procurement Contract Package, TVA Purchase Contract Reference No. 80p82-826628-2, " Fittings Pipe f or Reactor Water Cleanup System," q (Contract Date: 11/05/79, Performance Date: 11/26/79) - No TVA specification addressed. -( ASME Section III material.) Specifications a3 are in the f orm of attachments. / 163. Procurement Contract Package, Contract 66C31-90744, " Equipment Packages f or a One-or Two-Unit Nuclear Plant f or the Browns Ferry Site Near Athens, Alabama," (06/17/66)", includes: $i Specification 9065, " Major Equipment Packages f or 1-or 2-Unit TVA B Nuclear Plant" (no date) E1N 164. Procurement Contract Package, TVA Purchase Contract Reference No. 67C17-91550, " Control Equipment," (12/27/66) (No procurement specification number is addressed) v ,.m 38000-R4 (10/15/87) ~

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 i Page C-19 of 27 1 165. Procurement Contract Package, TVA Purchase Contract Reference No. 67C54-91517, " Galvanized Chain Link Fence," (12/21/66) (No procurement f specification number is addressed) i k 166. Procurement-Contract Package, TVA Purchase Requisition number 85116, ." Orifice Plates for Containment Atmosphere Dilution System for Browns Ferry Nuclear Plant Units 1-3 ECN M-120 and M-408," (08/20/73) - (includes bore calculations data transmittal, 12/19/74 from Vickery-Simms, Inc. to TVA) n 167. Calculation for TVA Ord'er Number 75C34-85916, Dieterich Standard Corp., g " Flow Calculation Report," Invoice Number 28845, Date of Calculation = o 11/27/74, calculation numbers 10059 and 10060. 9 ] 168. Letter from TVA to TTI Engineering, "Sequoyah and Watts Bar Nuclear f Plants High Crud Cleanup Filters, Contract 82 K62-830892-N2M-981 and i N3M-741," vendor calculation, (MEB 830512 201, (05/12/83), squadcheck sheet ME 81 11627-11630, 830892/SQN and WBN. q 169. Procurement Contract, TVA Purchase Contract Ref.erence Nos. 68C3-91111-1 and -2, "Radiat' ion Monitoring Equirment," (Contract date: 06/14/68), includes: 3 j TVA Specification 9576, " Radiation Monitoring Equipment Browns Ferry Nuclear Plant," (No date) 170. Procurement Contract, TVA Purchase Contract Reference Nos. 68C58-91088-1, -2, and -3, " Heater Drain, Condensate, and Reactor Feedwater Pump Recirculation Valves," (Contract date: 06/14/68), includes: j TVA Specification 9536, " Heater Drain, Condensate, and Reactor Feedwater Pump Recirculation Valves for Browns Ferry Nuclear Plant Units 1-3," (No i date) I 171. Procurement Contract, TVA Purchase Contract Reference No. 69C34-91121, ) " Control Rod Drive Hydraulic Systems," (Contract date: 08/07/68), includes: TVA Specification 9586, " Control Rod Drive H Ferry Nuclear Units 1, 2, and 3," (No date) ydraulic Systems for Browns 172. Procurement Contract, TVA Purchase Contract Reference No. 68C30-91124, "High Pressure Coolant Injection (HPCI) Steam Venturi Flow Nozzles," (Contract date: 06/26/68), includes: TVA Specification 9591, "High Pressure Coolant Injection (HPCI) Steam Venturi Flow Nozzles Browns Ferry Nt.nlear Plant Units 1-3," (No date) 38000-R4 (10/15/87)

x' 1 TVA EMPLOYEE CONCERNS REPORT NUMBER: '20400 SPECIAL PROGRAM REVISION NUMBER: Page C-20 of 27 173. Procurement Contract, TVA Purchase Contract Reference Nos. 69C30-91142-1 and -2, " Horizontal Centrifugal Pumps," (Contract date: 08/12/68), ~ includes: TVA Specification 9624, " Electric-motor-driven, Horizontal, Centrifugal Pumping-Units f or Raw Cool ng Water Booster Service and Fuel. Pool. Cooling i and Cleanup at Browns Ferry Nuclear Plant Units 1,: 2, and 3," (No.date),

174.. Procurement Contract, TVA Purchase Contract Reference No. 69C37-91143,

" Heat Exchangers," (Contract date: 08/14/68), includes: TVA Specification'9625, " Fuel Pool Cooling Water Heat Exchangers ;f or Browns Ferry Nuclear Plant Units 1, 2,- and 3," (No date) 175. Procurement Contract, TVA Purchase Contract Reference No. 69C58-91145, "Drywell Penetration," (Contract date: 10/18/68), includes: ) TVA Specification 9641, "Drywell Penetrations for Browns Ferry Nuclear 3 Plant Units 1-3," (No date) (Calculations are required) 4-176. Procurement Contract,'TVA Purchase Contract Reference Nos. 69C54-91151-1, i -2, -3, -4, -5, -6, -7, and -8, " Fittings, Pipe, and Accessories," (Contract date: 09/17/68) (No specification document) 7, 9-177. Procurement Contract, TVA Purchase Contract Reference No. 69C3-91181, " Sequential Events Recording Systems," (Contract date: 11/20/68), includes: TVA Specification 9710, " Sequential Events Recording Systems for Unit b' Control Rooms at Browns Ferry Nuclear Plant Units'l-3," (no date) o: 178. Procurement Contract, TVA Purchase Contract Reference Nos. 69C54-91187-1, } -2, -3, -4, -5, -6, and -7, " Valves, Pipe, Fittings, and Accessories," (Contract date: 01/09/69), (No TVA specification document) 179. Procurement Contract, TVA Purchase Contract Reference Nos. 69C56-92227-1, -2, -3,'-4, -5, -6, and -7, " Valves, Fittings, Pipe, and Accessories," Ri (Initial contract date: 06/17/69), (No TVA specification document) l 180. Procurement Contract, TVA Purchase Contract Reference Nos. 70C55-92241-1, -2, -3, -4, -5, -6, and -7, " Valves, Fittings, Pipe, and accessories," 44 (Initial contract date: 07/23/69), (No TVA specification document) g. Ai 181. Procurement Contract, TVA Purchase Contract Reference Nos. 70C55-92242-1, i -2, -3, -4, and -5, " Fittings, Pipe, and Accessories," (Initial contract A date: 07/25/69), (No TVA specification document) 9; [- I 38000'-R4 (10/15/87) ~ .w h-___.._____

TVA EMPLOYEE CONCERNS SPECIAL PROGRAM REPORT NUMBER: 20400 I c REVISION NUMBER: 2 Page C-21 of 27 { { 182. Procurement Contract, TVA Purchase Contract Reference No "High-Efficiency Filter Cells for Regenerative'and Nonregenera Exchanger Drain Vents and Cleanup Water, Equipment, and '.' v( eat Vents," (Contract date: 09/23/69), includes: ump TVA Specification 9858, "High-Efficiency Filter Cells for Rege and Nonregenerative Heat Exchanger Drain Vents and Cleanup W n ve Equipment, and Floor Drain Sump Vents for Reactor Building Nuclear Plant," (No date) , Browns Ferry - o 183.' Procurement Contract, TVA Purchase Contract Reference Nos -2, and -3, "Special Control and Isolation Valves and Accessories ". 70C6 (Initial contract date: 10/27/69), includes: Ferry Nuclear Plant Units 1-3," (No date), (De g or Browns calculations are required) W 184. Procurement Contract, TVA Purchase Contract Reference Nos -4 and -2, " Emergency Cooling Equipment," (Initial. contract date: . 70C35-92302-1 includes: 04/14/70), TVA Specification 9954, " Emergency Cooling Equipment for Co g i Shutdown Board Rooms Air-conditioning Systems Browns Ferry 9 ay and Plant," (No date) h-185. Procurement Contract, TVA Purchase Contra i TVA specification document) 05/29/71),(No 186. Procurement Contract, TVA Purchase Contract Reference No " Seismic Instrumentation," (Contract date: . 72C61-74882, 07/12/71), includes: Plant Units 1, 2, and 3," (No date)TVA Specification 1343, " Seismic Instrumentat uclear 187. Procurement Contract, TVA Purchase Contract Reference No " Isolation Valves for Drywell Leak Detection System," (Contract . 72C61-74943, 07/30/71), includes: TVA Specification 1354 System for Browns Ferry, Nuclear Plant Units 1, 2, and i k 188. Procurement Contract, TVA Purchase Contract Reference Nos -2, -3, -4, -5, -6, - 7, -8, -9, -10, -11, -12, -13, -14, -15, -16, -17, . 72C55-75035-1, and -18, " Valves, Fittings, Pipe, and Accessories," (Initial contract date: 10/01/71), (No TVA specification) 38000-R4 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page C-22 of 27 189. Procurement Contract, TVA Purchase Contract Reference No. 72C53-75446, " Energy Absorbing Protection Panels," (Contract date: 03/29/72), (No TVA specification) 190. Procurement Contract, TVA Purchase Contract Reference No. 72C3-75453, " Pressure Controls (Electronic) for Secondary Containment for Browns Ferry Nuclear Plants Units 1-3," (Contract date" 01/27/72), (No TVA specification) 191. Procurement Contract, TVA Purchase Contract Reference No. 72C8-75452, " Differential Pressure Controls," (Contract date: 01/25/72), (No TVA specification) 192. Procurement Contract, TVA Purchase Contract Reference No. 73C61-84256, " Diesel Engine-Driven Emergency Generator Power Packages," (Contract date: 01/11/73), includes: 1 TVA Specification 1737, " Diesel Engine-Driven Emergency Generator Sets for Browns Ferry Nuclear Plant Unit 3," (No date), (Calculations to be submitted) ) i 193. Procurement Contract, TVA Purchase Contract Reference No. 73C38-84305, " Pumps, Vertical, Turbine-Type," (Contract date: 12/13/72), (No TVA l specification) ) 194. Specification 2883, " Seals Between Ice Condenser and. Containment Vessel for Reactor Buildings at Sequoyah Nuclear Plant Units 1 and 2" (Reference TVA Contract No. 76K73-820648 with the Presray Corporation, Pawling, New York) i-195. Specification 2506, " Honeycomb Cushions for Pipe Rupture Protection at Sequoyah Nuclear Plant Units 1 and 2" (Reference to TVA Contract [- 76K71-86996 with L. I. Metal, Incorporated, Glen Cove, New York) 196. Specification 2653, " Vertical, Turbine-Type Pumping Units Essential Raw I Cooling Water Screen Wash Pumping System Sequoyah Nuclear Plant Units 1 and 2" (Reference TVA Contract 76K35-820227 with the Johnston Pump 1 Company, Glendora, California) 197. Vender Print, BLN Project File N4M-122, Contract 77K35-920122, Weir Pumps LTD, Cathcart Works, Glasgow G44 4EX, Scotland, " Works Performance Test j Certificate ErCW (Bellefonte Nuclear Plant)," R1, (03/19/79), (TTB 404, l 06/02/87) { l a I 198. Vendor Print, TVA Bellef onte Unit 1 and 2, Contract No. 77K53-820732, ITT Grinnell Pipe Hanger Division, Drawing Sketch 2KC-MPHG-0322, Sheets 1 and i 2, R2, (10/21/85), (TTB 360-1, 04/29/87) i 38000-R4 (10/15/87)

I ~ TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 1 SPECIAL PROGRAM . REVISION NUMBER: -2 1 Page C-23'of'27-199. Vendor Print, 'TVA Bellefonte' Unit 1 and 2, Contract No. '77K53-82-732, ITT Grine11 Pipe Hanger Division, Drawing. Sketch No. 2CF-MPHG-0239, Sheets 1 and 22, R4,. (11/17/82),- (TTB-395-4, 05/21/87) 200,- Vendor Print, TVA Bellefonte Unit 1 and 2, Contract No. 77K53-820732, ITT l Grine11 Pipe Hanger Division, Drawing Sketch No.1KC-MPHG-0036, Sheets 1, . 2, and 3, R3, (06/10/81), (TTB 402-12, 05/29/87) ] 201. Vendor Print N4M-2-69, (08/18/77), TVA Project: Bellefonte 1 and 2, ' Contract No. 71C62-54114-2,." Nuclear Steam Supply Sys.," Babcock and 1 . Wilcox, Nuclear Power Generation Division, Technical Document, Equipment. l Specificati on 62-1001170-0 for, " Fuel Handling Equipment Tests, TS 4400," ] (05/31/77), (TTB-396-3, 05/22/87) i -202. Vendor Print N4M-2-20, (08/10/79), TVA Project: Bellefonte 1 and 2,. Contract no. 71C62-54114-2, " Nuclear Steam Supply Sys.," Babcock and. 7 g Wilcox, Nuclear Power Generation Division, Technical Document, Equipment 9 Specification 08-1153000001-10 for, " Instrument And Control Panels," R10, -(05/01/79), ;(TTB-400-4, 05/28/87) ' 203. TVA Piping Bill of Material drawing for BFN units 1 and 3, " Main Steam 3 k Piping," 47W400 series,. 67 M 4 47BM400, Sheets 1 through 6 R0, (05/27/68) Sheet 7, RI, (02/16/73) i Sheet 8 R3, (08/29/69) f-Sheets 9 and 10, R0, (05/27/68) f TVA Piping Bill of Material drawing for BFN units 1 and 3, " Main Steam Piping," 47W400 Series, 67 M 4 47BM400-1, l g ~ Sheets 2 through 5, R0, (12/24/68) TVA Piping Bill of Material drawing for BFN units 1 and 3, " Reactor Water . Cleanup System," 47W406 Series, 67 M 4 47BM406, 4 Sheet 7 R1, R1, (04/30/69) %i TVA Piping Bill of Material drawing for BFN units 1, 2, and 3, "RHR . Service Water Piping," 47W450 Series, 67 M 4 47BM450, Sheet 1, R0, (09/22/71) j [ TVA Piping Bill of Material drawing for BFN units 1, 2, and 3, "RHR 'j g Service Water Piping," 47W450 Series, 67 M 4 47BM450-1, Sheets 1 and 2, R0, (10/13/70) 4 l 38000-R4 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page C-24 of 27 TVA Piping Bill of Material drawing f or BFN units 1 and 3, " Residual Heat i Removal System," 47W452 Series, 67 M 4 47BM452-5, { Sheet 1 R2, R2, (08/15/68) Sheet 3 R1, R1, (10/16/69) TVA Piping Bill of Material drawing.f or BFN units 1, 2, and 3, " Residual Heat Removal System," 47W452 Series, 67 M 4 47BM452-7, Sheet 12, R0, (05/14/69) TVA Piping Bill. of Material drawing for BFN units 1 and 3, " Core Spray 1 System," 47W458 Series, 67 M 4 47BM458-2, .] ?- ~ Sheets 1 R1, R1, and 2 R1, R1, (09/22/69) P l TVA Piping Bill of Material drawing for BFN units 1 and 3, " Core Spray System," 47W458 Series, 67 M 4 47BM458-3, Sheets 3 R2, and 4 R2, R2, (10/15/69)- Sheets 5 R3, and 6 R3, R3, (07/07/70) Sheet 7 R3, R3,.(02/05/70) ?- h TVA Piping Bill of Material drawing for BFN units 1, 2, and 3," Core Spray System," 47W458 Series, 67 M 4 478M458-4, Sheets 1, 2, 3, 4, 5 R1, 6, and 7, R0, (05/13/69) TVA Piping Bill of Material drawing f or 8FN units 1, 2, and 3, " Core j N Spray System Valves," 47W458 Series, 67 M 4 47BM458-6, a l Sheets 1 through 4, RO, (10/15/69) h Sheet 5 R2, R2, (03/11/70) 3 Sheet 6 R2, R2, (02/12/70) Sheets 7, 8, and 9, R0, (10/15/69) jy 204. Letter from Dircks, NRC, to C. Dean TVA, SALP Board Reports, .u [B45 850919 826], (09/17/85) 7 205. Letter from R. C. Lewis, NRC, to H. G. Parris, TVA, SALP Board Reports, c [NE8 840614 612], (06/12/84) u.i2 - 206. Letter from R. C. Lewis, NRC, to H. G. Parris, TVA, SALP Board Reports, N [A02 830415 001], (04/13/83) 207. Letter from R. C. Lewis, NRC, to H. G. Parris, TVA, SALP Board Reports, W3 [A02 820823 010], (08/20/82) >3 38000-R4 (10/15/87)

s

~

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page C-25 of 27 208. Letter f rom R. C. Lewis, NRC, to H. G. Parris, TVA, " Report Nos. 50-327/81-33 and 50-328/81-42" re: IE Bulletin 79-14 closure f or Unit 2, [A02 811019 014], (10/14/81) 209. Letter fra J. B. Youngblood, NRC, to S. A. White, TVA, with the attached transcript of the investigative interview conducted by the NRC on 02/21/86 at the First Tennessee Bank Building in Knoxville, TN, [B45 860714 832] (06/23/86) 210. Letter from G. Zech, NRC, to S. A, White, TVA, " Notice of Violation L (Inspection Report Nos. 50-327/86-62 and 50-328/86-62), (03/04/87) A02 870309 006 E 211. Letter fra R. Gridley, TVA, to B. Youngblood, NRC, " Additional Inf ormation on Sequoyah Design Baseline and Verification Program," [L44 861211801],(12/11/86) 0* 212. Letter from R. Gridley, TVA, to B. Youngblood, NRC, " Draft Safety i Evaluation Report - Design Baseline and Verification Program," [L44 870227 805], (02/27/87) 9 213. TVA memo from L. L. Jackson to Those Listed, " Institute of Nuclear Power 3 Operations (INPO) Corporate Evaluation Responses," [A02 860813 012] F (08/14/86). Relevant findings include 1.1A-2 and 2.5A-7. l 214. TVA memo from L. L. Jackson to Those Listed (H. L. Abercrombie et al.) " Institute of Nuclear Power Operations (INP0) Corporate Evaluation Responses" (08/14/86) [No RIMS No.] (

Reference:

TTB 107/ SQN-533) (Supersedes memo with RIMS No. A02 860422 022) E 215. TVA memo from E. Gray Beasley to F. W. Chandler,

Subject:

Audit Deviation Report No. 051-A-84-0006-D011, " Inadequate Systems to Ensure !) Calculations Are Updated to Support Design Changes Made after Plant Operations," [B05 850402 004], (04/02/85) 's 216. TVA memo from E. Gray Beasley to R. W. Cantrell, " Quality Management Staff Assessment of Problems Associated with Discipline Staffing," [B05 850402 005], (04/02/85) 217. TVA memo fra E. Gray Beasley to G. L. Dilworth, " Quality Management Staff Assessment of Problems Associated with Discipline Staffing," [B05 850417 003], (04/17/85) 3 3 218. TVA memo from E. G. Beasley to J. R. Lyons, " Office of Engineering (OE) Quality Management Staff (QMS) Audit 85 Technical and Administrative Staff (TAS)," [B05 850521003], (05/21/85) 219. TVA memo fra E. G. Beasley to F. W. Chandler, " Office of Engineering (0E) Quality Management Staff (QMS) Audit 85 Electrical Design Project (BLEP)," [805 850506 001], (05/06/85) 38000-R4 (10/15/87)

TVA EMPLOYEE CONCERNS REPORT NUMBER: 20400 SPECIAL PROGRAM REVISION NUMBER: 2 Page C-26 of 27 220. TVA memo frm W. C. Drotleff, Director of Nuclear Engineering, to S. A. White, Manager of Nuclear Power, " Design Change Process Improvement Program," (801 860801001], (08/01/86) ] l' 221. TVA memo frm J. R. Parrish to Those Listed " Browns Ferry Nuclear Plant - ) Quality Assurance Program," (06/20/72) located in BFN OEDC-QPM-No. 3-73, i R1 l 222. TVA memo from J. S. Colley to QAB Files,

Subject:

Situation Study - System Engineers in ~EN DES-Report No.1, [QAS 810729004], (03/02/81) i 223. TVA memo from J. A. Raulston to Those Listed,

Subject:

Sequoyah and Watts Bar Nuclear Plants - EN DES System Responsibility, j [ NEB 810807 286], (08/07/81) 224. TVA memo from J. A. Raulston to M. N. Sprouse,

Subject:

All Nuclear l Plants-SystemDescriptions,[ NEB 810110 266], (01/19/81) 225. TVA memo from J. A. Raulston to J. A. Kirkebo, " Design Calculations," (B45 860619 252), (06/19/86) I 256. TVA memo from J. A. Raulston to E. G. Beasley, "Bellef onte Engineering Project (BLEP) Nuclear Design Project - Quality Management Staff (QMS) Audit 85-23," [B45 850528 254], (05/28/85) [ 227. TVA memo from R. W. Cantrell to Those Listed,

Subject:

Sequoyah and Watts Bar Design Projects - System Design Responsibility, [SWP 811016 083], (10/16/81) 228. TVA memo from C. K. Buck to CEB files, "WBN Design Review of Unit-2 Pipe Support Calculations," (B41850919 005), (09/19/85) 229. TVA memo from R. Hernandez to T. Cruise, "WBN Design Review of Unit-2 Pipe Support Calculations," (10/30/85) 230. TVA memo from D. W. Wilson to J. A. Raulston, "Bellef onte Nuclear Plant - Supplement to the ' Technical Evaluation of the Bellefonte Decay Heat Removal System Design Criteria,'" (NEB 840510 256), (05/10/84) 231. TVA memo from T. R. Brown to WBN Plant Files, "WBN - Piping Analysis and Hanger Design Meeting," [C24 850327 600], (03/26/85) l l 232. TVA memo from W. R. Brown to H. G. Parris, "Bellefonte Nuclear Plant - i Need f or Independent Design Review," [EDC 840730 701], (07/30/84) 233. TVA memo from WBN Hanger FCR Review Team to D. B. Bowen and R. A. Pedde, "WBN - Field Change Request Study," [C02 850319101], (03/19/85) l 1 l 38000-R4 (10/15/87)

~ - ~ - 20400 REPORT NUMBER: TVA EMPLOYEE CONCERNSREVISION NUMBER: 2 SPECIAL PROGRAM Page C-27 of 27 i W tts Bar Engineering f; 234. TVA memo from H. B. Bounds, to J. F. Wein dit Response, l. [B26 870129 011), (01/29/87) Barnett, et al), " Policy ll 235. TVA memo from R. C. Weir to Those Listed (R f Engineering Memorandum - NEB 87-001 - Independent Verification o.95-12,0 Calculations," [B45 870303 253], (03/03/87), (TTB-3 "WBN - Employee Concern 23f.. TVA memo f rom R. W. Cantrell to W. H. Thom /11/86) 28/1987 237. Bechtel/TVA meeting notes, IOM 691, dated 01/26-l 238. Bechtel/TVA Telecon IOM 941 dated 02/12/87 239. Bechtel/TVA Telecon IOM 942 dated 02/23/87 10M-1232,(06/15/87) 240. Telecon, J. Williams, Bechtel, to E. Cole, TVA, TVA, 10M-1261, 241. Telecon, J. Williams, Bechtel, to C. Christopher, 10M-1262,(06/17/87) (06/17/87) l 1 242. Telecon, H. Simpson, TVA, to J. Williams, Bech_ te,IOM-A 243. Telecon, J. Williams, Bechtel, to F. Smith, TV, k s d 4 Es y l, ~.Q 38000-R4 (10/15/87) ~ _ ~ _. _ _ _ _ _

!l.

- U 1: 0 8 7 0 4 2 9 VUT ~ ' 'f, P.. : Bechiel Western Power Corporation l Engneers - Constructors 'I C Fifty Beale Street 'J San Francisco, California' Mail Address: PO Box 3961 Sa$ Frarcsco, CA 94119 April 27,- 1987 BLT-197- _Hr: George R. H K ' Engineering CEG-H' Tennessee Valley Authority-j Knoxville, Tennessee 37902 Watts Bar Nuclear Plant

Subject:

' Employee Concerns Evaluation Program - Tennessee Valley Authority Job No. 16985-026 l ~- ' TRIP REPORT _ f

Dear Mr. McNutt:

~ Attached.for.your information and use are the following docume s Sequoyah Element 224.5: g Trip report for walkdowns' conducted on April 15th and 16th o 1. . a id w..,. in control room and cable spreading room. k-l -Copy of Bechtel Calculation 224.5(B)-1, R0 p g..,.v. 3 f8@,/;[.f~2. $ _ Ap do The attached calculation confirms the conclusion in the (- This conclusion is w. all of the cables'in question are' adequately supported. based on a Bechtel review of applicable TVA dr j W i $9 above. The attached calculation has been prepared in response to an N L item resulting from meetings held on March 16th and 17th (se k transmitted by letter BLT-161). 4. 7' unless you decide it is necessary. Very truly yours, ,a 4.. hf G. L. Parkinson Project Manager f,.. GLP/gd Attachments 4/29/87---GRM:RMW RIMS, MR 4N 72A-C cc: N. A. Linkonis, W9 B85 C-K 20510 W. R. Brown, ECTG Bldg., Watts Bar ONP ' ij,. i 12614Je/es) -,- -m,mnr.; g 3,g y

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^ I' TVA EMPLOYEE CONCERNS PROGRAM - JOB 16985-026: - SEQUOY AH NUCLEAR PLANT,-TENNESSEE' CIVIL GROUP, APRIL 15 and 16 TRIP REPORT- .j ELEENT. REPORT 224.5(B) SUPPORT OF CABLES 1 1 A. INTRODUCTION The purpose oflthis. trip was to obtain additionalLinformation regarding how f cables for the main Control Room' panels are supported in the area of the floo'r ~ This' additional information will be used to. prepare an-penetrations. ~ l additional Bechtel ~ calculation -to supplement Element: Report.224.5(B). 'Particularl attention was given to the Electrically Control-Boards (ECBs) and - j] These two panel' types have steel-box structures, Main. Control Boards (MCBs). referred to as walkway,.below them. TVA drawings reviewed previously by Bechtel.do not clearly show: locations and sizes of floor penetrations.in the w-walkways. R. -Roberts -(Bechtel - SFAO) and S. Mabie (Bechtel - BFN) performed walkdowns of thel Control' Room (floor elevation 732 feet) on 04/15/87 and of the Cable [ ~ Spreading Room (below the ' Control Room) on 04/16/87. TV A DNE -(SQN) personne who' participated in the walkdown were H. Liao-(on 04/15/87) and'C. Henderson-1 t-(bot 1 days). ! B. CONTROL. ROOM WALK 00WN j -1. ECB. Walkway. A h . All' eight panels were walked down. 'Each panel.has four cable- ' penetrations in the sides of the walkway. " Cable entering the:. ~j a walkway through these penetrations is routed in-cable gutters inside i f the walkway.'. Cables are tied with plastic "ty-raps" to the cable l ith Drawing' [ t gutters. The' layout of the cable gutter agrees.w 45N816-5. H ~ k 2. MCB Walkways ' All 12 panels (6 per unit) were walked down, pictures were taken of l i the floor penetrations, and sketches were prepared showing floor penetration-locations. There are.14 floor penetrations.in the unit Each of the' d s 1 walkway and 13 penetrations in the unit 2 walkway. Cables floor penetrations has 'a cable gutter inside the walkway.

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are' tied to the cable gutters. The layout of the cable gutters j agrees with Drawing 45N816-6. Two unit-1 floor penetrations have a For each few cables each that are not routed in the cable gutter. [: of these conditions, the cable is tied to cross members inside the l >-d panel. M i Recording Instrument Boards, LL Distribution Boards, Etc. 3. d There are 10 panels north of the ECBs and 12 panels south of the None of these panels have walkways. Cables penetrate the W. ECBs. floor slab through square (9" x 9") or rectangular (5" x 9") openings or through embedded conduit. The layout and sizes of the 1 h 1991D-5 ) 4. L. - --u_. _ - _ _ _ _ _,, _ _

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SEQUOY AH'. NUCLEAR' PLANT; TENNESSEE: _

~ CIVIL GROUP, - APRIL' 15 and 116 TRIP REPORT. 1 ELEMENT REPORTt224.5(B).,5UPPORT 0F CABLES 2 1 floor. penetrations agree with Drawing 48N1295 and-Drawing 48.N1296,. Detail A. ; A11 22.. panels were ' walked down. Cable bundles'for these-panels have a small nuser of cables (varying from two-or three: ~,, ~ . cables for the smallest bundles' to approximately;12 to:15 cables for ~ J the' largest: bundles) compared to cable bundles for other panels.. Cables' are' generally routed vertically in cable riser ' enclosures, . between the floor penetrations and the' term nations. As stated in-g i ~ Section C.3, cables'for Panel 0-M-28B were tied to the panel, cabinet in order to prevent significant cable loads on the terminations.: Cable; ties were observed on many oflthelother panels as'well. As 4 .further ' stated' in Section C.3, cables for1 Panelz 0-M-28A were : Lobserved to have considerable slack after they. exit the cable' riser H enclosure, therefore precluding any.significant load on the-tenninations. This slack in the cables after exiting the cable riser enclosures was observed for. all panels. Floor penetrations are filled with silicone foam. The walkdown' team

l tried pushing and probing.on the surface of the foam to determine ~if-

-l there,are items embedded in the foam for supporting the cables.... These investigations were inconclusive due to' the resistance of the. [ foam. \\ Panels at. " Slot" Openings ' {. _c 4. There 'are four rows of panels- (total of 29 panels) above 1 ?-9"-wide-h slot openings in the floor. <These. slots' are detailed on Drawing: 48N1296-1,1 Details. A, B,' C, and C1.1 According to this drawing.. tube ' ' steel:(TS) 2x2 cross meters, spanning the sides of the slot. are L provided at each floor penetration:except.for:three penetrations for-1 Panel 0-M-12.. 'The walkdown ~ team observed that TS 2x2 cross menbers, l/ spanning the base members of^ the panel, are provided for these three i . penetrations. ' According to a TVA calculation and eyewitness j b statements from construction personnel who worked in the Control j g Room during the installation of the cables, the cables were tied to l p the TS 2x2 members to support the weight'of the. cables. -l ( Approximately 140 TS 2x2 menbers (including those shown on Drawing 48N1296-1 plus the additional three observed during the walkdown) I are provided for support of cables for the four rows of panels. The walkdown team observed that these TS 2x2 members are either partially or totally enbedded in silicone foam, depending on how the h. t 6 3, penetration sleeve was fabricated. Fifteen of the 29 panels were I walked down. The remaining 14 panels were not walked down.because L-the doors were locked. However, it was not considered necessary to walk down these 14 panels because the TS 2X2 cable support menbers {' are shown on the design drawing. 3 Y". 9 D 4 h 1991D-5 7 g C lii L_ u__ __ j_

+ 4 y..y w 7 >g, ~J08 :16985-026 ; .y . - TVA EMPLOYEE ' CONCERNS' PROGRAM. l SEQUOY AH' NUCLEAR PLANT,. TENNESSEE' l . CIVIL GROUP, APRIL 15 and 16 TRIP REPORT : -] ELEMENT REPORT 224.5(B)' SUPPORT 0F CABLES-

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-CABLE SPREADING ROOM'WALKDOWN q d L l1.- ECB. Walkway j I ' Walkdown of the-ECB walkway was not considered necessary because the - if ' walkdown of the' Control Room-showed.that there are.no floor: ! penetrations. The cables entering the ECB walkway through openings W in the! sides of the walkway 'are adequately supportedLby cable gutter. a 1 L 2. c MCB : Walkways i Nineteen of p~ The walkdown. team'took. pictures of floor penetrations. l the'27 floor-penetrations do not have cable gutters:below the As_ stated in. Section B.2, ~all 27 floor penetrations have ~ walkway. cable' gutters Linside' the walkway. 'The layout..of the cable gutters h ky agrees with Drawing 45N816-6. Recording, Instrument Boards, DC Distribution Boards, Etc.; 1 ^ 3. l

According to Drawing 45N816-51and as observed during_ the walkdown, 8 of the 10 panels north of the ECBs have' cable. gutters approximately-F

'i For the remaining 2 panels,!1-M-30 'and ' 5 ~2 feet below thelfloor. b 1-M-31, the walkdown' revealed that the cable bundles have been ~ The-cables for Panel 1-M-30f are adequately supported in. i F supported. .m cable gutter which also is used for adjacent Panel' RIB 9. For Panel j i '.1-M-31,: the cable bundle' is tied to a cable gutter support: angle i J approximately 3' feet from the underside of the floor penetration.- j .l 4-Eight of the 12 panels south of the ECBs have cable gutters. b.> approximately 2 feet below the floor. The layout.of the cable i 'l The 4' panels that do not have gutters agrees'with Drawing 45N816-5. cable gutters are' 2-M 4 .Therefore, these 1-M-30 and 2-M-31, the' cable is routed in conduit. cables are not unsupported.. For Panel 0-M-28A,.the cable bundle, consisting of approximately 15 cables, is approximately 1-1/2 inches in diameter with a vertical unsupported length of approximately All of the cables in the cable. bundle are non-class IE. 18 feet. For Panel 0-M-288, unsupported vertical cable bundles consist of R approximately 6 class IE cables, approximately 1-inch in diameter, g with a vertical unsupported length of approximately 11 feet; plus g approximately 3 non-class IE cables approximately 3/4-inch in diameter, with a vertical unsupported length of'18 feet. a" Reinspection of this panel in the Control Room revealed that the 1 4 cables have been tied to the panel cabinet in order to prevent ,r For Panel 0-M-28A, l significant cable loads on the terminations. l support of the cables inside the panel could not be verified by the l walkdown team because the cables are enclosed within a cable r However, since it was observed that there is l ) enclosure.

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a s 7 l JOB 16985-026. TVA EMPLOYEE CONCERNS PROGRAM SEQUOYAH NUCLEAR PLANT, TENNESSEE CIVIL GROUP,' APRIL 15 and 16 TRIP REPORT ELEMENT REPORT 224.5(B) SUPPORT OF CABLES considerable slack in the cables after they exist the cable _ riser enclosure, one can conclude that there is no significant load on'the terminations. . To ' verify th'e support of ve'rtical cable bundles for Panels 0-M-28A . and 0-M-288, the walkdown team ' pulled on the cable bundles directly i ^ below the floor penetrations in the Cable Spreading Room. The i estimated pull force was 10 to 15 pounds. There was no slip of the cable bundles due to these pull forces. The approximate weights of g the cable bundles are 30 pounds for Panel 0-M-28A and 20 pounds for y Panel 0-M-28B. Therefore, a pull force of 10 to 15 pounds would simulate a seismic inertia, force of 0.33g to 0.75g. A review of the SQN seismic response spectra shows an SSE peak vertical acceleration r of approximately 0.309 for 5% damping. The.refore, the pull forces g applied to the two cable bundles adequately simulated the seismic g-inertia forces. A 5% damping value is typical _ for structural 9 systems during an. SSE. For the_ two cable bundles in question, damping greater than 5% is expected since the cable bundles are 1 considerably more flexible than typical concrete and steel h-structural systems. Dynamic tests by 1VA of larger cable bundles established a minimum damping value of 21% damping for the '~ p'- horizontal ~ direction for SQN conditions.. Based on an assumed damping.value of 15%, the SSE peak vertical acceleration is 0.20g.. 5 Therefore, the pull forces applied to the two cable bundles varied p from a minimum of 1.67 to a maximum of_3.75 times the seismic L inertia' force. l '4. Panels of Slot Openings [5~ Since the cable supports are located above the floor, detailed 7 walkdowns of these panels were not considered necessary. b D. S110%RY Cable penetrations for Control Room panels were walked down. On the basis of b the following observations, the cable support > methods are considered to be acceptable for all panels: 1. ECB and MCB Walkways f Cables are adequately supported by cable gutters. f 2. Recording Instrument Boards, DC Distribution Boards, Etc. r Cables for 20 of the 22 panels are adequately supported by cable l L gutters, conduits, or ty-raps to cable gutter support. For Panels l L 0-M-28A and 0-M-288, the adequacy of the cable supports was verified I 1 l 1991 D-4 - _ _ ____ -_

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JOB 16985-026; TVA ElPLOYEE. CONCERNS PROGRAM ~i SEQUOYAH NUCLEAR PLANT,' TENNESSEE CIVIL GROUP, APRIL 15.and.16 TRIP REPORT ELEMENT REPORT 224.5(B) SUPPORT OF CABLES . by observation of the' ty-raps - (ties) for Panel 0-M-28B and by_ l pulling on the cable bundles for.both panels,. .1 m ' 3. - Panels.at Slot Openings TS 2x2 members have been. provided to -support lthe cables as is shown 7 on the design drawing and as was observed during the walkdown. p. l l 1 Nb ' P,repared-by _m %~ 2 7-8 7 u w a r* !t .m 'a m. G Y k

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( l l v: P~ l f ' /, 1991D-4, l h

CALCULATION COVER SHEET!. ... g PRoner _ TVA SEQuoVAH sce no. /G 925 - 0 2 G sSeseune Civ/L D SUPPOR T o f CA S L ES IN THE C ONTR OL Suener e,ue no. Room FLOOR PENETR A TIONS cruc. no. 2 2 A S ('0] ' I No, oF SHEETS 1 + A TTA CHMEN TS l-3 ( RECORD OF ISSUES ,lDATE lAPPRD lDATE l h*, No. DESCRIPTION BY DATE CHKD ?! A T&"n%!%fMNTa% /k6 4e/e, cWWa:ll.K % %Ve, z^s A y 3 A 4 R EFEREN C ES : SEE PP. 17 $ 18 m A TTA CHMEN TS : k I. EY E WITNESS STA TEMENT4 ( G SH TS.) p 2. SEISM /C RESPONSE CURVES ( 3 SH T3.) 3. TEST REPO AT PAMPING VA LUE'S '( + SHTS.) 0 ? E 5 ] " Utilization of these calculations by persons without 1 access to pertinent factors, and without proper regard for their purpose could lead to erroneous conclusions. Bechtel cannot assune responsibility for the use of these calculations not under its direct control". SFP.20220 RE V 7/8 3 .E O.1 R E V 5 ( 7 /B

0$10111.741 ' CALCULATION SHEET '~ o,1, 2,27 17 A. Ao beris 4 - 2 3-8 7_ cycyo,, M 1 I o,3,cy,, o 1, suerso. TVA Seqaoyah 1698s ,,noac, so, no.. - o 2 c, Supocet c/ Ca bles meusr,ouno. 2 24. M6)-I \\ su,aer na uo. l ~ w TABLE O F CONTENTS S SUBJECT SHEET ' N O S, i I, 1 N TR otu G T( O AJ 2-5 A, STATE M ENT O F-Pu&PoiE 2 9' 'Pa. S o u.R C E S OF /N F-O R. M A TI O M 2 v. c. SU M M A RY OF D ELA to /N G S 2-4 5 ~' D. AREAS OF Em PH ASIS FOR WALK 90WNS 446 l p I[.- EV A L U ATI O N o F C A Pa L E SU PPoRT - m E THSV5 5-/6 { A. TYPE l. P L 0 0 R. PEN ETR ATION S 6 f b. Ty PE 2. F lo o R. P EN ETR. A Tl oN 3 7-9 i C. TNPE 3 Fl_0oR PGNETR ATloNJ /O - /6 IEE, con e tu sioM /6 .Lv.. RE PE RENC ES /7g/6 I, DR A WlNG AN D.s k ETc H ES /7-26 A. COPY OF DR AW/NG 47W 606 - 1 /7f20 B. PL AN O F 'mC S WALK W ANS 2/ $ 22 c. F16u RES 1-4 23-2G ZI. ATTAc H m ENTS I-3

7._____ . 0$t0111741 - u CALCULATION SHEET - 4 Q 8/ oaTE A o beI +b DM'+/bb/[7CHECKEDBY NeI/Q 2 ] DESIGN BY SHEET NO. /6985-TVA 5 $0U0l0 h JOB NO. ~ 0 2 [e PCOJECT C4 b!bJ ~ !' FILE NO. 5MO[OI O !suaJECT CALCULATION NO. l 1 I.~ IN TR ODU C T/ 6Al ) A. 3TA TEinENT 0 F PUP P OSE The purpose of +his calcu./nhon is fo prowde a. l descripkon and an evaluahun of Jaffort mefbodJ ased inr es bles a)hi'ch penefrale the Conhol Rooin floor sixb at e /. 7 6 2'- 0." Thi3 ck/cu./ah'on \\ supplem en ts SQ A/ E~/ement Re ( Re f. l.) In addressing the em, cort 2 24.5 (S.) ployee concern. l l 8. Sou R c E3 0F IA/FORInA TION i TVA drawinfS, et/ca./ahunJ, and other docamenf5 I. 2. D13tu S3 fon 3 taffh TVA personne/ l a. Field welkdown condaeled by Bechfc/ and Tvn l on 4/15/87 and 4//6/87 V' C. SurnM A-R Y 0F DRAW /MGS l The letyout of panels in the Conhv/ Room 13 shown 1 Drawing 47W606 - / ( Re f. 2. a ). A copy of. on this drawing 13 included in thi3 ca /ca.!a hon on \\ ) pp. l9 $ 20. {. Shuclural defails of the floor peneira h'ons, /ncluding h lota bbn, site, and h britabbn deki/3 are.rhown on Dra win s 48Ali2 94, 4BN/296., +8N/29G, and ^ 48 Al I 2 96 g/ ( Ref. 2. b - 2. e ). These drawings tha t ther e a re 3 \\ pene fra hvns ( see pp)g enerz/ shou > 19420 e iden h*Aralion floor of Hoo r pene fra bbn +yp es

I' ~\\s g CALCULATION SHEET: Ji c ' *z y 2 h7/$,7 on,E O I CATE 14 b b /'8 7 DESIGN BY / CHECKEDBY_- N i' SH EET NO. PROJECT 04 N 8 Vd-i- i aos so, .2 Support of Cs bles sue,Eer e,ueu,r,on no. 2 24. 5(B)- l ,,u,no_ w. i c. summany oF DR A w>^tG3, (con I'd. ) Type I

• 5+ eel box Ntructuresbelow the Noor l

(re{ erred h as 'ivs.ths.y ~) ha ve been j furnahed for flectn%': / Con bol Boseds ( Ecos, Pan eh Ech I-8 ) and main Con frol 8oards { noc 8 3, Pan e/V/~m-/ -th rough l-m-G hr unrt / and fane/s y 2-m-Y throngh 2-n)-G for unM 2 ). p ^ 4 Type 2 : Af the north and south ena3 of the Conb-o/ Room running east-wesf and y along the east side.of the con tro/ .{ Room running north'- south are f ro w.s g of control panels and a total *f 2 9 ~ Floor penetraMn3 consat of./L 9 " panels. wide g slots wi+h sfee/ floor p/ ales hwihy/e and rictangu,lar speningS fpr 2s 6 sgaare p ene frs huns - Typ e b : A t the horth and.touth ends of the f ECBs are. of i ( 8 Recordinf/nsframentl Boards 2 2 pane /\\ Pan els RT6 2-9), 8 DC DBtribubvn a boards ( Pane /S.DC 2 - 9.), a n d 6 L con trol 2-m-50, pan ch ( Pa nels /-m-50, /- M-6l., 2-in-S}, 0 m-28A, and 0-m-2SS)N ) Pinor p)enetrabvns are sguare (typres/G) 9 % 9' or ireefangu.lar- (-typita //y 5"* 9 openings.-

37 \\ osio n oce gj: .,J CALCULATION SHEET e oAre _M/27!87 QA YA h ??b A 20 h ? cHecnoer Ml - otstan eY OATE SHEET uo. ly 3 n ~ N 4oudh 74 g>g g YVb l 4 enoasci l ,t / . roe no. ~O26 4j,o o P o Ca !dd I SUBJECT O ~ CALCULATION NO. - FILE No. C. Sum m A RY OF 'ORmo/NSS ( c on i'd. ) '~ Elec trre a / ' Drawings 45N8/6-5 and 45N8/6-fo ( Ref. 2 f. $ 2 3)8sshow th e la.yout of ca b/e gu tters fo y Ec , In c 8.s, and o ther pa n els. i Drawing 3 48/Vq3 0, 48N73 /, and 48N78l- / / (R e f.s; 2.h - 2f') show shuefura'/ supporis for f \\ +h e ca ble gutters below +/r e f/ Gor. f; (' L, Drawing 45 4/880 - 2 6 (Ref, 2. k ) prnede.s A regatremenb for ins talla hbn'of fire sfop/reJ s af ff ca. ble pen e fra b' nJ. J Thi.T drawth g s /2 " thithness of Tsu) peci ~ y the ase of a Corning 3 -6 5+8 ' h silic on e RTV foair). i. h3 s r ,1 fo D. M'E D OF EMfMASIS PoA WA LKDou)NS Parircular aIFenhbn 13 given h the adegaacg+gp x, ine+ hods and identifred by floorpenetrawn a Type /. klalhdowns. were condaded sf cables enferh3 +he welkways through penetrahvns in the f/oors of the. walk ways. Walkdown of cables enfermy the waIkways +hrough pene fra fibn.s th the side.s af ffe %s/kways i.s nof regawed since these esbles are adeguale/'v supporka' />y ca b/e \\ guiters as.chomn on }he drawrhg.s (def. 2.f ond 23). a o Typ e 2. Panils "/-tr)-15, 0-m-12, 0-m-2 6, 0-m-2 7, a nd. 2-/H-ID "w Ar4 h are speciAca//y idenfrfrec/ in m e'n o frok th e concerned indivis'ua / fo et i inark 5kaVeinski, daled tapo/e s (Ref. 3). s _ _ _ _ _ _ _ - - _ _ - - _. _ -. - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ^ - - ~ - - ' ' ^ ~ - - - ^ ' ^ ' ~ - ~ ~ ' - ' ' ^ ^ ^ ^ ~ ' ~ ~ ~ ' ^ ~ ~ ~ ~ ~ ' ~ ~ ^ ~ ~ ~ ~ ~ ~ ~

g/ 'T G g. t Y )' '$,, Q o c \\ t -.c ( /_ esio in.ra ,x O f l,.' CALCULKlfCN SHEET ("'. 3 417,lP7 'f,, / om R0bdYh AIZYD Wbb 5 Oesson eY om o er smno. /Sgg5 i g. i a ,__ V A 5e quova h i 1 j s ,o,, o. - o 2 c, . enoJtcu. i oN' Cf 4hk8 CAtcu Atidtt uo. 2 2 4. W O - / ,,te no. sus 7A5, M D. \\ } lf_f EA S OF EinPH AS/.S { f (c on 'l 'd. ) h>) r v < H (3 assamed na+ the reference lo " Pane / '51 0- tr). 2 7 " wa s mean t to be Pane /3 0-m '27A i k and o-m- 2 78,.since th ere is no Pa n e'l 0 - 171 '2 7 ( see Re f.

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e s k Pa n els /4z-30 3 l-trl-31,, 2-m-3 c7, 2-m -3 /, 0-m-28A, ~ Typ e 3. h y and 0 m-R B 8 do no t ha ve ca ble ya-i+ers to y )~ su-pporf, th e ca bles which 4 as indrea kd on Y th e " dreivings C R e f. 2. f ). 4 / m s, [j in .n / ~ g ~,lT., E VA L U A TION A OF CA 8 L E SUPPOR T METHODS 5 A. TYPE I FL 00/C PGA/E ik A T/OAl.S k! /, EC& trial K w/IY a ga f; Dra wing +8lJ/295 (Ref. 2. c).shoiv3 fabrRahun

• dd fails of Oe walk wa.y.

Drawin.s 48N8/6-6 I ,i M s9 (Ref. 2. f),ahd 48N75 0 (Ref, 2. ) show ca ble ~ ' [ kMer.s and 'ga ble yuHer sap,ocris for penetrstron) ,i n % e sides 4f the wa./hway. il l Field withdoduns ( Ref. 4) ver&ed tha t a// 9 r ca bles eni5 he walkway roufed in ca ble 9aHees nroujh en c fra hans in the JideJ o f s % e wa lkwQ, a '!es a r e Red wNh " Ty - Rap ' to he ca.ble gutters inside & c wa /hway. There a r e n o ca. ble~ p en efra hurts in th e flo or of n e paIkway. m j ner&r[zye$b/c3 are adequale/y.<worfed.

~ O ono one ~ CALCULATION SHEET i o4TE M,b7!I7. 4/fh/87 Y DESIGN 9Y DATE' CHECKE0 8Y NN - SHEET NO.. / PROJECT-N O JOB NO. SU8' JECT U-[,M O I O! Cd b!N1 CALCULATION NO. W8 W5} ~ ! ' FILE NO. (f' W /). TVPY / FLOCA PE NE'TRA TIONS (con / 'd.) a 2, m Cb ' WA LkwA YS y Drawing 4BN /2 9 G lRef, 2.d) shows fu byrca bbn' de4 ails for %e walk, ways.. ( Dra x; /ngs 4 5 AJ8 i& -G (R.cf.2 3), 4 8 Al 73D ( Ref. 2. h ), and 4 ban 3 i f ? ft ef. 2. ( ) s h ow ca.ble pft ers and ca.ble 9 at-h r su. g. Yhes e drawing s,ppor +5. According 4o ca.b le pen ch a.htns a.re I pro veded en Sofh the. s(des and +he floor [ W the :wal kwe ys, For genetrabbns in ne sedes of the w4Ikways, r ca.ble ytters used +o rou.fe +h e ca.bles 4htoqh the eneira.+rons provrde a.d.egna.:fe; so-y por + for e ca.bles. I For cables enlering the wa/kwa.y through. \\ h penefrahvns in the Hoor, adegaaey af the. cable supporf mcfhods could nof be veri /Ved l based on a review of the drswkqs. Therefore, ) { keld walkdownJ (Ref. 4) were Ebndacfed. V She}ches showin sizes of Moor,g approximate locahuns and oene frakns were. prepared and are included on pp. 21 and 2 2. his/kdowns nere conducted in hoth the Confro/ Rootri and +he Cable Spreading floom (below th e con tro / Room ). Inside th e wa/kways., ca ble gu+ters are provided for a// 2 7 floor penetrafronJ. l .-....._....a__..._.__.m_..._....---h .__-.r-.-1

0510 (11-74) CALCULATION SHEET J .2/z7hr . o TE ,/B7 oEsicN BY O r DATE CHECKEDBY SHEET NO. Tt/A Seau ova h nosECT ,o, no. -oes ) ,O,D 0 r O a O SUBJECT CALCULATION NO. - FILE NO. 4 /4. TVPE I Floor PE'h/E TRA TION 3 ( con + 'd. ) 2 ^. mcb to A L)<l0 A YS ( c on i 'd. ) ca bles t'n side th e wa lk way s' a r e fy-rapp ed p h) the ca ble gu +ter. Penefra huns 5 and 0 7 (see p. 21 ) ea.ch ha ve one sma// bandle o f ca bles tha t h no t rou/ed in th e ce ble h g a ++e r. Ilowev er, these 2 cable bandles have k been fy-ra the panel.pped fo sfructural members insMe g ?. g Therefore, ca bles are. adeguately supporfed. k For Pen e tra kons 8, 9,15, IB, l9., 2 3, 24, an d 2 6 (see pp.El ( 22), addihunal supports to cs bles are provicted by es ble y a ffers b e/ow s ? +h e floor. Y Th e la ha'a + o f c a b le g u tters o bser ved darin c +h e fre walkdowns a \\ 45N 816-5 ( Ref. 2.().grees with Drawing 1 8. TVPE 2 Fl o0K PENG TR A TIONS \\ Drawing 4BN I2 9 5 (Ref. 2.c ) shows lhe locahun) [ a nd sites of the 4 slot openings in +he Hoor. l 5+cel Hoor pla.ks with openiH 3 for cable 4 E pen e tra hans are de+ ailed' on frawing 4BA//296-/ (Ref. 2.e) .pe fail 3 Q B, C, a n d C /. For each a f +1h es e,ca ble pene fra fions, a sh eef m ela / en closure for a c cordan ce wiM Drawing 45N880 - 2(of&e sfop silic (cain B p(ronded in Ref.2.h). a

osioo,.m l a CALCULATION SHEET oAre-427,b / R. RO'ber 5 oire 4/23/8 7 eseexeosy.' hpMm ' sseer no. LoesioNay PROJEer- ~ M OV d-JOB NO. ~O b' Support a f - Ca ble.S cruevar,ou no. 224. El6) - I ; nee no;

sussac, b..

TYPE ~2: FL O OK ' PENE TR A TI ON.S (Con /'d.') Dra wing 48N /'2 9G-/ (Ref. 2. e.), De} ails A, 8, d, and ci a n d sec h'on A - A :sh ow TS 2-2 . t875 m em berS spanning across th e si&J of the slo t ppening S a t en ch ca ble penefra hon e xcep f h r i, 13 - 8 "i 9 " pen etra hans s hown in De tail A for Pa n e l 0- n1-/2 '. Reid walkdowni teves/ed that 1 I T.S 2~2 mem ber.5 were (urnished for each of p +h es e 3 pene frabbns. However, these 5 T3 2"2 - mem bers are nof Jh0mn on Drawin 4 48 N/296-I 7 ~ since th ey are a H-ached +o th e p1n e / fram e a nd g noF +o th e sides of the slo t opening. I Th e TS 2x2 members were used +o supporf the

ca ble.s based on the fellowing :

/, TS 2 x 2 m em berS Serve n o o+h er S fruclu rd/ ' htne h>n. ca leulahbn

• Control old 2.

TVA Pla f hrms " ( Ref. 5, a ).,g. Frames, Carb.S V 4 pp. 31 and 40 show.s +h a f TS 2i2 m em ber.s were deJf4ned 40 sufporf the eGht and setsmic lod?f3 of a ca. ble ban dle { S. Written.sk femenis by 5 7vA eleeIn'ca./ l cons frac bbn per.sonnel wh a warked in the con trol Room and the Cabic spreading Room when cables uere bemg pulied, )leemina/ed, or in.specfed ( see A ffachmen t I As sMed., Ty-Raps were used 40 attach the cab /e.1 fo +F>e TS 2 x 2 supporf m em ber.s. L i I

.l 'I 0610 01 74i ; - CALCULATION SHEET o,,Al2,ln R 0 b0Y h DATE' Y h 0 $ 7 cuecntoerYl N Y sneer OEssoN et PAOJECT O jf18S t JOBNO.

• O 2 0_..i SUBJECT M doi

'O Cd / /. CALCULATION NO. ~! FILE NO. fj 8. ITY PE' 2 ~Fl.00R. PENETR A TICA/S ( c o n } 'd, ) Idalkdowns veriked de use of Ty-Raps 4. l, k r Suppor t 'o f ca bles in simila y a reas.

• t Therehre, esbleJ are adeguadely Apporfed.

er v No k : since ri O 2 m em bers a re embedded in silicon e ham a t th e ca ble L penetra bbns, waaa / o bservahun o f Ty-Raps a t th e e< ble penetrahuns is no t possible. The memo frorn the concerned thdividua/ (gef. 3) describes y hi>n to be.. "a member of a F/amem4Jhh a crew and la/cr as a hreman of one. " based on +he freld walkdowns (Ref. 4), Ty it 4 apparen f that-the F/smemdsht coa hny w' one f,oarn was app //ed as afo/ red h the cab /es afkr i ne sibc ca ble penefra bbn.s.

Therehre,

\\ s. mem her of a Nam erncht crew would i nof he able /o ob.rerve the exaknee I of Ty S 2 > 2 Rap.s for a ffachthy he ceb/e3 h I th e T member $ sihce +h ey wcre i embedded ib st/mone ham. Th a could \\ l be the reason why the concerned \\ t indtwdual expressed his co>teern. J i 1 8 l 1 i i

. 0$10 (11-74) CALCULATION SHEET !I'/ oATE !O 4,/S b /d 7. CHECKED BY SHEET NO. ' O OI DATE DESION BY JOB NO. $a00Va PROJECT Of Ca b/d8 CRCUuTION NO. au H b)* / Figo, No,ooe SUNECT C. TNPE .5 FlooK PEAIETR A TIONS Drawing 48N l2 9 5 ( Ref. 2. c) shows the loca%n and dektll hype for I2 penefra Hans nor+h a f the E C b s a nd I 2 pen e fra hun.5 south of the

ECbs, Drawing 48N (2 9 6 (Ref. 2.d ),

Dehtil 14 sh ows the site of floor openings are hpi'ca //y i 5 "x 9 " for p en e tra h uns a t th e e n ds o f d e row l o f p a n els a n d a re +yp re a lly 9 " x 9 " hr p/G - G enetrahans for he nWddle pan els. Drawing +5N8 a (R ef. 2. f ) s h ows ca ble ga ff eks a r e pro u Med -for g floo r pen e tra hans exc ep t fo r th e -ho o a // k 5 '/2 " n 9 " p en e tra bvn s a f th e n orth en d a f Pan els l-in-5 0 a nd I-/H-3 / a nd th e hvo 5" 1

• p en e fra hvns y

af-d e sou+h end af Pan eIs 0-/n-28A and 0-in-286, h Floor pene}rahnns and cable gutters for Panels 7 - m-5 0 a n d 2 -in-S I are n o t s h ow n on th e drawings. R* See R p.23 for a skelch showing pane l yure / onIs.yout, floor penetrahunS, and c X: W Fo r n e p a n els n orth of h e E C6 s,,h e held walkdowns (Ref. 4) yeriked +ha + cable yuHers W have been provMed a accordance with +%e drawiny. 8 For de floor penefrahnn at the north end af Panel I-in-50, i+ was observed tha t ca bles are

)

n; routed in th e ca ble g utte r for +h e a dj'acers f-and ( see Ryure /, p 2 3 floor penefrahun 4 Figa re 2, p. 2 4 , Sec kons A - A a n d B-6 ). For i Hie floor peneirah'on at the north end of Panel y7 I-In -31, it wss observed dat th c ca bles are O I,y-rapped 10p. 2 3 and Fiyare 2, p. 2 4,p f fh e cab /c gu We r.ru JecHons A-A a nc/ j c-c). Therefore, a// of the esbles for fhe panel.s Q nor+h of the EC83 a re a de7 aafe/y rupperkd, a 11

CALCULATION SHEET - cars 4 f t7ff 7 _ R

• R O 6 I'I /)

4h b /8 z CECEDBY. NNl&_ SMmo. '// /G 92S DATE -oFG '. DESIGN SY, __ T Y4 Oe440Vab' aos No. Lenoacct y.i FILE NO. _. 8 CgorE' o[ Od b/fd cAtcVLATION'NO. 8 $suesser s' C. 74PE 3 FL OOR PENE YR A TIONS ( con f 'd.) ne panels south of %e ECB3, the fre/d Fo r ven'ked that cable yufter.S wsIkdowns (Ref24) For ' Pan els .2-/ti-50 and 2 In-3 /, es bles are roukd'ha h e on dui+s beloat th e floo r w h reh pen e fra fe t e. floor direeHy below 1he' ' panels. Therefore, Mese in ca bles are properly supporied.* For Me flooyPanels 0 penefra hbns a f the south end op' ' be/ ween and :o-m-288, th e ca bles are 'not suppor/edRoorn and ne cable } ray in yhe cable SpreadatfR ure I, p. 23 I an d ( see [ +he floo r pen eira bbn3 e-in-28 8, th e For Pan e [ Ryure 3, p. 2 5 ). be fy-rapped h the panel ca bleJ were observed }o Panel 0-in-28 A could ty-raps for ne a ca bine f. Strnila e not' be o bserved because +he cables inside rouled inside' a meht/ enclosure. i panel are {g order k deferenine the adeguaeg of ca in Q; supporis forItam pulled on. the cable bund /e3 i The walkdown penefra hans. directly below the flooY lC }o /5 pounds, There s'e eSb>nafed pu// force wnJ f' was no slip of +he cable bundle > due b +hese I E$ The h//owing celeulahon comica res hrc es wi+h th e 33 E S et3inic in er h'a. ? pull krce.s. B y inspe chbn, SSE Q mo re crib'ca./ tha j +h e pa // forc e. pn OB E, V. J. Ver+tca./ di3knce between horironk./ L conduit $ boftom o f floor penefra fivn3 13 l

• Nole :

i G ' +o 8 ' &, on ly ~. .n ~~^--G--

osio n o., ) CALCULATION SHEET l 4139l87 ) oATE DESloN BY OATE 2 CHECKED BY SH E ET No. /698 I TVA Seg u oya h -oes noseCr so, No. D0r f of (d h kJ

• ! FILE NO.

SUBJECT CALCULATION NO. C. TVPE 3 Ft.00R PEA /E TRA T/0A/S ( c on j'd. ) De t erinin e w eG h t, w, o f ca ble bandle.s 1. y = x-d',,,gr + where d = diameler of ca'ble bundle l 1 = verweal uns orled leng/h e of cable bundle 8' = cienstly of ca ble handle densily, d', of ca ble bund /e usthy da k De+ermin e l frorn TVA cales/a hbn " Cab /c J+ress Analys4 for l Unsupporlect Verb'ca./ Rans in Spreading Rowri, El. 70G, Con irol building " ( Ref, S. b), p. 4 Ca ble Cable weight /ff. Cable Dendly i Inark Alo. Type (Ibs./fi.) Dia. Gh.) (Ibs/in3) i 1 f WH8 2C # ff 0.077 0.39 6 0.064 tvHo -l 0.07'l 0.s48 0.o G 9 NHC SC #14 0,098 o,400 o.045 w n ?> 4C *l4-0,l'28 o,452 0,06G l NHE SC *)+ 0.15I o.484 0,068 i WH6 7c #l4 o,205 0,531 0,077 W GH 9 C A '2 0352 0,6 % 0,077 l i wvA 2C */G 0,070 c.S 45 0, 0 G '2 j 0.056 0.s42 0,061 WVK

-,,,,c, CALCULATION SHEET 413,171 o,,E j 4/bb!b7 CHECKEDBY M SH EET NO./C, ' ! r oATE DESIGN BY 985 ~Oeb b b JOB NO. PROJECT Suppoe+ of ca bles e,teus,,eu no. 2 2 4. M e) - t,,ue no. susJECT C. TVPE 3 FLOOR PENGTR A TIONS ( c on f 'd. ) Ddermine Weiyht, W, o f exble bundles (con f'd.) /. From +a ble on previous pgge, average ca. ble densiby x

0. 070,1b3 fin I

d From Ref. 5. b, p. 5, FlamemaJ hb 'densiG = 0.067 lb>/in ) w h ec h is appro ximafely equa./ h the average co b /c ciensrg 9 D Q There fore, le f f = 0. 070 lbs /in h Fo r ca ble bundle hr Panel 6-In-28 A

• w =

" *4

• 18 - l2 - 0. 0 70

= 2 6. 7 lbs. I For ca ble bundle by Pan el 0-ir)- 28 8 : p.;. W={ ~ ll 12 0. 0 70) + ( '4 ? 7 o.07 j 18,9 lbs. g 2. .De+ermin e SS E verkcal s e rsmic a ccelera bon, a v Building, el.pecfram carves (vr t 9, VerHea.l 0 8E <esponse S 79/. 2 5 ' fvv O 5 % Au xt'liay/o damping a re y/ven in AHselun en p I%,2 - / w s

---

e-

0$104tt7G. ' CALCULATION SHEET '

• z 4,/37/87

,.f oATE !. A ber DATE_4h3/87 CHECKEDBY 'M SH EET NO. DESIGN gy /4985 ~OEb 4 oVd JOS NO. PROJECT P 8lCDoorl' o[ (a b/e3 CALCULATION NO. 2 24' 5 b ) * / FiE NO. susaEci a C. T1PE 3 FLOCK PENETU T)CA/S (con 'd.)I

2. -Delerrnine SSE verh'ca.I seisinic accelerahtn, etv lcoMW

?1. Since verRca.I response spee.hwn ca.rve3 a.re not g ava.ila b[c.. for the. /hilr43 B u.il c(in g

e. l. ~7 5; 7.. O j ~

W +h e c u r v eJ (n 4ttichnerat 2 for -a Floor level approxima fely 60 ' a cove +h e ' C on frol Acorn floor { may be conservah'vely used. t g Sin ce SSE verh'ca./ response Jfectru!M curve 3 Gr8 ( n o F a valla ble,, th e 08 E curveJ in Ot'achmenf i f 2 can be - mulhph'ed by '2 i>, order lo develop SSE curves. Y; i For th'e: purpose of tht3 calculahyn, it will be conserva fivel a ssamed +ha t the ca ble band /es a re su.bjecfed +o th e pea k ssE veeitca / a ccelera Won. Due.1o the flextbr/tig of Me long, p{ . slender cable bundles M guestivr>, the aclual \\ f: SSE verhica./ accelera fruni corresponding }o the 'naht.rs.l frequencies -of the cable bundles w/// 3 %l frohaby be considerably sma//er + hen the pesk l i accele ra b'on. g o SQAl FSA /C Ta ble 3.7./-3 ( Aef, &), a. { According +S E clampthy ra h'o j lyp rea l S for concrefc and stee/ struefures 13 5 %. Dynamic hj +es hny by Tv A of a 2 0 ca ble bun dle,, 20 fee t long) with Plamemns h'c con ting ( Test s Series 3 resulled in m essared h orieon fal l damping va lu es of 21. I % an d '24.8 % i a c c ordiny +v Table I of Test Ae, cort CES -BN-10/0 D (see arrachment 5).

0510111 746 CALCULATION SHEET 4h,In eaTE R RObePb 4h /87 CHECKEDBY NA7 DATE $H EET NO. oEsion sY ] PROJECT ko d JOB NO. -O SUDJECT DDdI O d O) CALCULATION NO. 2 2 4' W b ) ~ / RLE NO. I c. TvPE 3 Ft00A PENE TRA TIONS (con //d) 4. ConcluS fon Since the esHmaled pa// hrce (= /0 h /6 lbs. ) egaals or exceeds the JSE verb'ca/ seismic i in er h'a. force ( = 5. 5 +o 8. 0 lbs. ), th e support me+ hods hi yverifted the cableyerh'ca/ un pull fes f5 adegua fel a ca ble for Pan e/J 0-m-28A and 0-nt-28 8, c. e l Therefvre, va bles are adegaalely.rupporfed. a ? E. CONC Lust oN l ) 2 i 6 a.s ecl on +h e e valas hun describ ed in Secfron E consa hhg of a review of applicable Twl dra wing.s., i clise.as.sions wtth TVA per3 onn e/, and a fre/d a" ws lhdown, the esble supporf meIhods used for 4 ca bles pene tra/9 the control Room Hoor ce considered }o be ade pale. of 1 i i A

o,....., CALCULATION SHEET

• F -

4,/2,7/87 cars / 8, 8 0 b 6 r f5 cits 4h 3/8 7 essexto.y nmM /5 sseerso. /6985 oesicu ay

• • O 2 Ie --

JOB NO. Y ea/dOVa PROJECT $ cp orf of Ca b/eJ cAtcuution so, 22 4. F(S) - / ntn no. susaect C, TYPE 3 PLooR PENE TRA TIONS (con f 'd. ) Defermine SSE verh' cal rei'Smte accelerabun, av (cmt'd.) 2. l Fiya.re 4 on p. 2G plo ts fh e pea k 08 E ver h'ca / a ccelerah'on values taken froiri ra h ' s, 2 vs. % e damping'ar relah'enship o A +taihmen t are 4, a lih e Ry' log-log scale. As shown in Froir) Ryure exrsts asing a 4, th e p e a k 08 E v e r h' cal a ccelera hvn a t 5 % damping /5%, which is a redsonable0, / 5 g For an assum ed is damping ra h'0 of v a lu e based on Tvnh dynamic leshhg s f ca.ble h u n d/c5, +h e pes k 08 E ver h'c a./ accelerah'on i.s

0. / 0 g.

3. Defermine 55E verh'caI seBmil: inerfra hrce, F I F= W a ~ v 3 where kl= weight 0f cable bundle \\ 26.7 lbs by fane/ O-in -28i9 =

12. 9 lbJ by Pa n e l 0-m-28 6

= le F w = ma x. us ey h t of ca.ble bundle) 1 2 /o.7 /hJ. = i 4 ay= paak ssE verhcca.I a cceierahon 2 pea k 06 G ver h*ca / a ccelera hon hr 5% dsupkg 0.303 2 > o./5 g== d 'zo y hr l5% demptf = 2 - o,10 3 = F = 2 6.9 - 0.30 = 8.0 lbs. h r 5% dampmg 2 6. 9 0. '2 0 = S. S lbj. h y /5 % da mptny = - - ' - - - - - - - ~ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _, _ _ _ _ _ _ _ _

0$10 (1174) CALCULATION SHEET A/21,/87 om ,i R. Roherk 4h s /87 en,eneo s, _>t<p)d. /7 om , w uo. ons,an, TvA Sea u aya h -oe8_ ,e, no. 3 ,,one, Jaogor F of Ca b led c tcut,, ion no. 2 2 4. 6 (8 )- /,,te no. suancr 17. R E~F ER ENe E S S Q^/ Elem en F Repor t 224. 5 (8), R 0, Suppor f-1. o f Ca bles 2. TVA Dra wing.s I a. Drawin 4 7W (o o 6 - /, R 2 2, "'M echa n t'ca./ Layou t of c on h ol B oards ' Drswing 48al/2 9 4, & s, " Misce /lineous S/ee /, b. fram es, car bS 4 Pla f foras - She et '/ " Dvdwing 48N1296, R I7, " Miscellan eous Sfeel, c.

Frames, CarbS $ Pla f hrms - Sheet 2 "

1 i d. DrawIn 4bN l296, RI2, "Mtseellaneous SleeI, Fra m es, Ca.r hs f Pla / hrms - Sh ee f B " e. Dra wing 48N /296-1, R 20, "Inise eIldn cou) Sfee /, Fram es, cise bs $ Pla tforms - Sh ee t 4 " i 1 \\ f. Drawing 4 5N816 - 5, A 6, " Condaff $ Grounding,, Floor El. 79 2. 0, De hu'/s - Sh ee f 3 ', g. Dra wing ).45 N 216 - G, RI O, " Con 0'uff $ Gr 73 2. 0, De tails - Sh ee f 4 ' Ploor E b. Drawing 42N73 0, R 6., " Miscellaneous S/ee/, ca ble Butter suppoei3, Plan B eIow El. 73 2. O,, i. Drawinq 48 Al7SI, AS, "(niscellaneouJ 5 fee /, ca b le Gutter Suppo ris,3ec Wons Below El. 73 2. 0,

CALCULATION SHEET M%7b ^ oaTE 4/25!87 CHECKEDBY >1$I7Q SHEETNO. O OI DATE / fo 98 5 DESIGN 8Y

• O2h-JOB NO.

N N OV4 PROJECT P / cAtcuatsonno22$.SCO)*l bkCforf ab (dN f3 rutE no. s'veJEcr 2. R EFG R ENCES _ (coni'd ) 2. TVA brawing.s tYliscellaneous 3 feel, Drawing 4BA/ 751-1, R ), 'ca bie Gu++er Supporf5, secWons Below E/. 75 2.0 " j. 45/4 880- 2G, RI9,' Condait and l<. Drawing Grounding,Shee t IS ' y3, Fire Shp Penefra hu Cable Tra b De+ ails - b

3. Memo from +he concerned indivMaa./ h Mark i

S k a r win s k i, da fed 12/ /o/86, w h ich in clu des i hr th e adeg u.a.9 of th e ca.ble a concern y sappor tb hr Pan e/J l-m-!5, 0-m-l'2, 0-M - 26, b 0 - m - 2 7, a n d 2-m / 5

4. Field walkdowns of Control Room and Ceble H

reading Room condackd on 4//S/87 and Sp/I&/87by A. bberis (8ech k/), s. ma bre (kl 4 ( 8 ech fel),, C. Henderson (TVA ), a n d H. l fa o b (T V A.). - Trip R eport. d 5. TVA Calculahnns " Con trol Bldg. Fram es, Car bs $ Pla thrms, " k a. l RI, [ e2s asosos soi J orkd Verh' cal " Cable Stress /Inalysi3 for unsYOG > Con trol b. Rans in Sp' reading Room, El.86053/ 800 ], (06/05/85.' A Building, R o, 182 5 Ta ble 3.7. I-3," Damping Aa fios used in

6. SGAl FSAB knalysi3 of Caiegory I Siru e }u r es, Sy s lem s, Compo n and soil kr Struefures Lisled in Ta ble 3. 7. /- I

~- - -... n xo

0510 (111at CALCULATION SHEET a.n,/n em 4 h b /3 7 CHECMDBY N] ~ SHEET NO DATE DESION By /6985 TM Sequovah -oes so, No. nosect r .i $ldO OOI' Of Cd b!b5 + b b '* FILE NO. CALCULATION NO. SUBJECT // T I 1 .S y i ,I Q H i ... ;-l N s t ram as g g -1 Asria/rs - '

• / >

r* f r. * * - m W (n w i t . f; tQ o e i ' 'h l i u L ,- Egg t i i .! oooo;oE.- i l 4 I i i' S l __v.Pysq,p o .~ j i.~pf .~ 1 e ., ~ ,~ 2 i-t t 3;! i a. 'e: i ,i ~* c: g . I> 3 l w c 1, o x s o.,[' %.-t? k'. 15 9 -.-f a k g, y p ; )i - .;-4 2a -~ s a 1 f E (c..i n y ~ i e sI ce io f-

====, i ? i s g o! ! s i 68 Ba i i i r w 8 ? 5 Q. r.'- ___2 e i I O ! f j ? l e W s i L V-pi w u,,f-o gj 1 J. Q 97 ; i[ n k i e. o .Tme a;j gi t 2 W,w s r . g ...e

1. ~

N O , f,' h *- NCp k. y[_,.;l. m g- __s w m i

• V g

t.:., 'd,e}'. Q. m a g i-e i D I t = = { l]; 3 ii i L4J / u

Q h

f [ ~-- d i C ~g o g/ ,88",,,,, + { b = ,i. g N 1-T1 t . '} r = m Q. = 4 (. n g4 t ,o e e o = 1 i ,6 r r y i, AC I 1 C 1 4 '. I o h l pg W Q D ll \\ ~~ }s; 4 s g w 2 l l. sp ia _!_ o y. j b e T h.ME I 3 D

• Q '%

L: ~2 S \\ b ; ! a J .b .a n MATCH

i. _ '. _

A .. -) - - *' '5 i ) I_'l 4 Mar % e_ . t._- 1 K* ^ o LJAJE \\ 1 ( 4 N a l

k. - jp w

I' 40 y $ l .w 'a h_____.__..._._-_.

CALCULATION SHEET ~!17,!((_ l oATE SHEET NO.' h / +/2 b/8 7 CHECKED BY I DATE 6 -_ oEslGN SY _ .aosNo. - NA b 6 4 4oW b J er,oaEcT _ r i ~ _ FILE NO. -- Of bbb CALCULATION NO. SUBJECT ,o,o o P y

-u o l N -

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• l A TTA CHMENT: 3 SHEET - 2 0F 4-03/26/1987 11:22 DNFCAS Wil 190 C-K 1

l~1 - 615 622 6869 P.12 a5 i TABLE I % F~i sux"^av or eraroaxeo te57 auas-5 ?? ] i TEST L RilN TEST ACCELERATION (o) NO. TYPE OF TEST. AXIS TEST LEVEL X-LPA Z-IPA Y-LPA ..4 COMMENTS AND Rll MARKS ^ [ Test Series 1 - Fixture Evaluation Testinal 1 Sine f. weep X ' 1-2 Sine Sweep 2 - 0.1 g . b 0.1 g See Note 1. g i,,) 3 Sine Sweep Y 0.1 g See Note 1. b 4 RMF TRI <Q-SQN See Note 1. 5 RMF TRI ,Q-SQN 1.1 .1.3 0.8 N r\\ 1 ]TestSeries2-UncoatedCableBundle(44 Pounds)l. 4a-1 Sine Sweep X 0.1 g p a 2 Sine Sweep Z 0.1 g See Note 1. G 4 [ 3 Sine Sweep Y 0.1 g See Note 1. F 4-RMF TRI Q-SQN; -1.2 1.3 0.8 l See Note 1. [> S RMF TRI Q-SQN 1.1 1.3 0.8 { 6 RMF TRI Q-SQN 1.1 1.3 0.8' 1 7 RMF TRI Q-SQN 1.1 1.3 0.7 ~ j 8 RMF TRI' Q-SQN 1.2 1.3 0.7 With LYDT's disco [ 9 Sine Sweep - X 0.1 g nnected. 2 y Repeat of Run 1 pith .l 4 damping LVDT's disconnec4ed.. i is 18.2%.. l is 13.3%. {TestSeries3 < F1 mastic Coatino on Cable Bundle (72 Pounds)c s.. m 10 Sine Sweep X 0.1 g .g 11 Sine Sweep Z 0.1 g See Note 1. p 12 Sine Sweep Y-0.1 g.. See Note 1. 13 RMF TRI Q-SQNi 1.2 1.3 0:7 See Note 1. 1 .14 RMF TRI Q-SQN 1.1 1.3 0.8 l i: 15 RMF TRI Q-SQN 1.2 1.3 0.7 16 RMF TRI Q-SQN. 1.2 1.3 0.8 ~l 17 RMF - ) TRI Q-SQN 1.1 1.3 0.7 With LYDT's disconnected. 1 Damping ll i I ] X-Axis 21'.1%. 18 RMF TRI <Q-WBN 3.3 4.1 1,3 Z-Axis 24.8% l ^ 19 RMF TRI <Q-WBN 4.0 4.6 1.7 l 20 RMF TRI Q-WBN 4.6 4.4 1.9 21 RMF TRI Q-WBN 4.6 4.6 2.5 22. RMF TRI Q-WBN! 4.2 4.6 2.2 [, s

. ', n ' A TTA CHMENT 3 SHEET 3 0F 4

• 2i@ri039),"j'"j" 03/26/1987 11:23 DNE/CI,5 Wil 190 C-K 615 632 6869 P.1J

( '4_jlsrlQf Report No. 17747-L l

llfb:h.? h.,:f]f' ' j,'f", TABLE I (Continued) l I ~ TEST RllN TEST ACCELERATION (g) NO. TYPE OF TEST AXIS TEST LEVEL X-ZPA Z-ZPA .Y-ZPA COMMENTS AND JEMARKS n [ l Test Series 4 - Flamastic Coating and 192-Pound Weicht (262 Pounc3)l ll u 23 RMF TRI Q-WBN 4.2 4.4 2.1 i [i! Damping X-Axis 15.1%. ~ g Z-Axis 4.3%. W q h p p NOTE 1: All sine sweep tests were run from 1 to 40 to 1 Hz at a sweep rate of y 4-one octave / minute.. l h NOTE 2: Detailed results from each test series are included in the folloUing appendices: k p" Test Series Aopendix l d l Q 1 IV q 9 2 Y 3 3 VI ,4 V.II a a r i i M LEGEND: ZPA = Zero Period Acceleration RMF = Random Multifrequency I ,,1 TRI = Triaxial ~ .Q-SQN

• Q ' level is 1.25 X SSE; SQN = Sequoyah Nuc' lear Plant t

Q-WBN a Q 1evel is 1.25 X SSEr WBN = Watts Bar Nuclear Plant i LVDT = Linear Variable Differential Transformer f 9 m l u l r f

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