Text

Rev 0 to BFEP-PI 86-05, NRC IE Bulletin 79-02/79-14 Program Document for Browns Ferry Nuclear Plant
	ML20147E392
Person / Time
Site:	Browns Ferry
Issue date:	07/29/1986
From:	Buchanan L; TENNESSEE VALLEY AUTHORITY
To:	;
Shared Package
ML18032A736	List: ML20147E324; ML20147E392; ML20147E415; ML20147E438; ML20147E546; ML20147E560; ML20147E586; ML20147E653;
References
	BFEP-PI-86-05, BFEP-PI-86-5, IEB-79-02, IEB-79-14, IEB-79-2, NUDOCS 8803070052
	Download: ML20147E392 (57)
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FOR BR%'NS TERRY NUCLEAR FIANT

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Wh b2 AFFECTS: Civil Engineering Branch Nuclear Engineering Branch Browns Ferry Civil Lesign Project Browns Ferry Mechanical Design Project Browns Ferry Analysis and Support De. sign Project REVISION RO R1 R2 R3 R4 R5 DATE PREPARED

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s NRC-OIE BULLETIN 79-02/79-14 PROGRAM DOCUMENT BTEP-PI 86-05

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.- 1.0 DOCUMENT PURPOSE................ m.................................

.0._. BULLETIN RE IREMENTS AND BFN SCOPE................................

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-....___.._.1. I_E Bulletin 79-02/79-14.Requ remen s..........................

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3.4 DNE Site Coordinator - Browns Ferry Analysis'~and Support I

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Browns Ferry ArialysiE ~and"Slipport Design ~ Project 79-02/79-14

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- - 4:1 -Procedures............................,....

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-4.1.1.BF-SMMI-5.1-A.......................................... -- 1 1_ _

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4.1.2. BF-MMI-99.............................................

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.._.4.1.3 BFEP-PI 86-06........................~................~ ~ 11 4.1.4 BTEP-PI 85-01.........................................

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" I. 2 Inspections

............................T..:.................. 1 4.2.1 IE Bulletin 79-02 Inspections.........................

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4.2.2 IE Bulletin 79-14 Inspections.........................

12 4.2.3 V e r i f i c a t i o n ' 'a l k down.................................

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4.3 Data Eva1uation..............................................

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14 4.3.1 79-14 Evaluation Progra:

4.3.2 Ini t ial DNE Saf ety Evaluation.........................

15 4.3.3 Inspection Package Evaluaticn.........................

16 4.4 Reconciliation Analysis and Support Design...................

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4.4.1 Piping A:.alysis.......................................

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@. s e 4.4.2 Support Design........................................

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NRC-0IE BULLETIN 79-02/79-14 PROGR.e. DOCLHD;T BTEP-PI 86-05 DWy l

TABLE OF CON' TENTS (Continued)

Page 4.5 Design Modifications.........................................

17 17 4.6 Program Records..............................................

4.7 Hanger Tracking Program......................................

17 18 4.8 Final Report.........................'.......................

4.9 Post Program Change Control and Evaluation...................

18 5.0 REFERDJCES AND DEFINITIONS........................................

20' 5.1 References...................................................

20 5.2 Definitions..................................................

21 6.0 APPDiDIXES A.

BFN Hanger Tracking Program (Preliminary).....................

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Listing of Drawings IES 79-14 Analysis / Inspection Boundaries (Preliminary)....................................

B.1 C.

Analysis List and Associated Design Documents (Preliminary)...

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l NRC-OIE BULLE"'IN 79-02/79-14 PROGRAM DOCL'ME?C BTEP-PI 86-05' i

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1.0 DOCUME?C PURPOSE The purpose of BFEP-PI 86-05 is to outline the essential elements of-TVA's program to assure satisfactory' address to the Nuclear Regulatory Commission (NRC) requirements found in Office of Inspection and Enforcament Bulletins (OIEB) 79-02 and 79-14, to coordinate and. control i

the independent elements within the program and to define the-Division of Nuclear Engineering (DNE) project organization and responsibilities for the completion of the scope work.

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BTEP-PI 86-05 is an upper tier document.that establishes the program plan.

Section 4.1 provides a brief description of subordinate documents that prescribe specific procedural control associated with OIEB

.79-02/7 9-L4r reconciliation: ac.tivitien e ".a i:,n...................

I I, The scope of this document is limited to OIES 79-02/79.-24 issues for the.

Browns Ferry Nuclear Plant (BFN) Units 1, 2, and 3.

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Due to the similarities of the two bulletins relative to systems to be inspecte'd,' inspection. ele =ents and. reportability, as well. as to minimice any duplication of effort, the two programs are merged.

NRC-OIE Bulletin 79-02, "Pipe Support Base Plate Designs Using Concrete e.{3 Expansion Anchor Bolts" was issued March 8,1979... Principa.1. purposes of.

9,y the, bulletin were to verify that pipe support base plate flexibility was accounted for in the calculation of anchor bolt loads, that the anchor bolts were. installed properly, and that adequate factors.of safety were met.

NRC-0IE Bulletin 79-14, "Seismic Analysis for As-Built Safety-Related Piping Systems," was issued July 2, 1979. The purpose of the bulletin was to ensure that the as-built safety-related piping systems and supports are verified as being consistent with the seis=ic analysis model.

The basic directive of the bulletin was "to verify that the seismic analysis applies to the actual configuration of safety-related piping systems."

The scope of this project instruction does not include the following piping:

a) Piping included in the Long Term Torus Integrity Program (L'I"'IP).

The controlling document for L"'I'IP is CEB Report 83-34 I.EB j

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79-02/79-14 requirements are being reconciled through this program.

j b) ControlRo[ Drive (CRD)insertandwithdrawpiping. As constructed conditions are being reconciled through ECN P0880 (unit 1), P0859

^g (unit 2), and P0881 (unit 3).

c) Control Rod Drive (CRD) scram discharge piping.

IEB 79-02/79-14

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requirements are being reconciled through ECN P0392 according to procedure SMMI 14.4.1.3-L.

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NRC-0IE BULLETIN 79-02/79-14 PROGRAM DOCUMENT BTEP-PI 86-05 Sh

..e 2.0 BULLETIN REQUIREMENTS AND BFN SCOPE 2.1 IE Bulletin 79-02/79-14 Recuire=ents IE Bulletin 79-02 was issued March 8, 1979, first revised June 21, i

1979, supplemented on August 20, 1979, and further revised November 8, 1979. The purpose of the bulletin was to ensure that concrete expansion anchor bolts used on safety-related piping meet design requirements.

1 IE Bulletin 79-14 was issued on July 2, 1979, revised on July 18, j

1979, first supplemented on August 15, 1979 end further supple =ented on September 7, 1979. The purpose of the bulletin was to ensure that as-built safety-related piping was reflective of the design document used as input into piping system seismic analysis. These requirements apply to all safety-related piping 2-1/2" in dia=eter and greater and to seis=ic Category I piping, regardless of size which was dyna =ically analyzed by computer.

For older plants, where Seismic Category I requirements did not exist at the time of licensing, it must be shown that the actual configuration of safety-related systems, utilizing piping 2-1/2" in diameter and greater meets design requirements.

The bulletins request the licensee to inspect and verify certain hf2 design aspects of safety-related piping and pipe support components.

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The licensee is required to:

2.1.1 Identify inspection elements.

2.1.2 Initiate an inspection program.

2.1.3 Expedite inspections where nonconformances affect system operability and submit a description of the results.

2.1.4 Evaluate the effect of nonconformances on system operability and co= ply with applicable action statements in technical specifications.

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2.1.5 For pipe supports that use concrete expansion anchor bolts, inspect and evaluate in accordance with OIEB 79-02 requirements.

2.2 BFN Progra= Scoce TheB7Np[ogramscopeforsafety-relatedpipingsystemsand components requiring inspections and reconciliation to IEB 79-02 and i

79-14 is the same.

Inspection and reconciliation will be perfor=ed on all safety-related piping (TVA Class 1 Seismic) 2-1/2" in diameter and greater and to all safety-related piping regardless of Fwa

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s NRC-0IE BULLETIN 79-02/79-14 PROGRAM DOCUMENT BTEP-PI 86-05 dhh

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W 2.2.1 IEB 79-02 Scope-IEB 79-02 requires the inspection of expansion type anchor bolts. BFN did not use wedge bolts during the construction phase; only self-drilling type anchors were used. Wedge bolts were used in the repairs resulting from the

'79-02/79-14 evaluations. Therefore, IEB 79-02 inspection and reconciliation requirements will be.perfor=ed on-all-

. expansion type concrete anchor bolts employed on safety-related pipe supports within the BFN program scope.

For the purpose of identifying re=aining IES.79-02 inspections, beginning May 1985 DNE prepared "tally" sheets to. identify- 02 inspections already perfor=ed; then "79-02 Haster Copy" location plans were prepared to identify 79-02 inspections not yet performed..These location plans are-.-

-- A arked..to. uniquely identify.each. support to.be inspected +:

r r..'.=along with sufficient information to locate.same.

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' location plans are assigned a unique drawing number by the-..

DNE Site Coordinator and will be updated for-the duration of the IEB 79-02/79-14 program; they will be =aintained as design input documents.

d As IEB 79-02 inspections are completed and submitted to the

. Analysis and Support Design Project for evaluation,.a...

ir.. listing of;the supports will be maintained as part of the.-

Qy N-14 hanger tracking program. Appendix A is a represen-tative sample of the 79-14 hanger tracking program which lists all the supports and piping analysis within the scope of IES 79-14 See Section 4.7 for a description of the hanger tracking program.. A representative sa.:ple of this listing is presented in Appendix A.

(Note: This listing will be constantly updated until the progra= is co=plete as inspections are being co=pleted.)

2.2.2 IEB 79-14 Scope

'"he initial IES 79-14 scope is based on TVA Class 1 functional boundaries as defined by NES =arked-up flov diagra=s attached to standalone quality information

=emora%du: NES 840416 261.

The original version of these flow diagrams was developed

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using design input fro = Nuclear Engineering Branch'(NES) and, Civil Engineering Branch (CEB). NEB is responsible for identification of all syste=s or portions of syste=s that are safety-related irrespective of pipe sir.e. and CEB is responsible for identification of portions of syste:.s dynamically analy::ed by co=puter.

It is the responsibility of each section perfor.::ing IES 79-02/79-14 reconciliation

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NRC-0IE BULLETIN 79-02/79-14 PROGRAM DOCLHE!C BTEP-P: 86-05

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tasks within the Analysis / Support Design Project to. update, secure interface reviews, and maintain current a set of special "analysis / inspection boundary'" schematics for i

units / systems within their scope.

The final scope of IEB 79-14 will be shown on these "analysis / inspection boundary" sche =atics. The boundaries will be extended beyond the functional boundary to a physical boundary, either an anchor point or through a combination of supports / restraints forming an equivalent anchor. All piping and supports within'that boundary are subject to the provisions'of IES 79-02/79-14 These sche =atics have been assigned unique drawing numbers and will be =aintained for the duration of the 79-14 progra=. A sche =atic has been prepared for each safety-related system within the BFN scope for IEB 79-14 for each of the three units of the BFN plant.

A listing of these drawings is provided in Appendix B.

Piping / anchorages outside the scope of 79-02/79-14 is either not shown or depicted by dashed line. This exclusion will generally include safety-related piping less than 2-1/2" in diameter that was not dyna =ically analyzed 4

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and non-safety-related piping. Exclusion criteria is N

defined in BFEP-PI 86-06.

For those portions not under the 79-14 scope but initially identified under the 79-02 bulletin scope, DNE will provide independent justification i

by sa.pling.

In the event small branch lines are included in the seismic analysis model, these lines will be included within the IES 79-14 progra=. An accountability will be made prior to the completion of the IES 79-02/79-14 program to assure all ite=s have been addressed.

Appendix C contains a liGting of pipe stress analysis proble= nu=bers within the scope of IES 79-14 along with I

applicable design docu=ents. The original issue of this is considered preli=inary information.

3.0 PROGRAM ORGANI".ATION AND RESPONS!BILITIES This section defines the organization within DNE responsible for the resolution of NRC IE Bulletins 79-02 and 79-14

'"his organization is presented in Figure 3.1.

This reflects the matrix organi:ation with the IEB 79-02/79-14 Lead Engineer accountable to both the Project Engineer and Chief Civil Engineer.

Accountability to the Project Engineer includes schedule, budget, and progress. Accountability to the Chief Civil Engineer is manpower availability and technical

.g6 adequacy. The following paragraphs delineate responsibilities for key nh IEB 79-02/79-14 project personnel.

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--- 16hted6 NRC-0IE BULLETIN 79-02/79-14 PROGRAM DOC"".Er BTEP-P 86-05 i

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.1?;7 3.1 IEB 79-02/79-14 Lead Engineer

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Obtain schedule direction from BTEP Projset Engineer.

o Assure manpower availability to meet IEB 79-02/79-14 project o

requirements, Reports progress to BFEP Project Engineer.

o Implement criteria and guidelines controlled by Chief Civil o

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Assure criteria and procedures employed by the Analysis and o

SupportsDesign--Project;. meet.the:19-02/79-14 project.requitecent.

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o Facilitate interface between DNE Inspection and DNE; Program

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Coordinators.

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o Coordinates and is the DNE representative for all 79-02/79-14 r'esponses.

3.2 Project Centro 11er/ Contract Administrator Develops and i=plements project. control procedures to assist. lead w

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' $. Ei engineer in assigned responsibilities..

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Design Project.

o Establishes and maintains a status monitoring program for IE Bulletin 79-02 and 79-14 o Coordinates contractor activities and approves contractor billings.

3.3 DNE Procra: Coordinator - Browns Ferrv Analvsis and Sucoort Design Project o Coordinates implementation of the DNE program to meet the requirements of NRC IE Bulletins 79-02/79-14 o Ensures that discrepancy problems (deviations fro = or deficiencies in design which present potential safety

concerns) are evaluated.

See BTEP-PI 85-01.

Coordi' nates anchorage problems identified by IE Bulletin 79-02 o

inspection which have Bulletin 79-14 i=plications.

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NRC-OIE BULLETIN 79-02/79-14 PROGRAM DOCUMEIC BTEP-PI 86-05 I'

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$7 3.4 DNE Site Coordinator - Browns Ferry Analysis and Sucoort Design Project Schedules inspection activities to bring about a_ complete and o

timely inspection of the physical areas covered by IEB_79-02 and 79-14 Submits Phase I inspection data to DNE Program Coordinator for o

records control.

Ensures that Phase II data is transmitted to those perfor=ing the o

inspection review, design, or analysis.

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NRC-0IE BULLETIN 79-02/79-I4 PROGRAM DOCUMENT LFEP-PI 86-05 T.#

FIGURE 3.1 OlVISION OF NUCLEAR EWINEERIE 4

CHIEF CIYil E W INEER PROJECT EEINEER R. O. Barnett BRCWNS FERRY EWINEERING PROJECT J. P. Stapleton ASSISTANT PROJECT E MINEER LEAD EEINEER lEB 79-02/79-14 OlVISION OF NUCLEAR EEINEERIN W. L. Strathers PROJ CONTROL / CONTRACT ADMINISTRATOR C. Turnbow Boundary / Scope fyf

.:r Progress Schedule Final Report DNE PROGRAM DNE SITE COORDINATOR COORDINATOR J. Beason B. Caldwell TVA Knoxville BFN Site Knox / Site Interface Knox / Site interface ANALYSIS AND SUPPORT DESIGN PROJECT PIPIE ANALYSIS / SUPPORT DESIGN SECil0NS 19-02/79-14 PROSRAM l

DNE SliE DNE KNOX CONTRACTOR I CCWIRACIOR 2 5SPECil0NS ANALYSIS /

ANALYSIS /

FIELD ENGINEERIM DESIGN DESIGN DESIGN 3i EVALUATION EVALUATION EVALUAll0N

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BTEP-PI 86-05 NRC-0IE BULI.ETIN 79-02/79-14 PROGRA.M DOCUMEhT

&Rh tg 3.5 Browns Ferry Analysis and Suecort Design Project 79-02/79-14 Piping Analysis and/or Supoort Design Section(s)

Evaluate deviations of the as-built versus as-designed piping and o

pipe support configuration.

Review the completed inspection data packages to determine if o

additional inspection information is needed.

Perform final piping analysis and/or support design as necessary in accordance with the Design Criteria for As-Built Piping o

Systems, BFN-50-D707 and DNE calculation BFEPC 51186 for support design methods.

Prepare unitized physical piping drawings _(separate drawings for o

each BFN unit) for project cechanical group utilizing as-built data.

Initiate and approve design modifications to reconcile as-built o 'co'ndition of plant to licensing co==itments.

Docu=ent the analysis of all safety-related piping and supports o

within the scope of the bulletin.

Perform walkdowns of piping and supports for which the analysis 2

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and support design will be based.

Update, interface review, and maintain current the IES 79-14 o

Analysis / Inspection Boundary Drawings.

4.0 PROCEDURES / TASK IMPLEMENTATION GUIDE 4.1 Procedures Due to the relative time of issuance, nature, and si=ilarity of affected systems, TVA committed to recencile NRC OIE Bulletins 79-02 and 79-14 sicultaneously.

TVA's total program for the reconciliation is a combination of procedures and programs intended to address specific issues contained in the two bulletins.

The intent of this section is to provide an overview of the progra= for the technical resolution of II Bulletins 79-02/79-14 The following is a listing of subordinate documents that' establish procedural control over associated IEB 79-02/79-14 reconciliation activities and shall be used for the Browns Terry Nuclear Plant.

These documents stand alone and are not an integral part of this l

document. The require =ents of this document take precedence in the event of conflicting information or require =ents.

Figure 4.1 l

presents the 79-02/79-14 flowchart.

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PEPRF edb4mmL NRC-0IE BULLETIN 79-02/79-14 PROGRAM DOCUMFfC BTEP-PI 86-05

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W 4.1.1 BF SMMI-5.1-A Browns Ferry Nuclear Plant Office of Nuclear Power Special Mechanical Mai~ntenance Instruction Controls the inspection and repair program for self-drilling type concrete anchors for all safety-related components within the BFN

.Provides a means.of corrective program scope.

' action for. systems and components within the IEB 79-02 scope.

. Browns Ferry Nuclear Plant 4.1.2 BT MMI-99 Office of Nuclear Power.

Mechanical Maintenance Instruction c;r:2 -. Establishes. procedural control:for. recording -

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. r and documenting required inspections for implementation of IEB 79-14 requirements.

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Inspection requirements include supports, valves, configurations, penetration t ir.;4::. c :..... clearances,,and spring hanger data.

4.1.31.BFEP-PI 86-06. Browns Ferry. Nuclear: Plant

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- Division of Nuclear Engineering Project Instruction

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]TI Establishes procedural control for recording and documenting required inspections for implementation of Phase II requirements for IEB 79-14 4.1.4 BTEP-PI 85-01 Browns Ferry Nuclear Plant Division of Nuclear Engineering Project Instruction Establishes procedural requirements within the Division of Nuclear Engineering for i=plemen-tation of IEB 79-14 requirenents.. Establishes procedural control for the review and evaluation of inspection data packages generated under BT SMMI-5.1-A and BF MMI-99 for the identification and processing of "potential safety concerns."

4.2 Insoections t

Prior to May 1985, inspections were performed by the BFN Modifications Group. Beginning May 1985, all 79-02/79-14 inspections will be perfor=ed by engineers and/or design engineering associates within DNE Analysis and Support DesiC Project. DNE1 - 1112A

NRC-OIE BULLETIN 79-02/79-14 PROGRAM DOCUMIST-BTEP-PI 86-05 dM kj;$

Inaccessible areas vill be inspected during outage periods.

Difficult access areas vill be addressed on,a case by case basis.

4.2.1 IE Bulletin 79-02 Insoections IE-Bulletin 79-02 addresses the improper installation and/or analysis of concrete expansion anchor bolts in safety-related systems including TVA Class 1 seismic All inspections of anchor bolts to address IE systems.

Bulletin 79-02 shall be inspected in accordance with SMMI-5.1-A (Ref. 5.1.4).

SMMI-5.1-A provides instruction for the recording of as-built measurements, establishes acceptable tolerances, and directs the repair of anchors built out of tolerance. All applicable SMMI-5.1-A data sheets are to be completed as the means of transmitting as-built data to DNE for evaluation.

4.2.2 IE-Bulletin 79-14 Inspections

-IE-Bulletin 79-14 (Phase I) requires the verification that the seismic analysis of safety-related systems apply to the actual as-built configuration. The Phase II portion requires verification that the analysis and support design

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c:eet code compliance. All systems within the 79-14 program

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scope shall be field inspected in accordance with BF MMI-99 (Ref. 5.1.1).

Inspectors shall be trained in accordance with QZN101.001 (Ref 5.1.9) and QZN101.002 (Ref. 5.1.10) so that they =ay be able to recognize potentially significant safety concerns requiring prompt evaluation and resolution. The intent of the training is not for quality acceptance of deviations but rather for purposes of gathering appropriate data for use in the evaluation of the as-built condition.

Inspections vill include the detailing of the pipe support attach =ent locations and configurations onto base plates. This is also a IEB 79-02 concern since it affects the plate flexibility.

BTN has i=ple=ented a separate program to address c:iscellaneous or supplementary steel.

For purposes of gathering necessary data for input to support this progra=,

the actual inspection boundaries vill include limited portions of miscellaneous steel. This is addressed in BTEP-PI 86-06 and BT MMI-99.

4.2.3 erification Walkdown l

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Walkdowns shall be per BTEP-PI 86-06 and the requirements of the following specified guidelines.

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. DNE1 - 1112A

NRC-0IE BULLETIN 79-02/79-14 PROGRAM DOCUMD."I' BTEP-PI 86-05 NES Piping and Support Verification Walkdowns

'Y a.

Any walkdown will include:

- A co=plete verification and docu=entation of all

, supports.

- A'G-32 bolt spacing violation inspection to the

, require =ents of Reference 5.1.5.

- Verification of piping configuration data including support location and direction of restraint and valve

^

location and orientation.

2 Any revised dr added information will be. clearly.

..[ identified (e.g.,additionalite=slhich'E.aybe*

supported from the supports or process pipingh n...... i.1...... r v ;...... 4 A11'wa1Ydown' data'will have "Preparer" and "Verifier"

_ sign and date.

. Reverification Due to 0.=itted Infor=ation.

b.

c..

..g..

in the event that a data package is deter =ined to.be,.

2t3

...lirico=plete or"codflicting, 'it shah '. tie' returned #5r%

-3

'??

', reverification.' Only those items indicated as being additionally required =ust be "prepared and verified."

c.

Final Piping Walkdown After perfor=ing the analysis, the piping system shall be walked down to verify that the analysis is a true representation of the as-verified configuration. This i

verification is to include: A visual verification of the piping configuration to verify that the condition found at the time of the walkdown is consistent with the data used as analysis input, a thermal clearance check for anticipated movements, and a feasibility study to determine if any required new supports can be installed.

d.

Final Support Constructability Walkdown After the support design calculations have been perfor=ed but prior to issuing the design drawing, the system shall be walked down to verify the constructibility of new supports or =odification.to existing supports.

LP

..r

' DNE1 - 1112A j

NRC-0IE BULLETIN 79-02/79-14 PROGR.d DOCUMrf."T BTEP-PI 86-05 4 A.

.. si.s 33.y 4.3 Data Evaluation

4. 3'.1 79-14 Evaluation Progra DNE SEP 81-02 (Ref. 5.1.2) was developed within the guidelines of a three phase plan to specify DNE's

=ethod of evaluating as-built information to comply with IE Bulletin 79-14 (Note: The =ethod described also satisfies the 79-02 requirement of those supports within 79-14 syste=s). The procedure was initially used by DNE to resolve the requirements of the bulletins until May,-1985.

Changing i,

responsibilities, organinations, and procedures j,

caused DNE SEP 81-02 to become outdated. BTEP-PI 85-01 (Ref. S.1.3)-is the current procedure to be followed.

The fra=ework for "VA's progra= to co= ply with OIE Bulletins 79-02 and 19-14 was first established in a June 18, 1981 letter from L. M. Mills to James P.

O'Reilly. The following is a description of each phase.

4.3.1.1 Phase I ADG The initial evaluation of the inspection data for M

potential safety proble=s will be performed, co=pleted, and docu=ented al=ost concurrently with the inspection. As individual inspection deviations are discovered they will be sent to engineering for evaluation. At any ti=e, if the deviation is determined to be a potential safety proble=, a seismic analyst's discrepancy resolution input sheet (BTEP-PI 85-01, Attach =ent 6.1) will be initiated and action will be taken in accordance with facility technical specifications within the appropriate-li=iting condition for operation.

Each discrepancy (nonconformance) received by engineering will be evaluated within two days utilizing engineering judg=ent and by rigorous analysis (if necessary) within 30 days.

All significant safety proble=s evaluated as a definite potential for loss of pressure bounda:y or centainment seal will be corrected within this ti=e period. These will be pro =ptly reported to the NRC in co=pliance with applicable action statements in technical specifications.

3 ilhl3 "F DNE1 - 1112A r

v- - - -

__)

NRC-0IE BULLETIN 79-02/79-14 PROGRAM DOCUMEvr BFEP-PI 86-O's

...g F

4.3.1.2 Phase II The second phase'of evaluation shall be to evaluate each system for code compliance.

Following the receipt of the Phase I inspection data package (i.e., one system in one unit) and any verification

.walkdown information, engineering shall evaluate all data with respect to existing analysis and coda requirements.

If the piping analyst determines that a potential safety problem exists for any i

i h ll be

.given analysis problem,.appropr ate act on s a r-taken in accordance-with facility-technical specifications..

.:r.

. :. b. ;. ;.". & : -

r.. :.1: tre.

...e

.O 4.3.1.3 Phase III Modifications resulting.from reanalysis and/or..-

F: support design-is the next-step-to: ensure l. co=pliance.. :t tr ir::-

. P. i r

. J: c s

4.3.2 Initial PNE Safety Eva'luation IE.Bulletin 79-14 requires the performance of an

..rs evaluation of the significance of a nonconformance J$fk.

(discrepancy) as rapidly as possible to determine

~r whether or not the operability of the system might be jeopardi:ed during a safe shutdown earthquake.as defined in the regulations. This evaluation is expected to be done in two phases involving an initial engineering judge =ent (within 2 days),

followed by an analytical engineering evaluation (within 30 days).

TVA procedural address to these NRC requirements is found in BTEP-PI 85-01 Paragraph 4.2.3 which requires:

A 48-hour time limit for the potential effects of a.

a discrepancy.

This limit applies from the time the discrepancy is identified to the evaluating l

section until the safety evaluation, if required, is performed.

b.

If reanalysis is required to confirm engineering judgment, it must be completed within 30 days of I

when the discrepancy is identified in the evaluating section.

2 s.W C;".$

L=r DNE1 - 1112A

NRC-0IE BULLETIN 79-02/79 PROGRAM DOCUMil.T BTEP-PI 86-05

EDs,

w e if to -

c.

Units in a cold shutdown condition are exempt from the requirements of 4.3.2.a and 4.3.2.b with the exception of those systems whose continued operation is necessary to maintain cold shutdown as identified by NEB and defined by plant technical specifications.

For those units exempt from 4.3.2.a and 4.3.2.b the requirements of NEP-9.~1 must be met.

4.3.3 Inspection Package Evaluation The DNE Program Coordinator receives the co= pitted inspection package from the DNE Site Coordinator and passes it on to the piping and/or support analysis sections.

The inspection data package shall be reviewed for,co=pleteness, assembled, and evaluated per BFEP-PI 85-01.

Any package found to be ince:plete shall be returned for reverification.

4.4 Reconciliation Analysis and Succort Design 4.4.1 Piping Analysis

.O 47.*{,-

When all inspection data has been assembled and "q4*

Evaluated per the require =ents of SMMI 5.1-A and MMI-99, a final as-built analysis shall be performed in accordance with BTN-50-D707 (Ref. 5.1.6).

Iso =etrics and load tables are issued within the 79-14 program.

schedule and a reverification is perfor ed as described in Section 4.2.3.

This analysis will de=enstrate code compliance and establish the necessary design modifications.

4.4.2 Support Design Once the final.as-built analysis is co=plete, the configuration is field verified, the supports are evaluated, and if necessary redesigned. All support I

evaluatiens shall be done in accordance with DNE calculation BTEP C51186 (Ref. 5.1.8).

All anchor bolt i

designs and the effects of baseplate flexibility shall be in accordance with D3-C1.7.1 (Ref. 5.2.7)'.

Pipe support drawings shall be issued and calculations microfilced within the progra schedule.

g~r,

.4.h

, DNE1 - 1112A

NRC-0IE BULLETIN 79-02/79-14 PROGRAM DOCUMEC BTEP-PI 86-05 a cs

'i5~~h 4.5 Design Modifications All necessary design modifications are required to reconcile the "as-built" configuration in order to be in compliance with the code and licensing commitments.

Design additions and modifications shall be accomplished only through approved documents or work plans with QC inspection. The two principle documents governing implementation of IEB_79-02/79-14 design modifications are HAl-L and MAI-23.

Any subsequent relocation of supports shall be in accordance with Section 2.6 of MAI-23.

4.6 Program Records All original. iEB 79-02/79-14.' program ' records;are the'??.' 4n0 responsibility'.of DNE.*?These are to be 'onsidered as-design c

records and shall be controlled per the recuirements of NEP-1.3.

9: L:T? =* :5-T '.

i '. ' : *. a Prior to 'the co'=pleti'on'of the'79-14.progra=p modifications by

,'others to the piping systems and/or piping supports under the 79-14 program require reporting to, and approval of, the BTN Analysis and Support Design Project Lead Engineer for the purpose of maintaining configuration control. The monitoring of post program modifications is addressed in subsection 4.9.

.:?>

c55R 4.7 Haneer Trackinc Program

~;

A hanger tracking program shall be maintained by the Analysis and Support Design Project. This will be a co=puteri ed data base.

The type of information will include:

a.

Cross-reference between analysis problem and support designation.

b.

IES 79-02 applicability, c.

Design status.

d.

Total work scope.

This program provides the mechanism to identify and track both design and modification work.

It also provides infor=ation that may be used as a planning tool.

.3 W$

- DNE1 - 1111A

NRC-OIE BULLETIN' 79-02/79-14 PROGRAM DOCUMEh7 BTEP-PI 86-05

%j, Ti.

4.8 Final Reoort At the completion of the 79-02/79-14 progra=, DNE shall prepare a final report for subsequent submittal to the Nuclear Regulatory Commission.

This report shall contain a su= mary of all TVA actions perfor=ed and the results.

Post Program Chance Control and Evaluation 4.9 Following the inspection, evaluation, and reanalysis associated with the 79-02/79-14 program, there is a continual need to conitor all changes affecting the system throughout the life of the plant. The procedures identified below have been established and shall be used to control all subsequent design codifications.

Following the issuance of the report to NRC, it shall beco=e the respe libility of DNE to monitor all change

.,docu=ents as detailed in NEP-6.1 (Ref. 15).

Incoming change documents can be in the for= of FCR's, DCR's, ecc.

~

If an ECN is issued, documents revised to incorporate the change shall be listed on the ECN, and the reissue after revision of all documents listed is required before the ECN can be closed.

Design Change Supple =ents (DCS's) 5.gyg shall also be listed and used on the ECN, and their

.ra incorporation on issued drawings is required before the ECN can be closed, as detailed in NYP-5.1 (Ref. 14).

General Constr;ction Specif.'.ations G-29C, G-29M, G-32, G-43, and G-66 shall be the controlling documents for all modifications resulting from IEB 79-02 and 79-14 and all future modifications to piping syste=s and supports within the scope of IES 79-02 and 79-14 Plant procedures must confor= to these docu=ents.

It shall be the responsibility of plant QE to snsure that the appropriate procedures are in place to ensure that design require =ents are cet.

Deviations outside acceptance criteria must be reported to DNE for approval.

i 4

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" DNE1 - 1112A

s NRC-OIE ',ULLETIN 79-02/79-24' PROGRAM DOCUMEh-BTEP-PI 86-05

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.{p FIGURE 4.1 79-02 /79-la INTERFACE LOGIC - FLO CHART t--;---

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NRC-0IE BULLETIN 79-02/79-14 PROGRAM DOCUME1.T BTEP-PI 86-05 did4

.W

5.0 REFERENCES

AND DEFINITIONS 5.1

References:

1.

TVA Browns Ferry Nuclear Plant, Mechanical Maintenance Instruction 99 (BT VMI-99) Instructions for the Implementation of NRC IE Bulletin 79-14 Units 1, 2, and 3.

2.

Special Engineering Procedure (EN DES-SEP 81-02) Implementation of NRC OIE Bulletin 79-14 for Browns Ferry Nuclear Plant.

3.

Project Instruction for Implementation of NRC OIE Bulletins 79-02/79-14 (BTEP-PI 85-01).

4 TVA Browns Ferry Nuclear Plant Standard Practice / Instruction (SMMI-5.1-A) Verifying Correct Installation of Self-Drilling-Type Concrete Anchors.

5.

TVA General Construction Specification (G-32) for Bo)c Anchors

$et in Hardened Concrete.

6. "TVA Browns Ferry Nuclear Plant (BrN-50-D707) Detailed Design Criteria for Analysis of As-Built Piping Systems.

.. Q 71.i,w 7.

Civil Design Standard (DS-C1.7.1) General Anchorage to Concrete.

(

8.

79-02/79-14 General Referer'_a I:.struction for Pipe Support j

Design (BTEP C51186).

9.

TVA Nuclear Training Branch - QC/NDC Training Section "Weld Identification and Sizing Techniques for the I=plementation of Browns Terry Mechanical Maintenance Instruction 99" Course No.

(QZN101.001).

10. TVA Nuclear Training Branch - QA/QC Training Unit Nuclear Quality Control Inspector Training "Mechanical and Progrca Requirements for the Imple=entation of BT MMI-99" Course No.

(Q N101.002).

11. TVA General Constructio'n Specification (G-43) Supports and Installation of Piping Syste.cs in Category I Structures.

12. TVA BTNP Rigorous Analysis Handbook.

13. TVA BTNP Pipe Support Design Handbook.

14 Division of Nuclear Engineering's design output procedure NEP-5.1.

73%

15. Divisi'>n of Nuciear Engineering's change centrol procedure Q

NEP-6,1.

14 a

,3 DNE1 - 1112A

___Pyrw LN NRC-OIE BULLETIN 79-02/79-14 PROGRAM DOCUM%7 BTEP-P! 86-05

.py

.y

16. Project Instruction for Implementation of NRC-OIE Bulletin 79-14 Phase II Verification (BFEP-PI 86-06).

NOTE: All documents referenced' pertain to latest revision.

5.2 Definitions.

Deviation - A difference between the as-built and the output -.

1.

document.

2.

Discrecancy - Any deviation that results in a potential safety

-,.ern conc -.,

3.

Nonconformance - (IEB 79-14) A discrepancy. Nonconformances shall be reported unde'r NCR BFNCEB 8103.'

s t.

Final As-Built Analvsis - Reanalysis incorporating all as-built 4

information to meet code co=pliance.

p.

tn

... r. -. t :.-

u.:.

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5. 'ioect' ion..The?actrof: recording information using measuring hs techniques of sufficient accuracy to describe the as-built condition of a piping / support system.

6.

Walkdown - A configuration check to confirm pipe routing, f(. ?>\\"$$D hanger location, direction of support / restraint. -

relative location of piping components, hanger ce=ponents,~.

f E*'

A walkdown may or may not include physical =easurements.

7.

Insceetion Data Packare - The completed package regttired to perform the Phase I evaluations.

8.

Verification Walkdown Package - The data gathered as a result of the Phase II walkdowns.

9.

Accessible (A) - Defines piping in an area with no restrictions for inspection.

10.

Partially Accessible (PA) - Defines a piping subsystem that contains an inaccessible portion.

11.

Inaccessible (IA) - Defines piping in an area of the plant that*

cannot be inspected curing reactor operation.

12.

Difficult Access (DA) - Areas where inspections are required by IES 79-02 and/or 79-14 but are considered i= practical even with the reactor shutdown.

Information concerning the burden of performing the inspection and the safety consequences of not perfor=ing the inspection will be documented in the final report to the NRC by TVA.

.y

' ~A "45$?

13.

As-Built - A ter: used to describe the installed configuration of piping and related supports.

~' DNE1 - 1112A

1

.A-

S

.y APPOCIX A BFN F. ANGER TilACKING PROGRAM (PRELIMINARY)

Pages A.1 and A.2 ijh

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APPENDIX L LISTING OF DRA'.IINGS INDICATING IEB 79-14 ANALYSIS /INSPEC ION BOUNDARIES (PRELIMINARY)

Pages B.1 - B.3

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31 DNE:

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BFN !?OEX OF IEB 79-14 ANALYSIS /INSPEC'* ION BOUtcARY DRAWINGS

){ij i

47W400-401 Main Steam Unit 1 47W400-402 Main Steam Unit 2 4TJ400-403 Main Steam Unit 3 i

47W406-401 Reactor Water Clean-Up System Unit 1 47W406-402 Reactor. Water Clean-Up System Unit 2 47W406 403 Reactor Water Clean-Up System Unit 3 47W415-401 Reactor Feedwater Unit 1 47W415-402 Reactor Feedwater Unit 2-47W415-403 Reactor Feedwater Unit 3 47W446-401 Raw Cooling Water Unit 1 47W446-402 Rav Cooling Water Unit 2 47W446-403 Raw Cooling c ter Unit 3 a

47W450-401 RHR Service Wa:er System Unit 3 47W450-402 RER Service We.ter System Unit 2 47W450-403 4tER Service Water System Unit 3

}

47W451-401 Emergency Equip =ent Cooling Water Unit 1 47V451-402 Emergency Equipment Cooling Water Unit 2 4TJ451-403 Emergency Equipment Cooling Water Unit 3

(?

47W451-404 E=ergency Equipment Cooling Water Unit 4 n

474452-401 Residual Heat Removal System (RER) Unit 1 47W452-402 Residual Heat Removal System (RER) Unit 2 47W452-403 Residual Heat Removal System (RER) Unit 3 4T4454-401 Fuel Pool Cooling System Unit 1 4TJ454-402 Fuel Pool Cooling System Unit 2 GTJ454-403 Fuel Pool Cooling System Unit 3 474455-401 High Pressure Coolant Injection System Unit 1 4TJ455-402 High Pressure Coolant Injection System Unit 2 474455 '03 High Pressure Coolant Injection System Unit 3

..TJ456-401 Reactor Core Isolation Cooling Syste= Unit 1 i

4TJ456-402 Reactor Core Isolation Cooling Syste= Unit 2 47A56-403 Reactor Core Isolation Cooling System Unit 3 47W458-401 Core Spray System Unit 1 4TA58-402 Core Spray Syste= Unit 2 4TA58-403 Core Spray System Unit 3 4Tsa60-401 Containment Inerting System Unit 1 4TA60-402 Containment Inerting System Unit 2 47Wa60-403 Contain=ent :nerting Syste= Unit 3 E

i I

S.2 ONEt - t:3cA

, _. - _,. ~. _ -.. _,, _.. - _ _ _ _. _. - _ _ _ _ _ _ _ _. _

~

B m INDEX OF IES.79-14 ANA1.YSIS/INSPEC ION BOUNDARY DRAWINGS (Continued)

..y 47W461-401 Containment Atmosp%e: e Dilution System Unit 1 47W461-402 Containment Atmosphett Dilution System Unit 2 47W461-403 Containment Atmosphere Dilution System Unit 3 47W462-401 Standby Liquid Control Unit 1 47W462-402 Standby Liquid Control Unit 2 47W462-403 Standby Liquid Control Unit 3 47W464-401 Reactor Building Closed Cooling Water System Unit 1 47W464-402 Reactor Building Closed Cooling Water System Unit 2 47W464-403 Reactor Building Cicsed Cooling Water System Unit 3 47W465-401 Nuclear Boiler Unit 1 47W465-402 Nuclear Boiler Unit 2 i

47W465-403 Nuclear Boiler Unit 3 47W468-401 CRD Hydraulic System Unit 1 47W468-402 CRD Hydraulic System Unit 2 47W468-403 CRD 1:ydraulic System Unit 3 47W482-401 Clean Radwaste & Decon Drainage Un4t 1 47W482-402 Clean Radwaste & Decon Drainage Unit 2 47W482-403

3;,4 Clean Radvaste & Decon Drainage Unit 3 4')7 47W482-404 Floor & Dirty Radwaste'. Drainage Unit 1 47W482-405 T1oor & Dirty Radwaste Drainage Unit 2 47W482-406 Floor & Dirty Radwaste Drainage Unit 3 47W553-401 Condensate Storage and Supply System Unit 1 47W553-402 Condensato Storage and Supply System Unit 2 47W553-403 Condensate Storage and Supply System Unit 3 47W586-401 Diesel Generator Intake / Exhaust Unit 1/2 47W586-402 Diesel Generator Intake / Exhaust Unit 3 47W588-401 Tuel Oil Syste= Unit 1 47W588-402 Tuel Oil System Unit 2 47W588-403 Tuel Oil System Unit 3 f

47W590-404 t

CO: Storage. Fire Protection & Purging System Unit 3 & Co= mon t

47W600-401 Control Air System Unit 1 i

47W600-402 Control Air System Unit 2 47W600-403 Control Air System Unit 3 i

47W935-401 Air Conditioning Chilled Water Unit 1 47W935-402 Air Conditioning Chilled Water Unit 2 47W935-403 Air Conditioning Chilled Water Unit 3

.4 fip@4 47W831-401 Condenser Circulating Water Unit 1 47W831-402 Condenser Circulating Water Unit 2 47W831-403 Condenser Circulating Water Unit 3 B.3 DNE: - 1130A

~

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APPC.' DIX C

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/JJALYSIS LIST A!O

-ASSOCIATED DESIGN DOCL' MEN ~S

.<r..

t-

-(PRELIMINARY)

?,' i I 2

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C.1 ONE1 - 1:30A

SYSTEM N/.ME - Main Steam

,h FLOW DIAGhh - 472801-1 GE 719E597 g

PHYSICAL DRAVIN - 47W400-Series, GE Dvg. 729E229 (Cont. 90744)

BILL OF MATERIAL 47BM400-Series, 47BM435-1, 47BM404-7 ANALYSIS ISOME3IC DRAWIN(, - 47W400 - (200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-101-1RA 1

IA N1-201-1RA 201.202,203 N

2 IA N1-301-IRA 3

IA N1-101-2RB 1

IA N1-201-2RB 20a Thru 209 N

2 IA N1-301-2RB 3

IA N1-101-3R

-.210 Thru 213 N

2 PA 1

N1-201-3R PA N1-301-3R 3

PA N1-101-4R 1

IA N1-201-4R 214 3 ru 217 N

2 IA

$..12 N1-301-4R 3

IA My N1-101-SR 1

IA N1-201-5R 200 N

2 IA 3

N1-301-5R 3

IA N1-101-6R 1

IA N1-201-6R 200 N

2 IA N1-301-6R 3

IA L

ORIGINAL ISOME3IC - 1.iW335-1 ORIGINAL LOAD TABLES - GE729E401 ORIGINAL SUPPORT DETAILS

".E729E401, 47A400 Series ORIGINAL MANGER LOCATION DRAVINO - GE729E401 I

ES' MA~ID SUPPORTS UNIT 1 - 115 UNIT 2 - 118 UNIT 3 - 115 ISOME3IC, EANGER - (CONI. 90744) Teledyne U-3802, D-3803, D-3806 "hru

& RESUAIN S i

D-3809 D-3826 Tr.ru D-3829, D-3822, D-3831 etc.)

LOCATIONS

s.3t i

es-l C.2 DNE1 - 1130A

SYSTEM NAME - Teedwater

'1:{p FLOW DIAGRAM - 47W803-1 PHYSICAL DRAVINGS - 47W415-Series BILL OF MTERIAL - 47BM435-10, 47BM415-Series ANALYSIS IF,0ME'IRIC DRA' JING - 47W415 - (200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLDi NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-103-1RA 202 N

1 IA N1-203-1RA 200

J.

N 2

IA N1-303-1RA 203 N

3 IA N1-103-IRB 204 N

1 IA N1-203-1RB 201..

4.

N 2

IA N1-303-1R3 205 N

3 IA

, ;;;_ r ORIGINAllISOME~RIC - 47W335-2, -3 IM..

LUGINAL. LOAD TABLES - None

"' 7.?

. -:0'. !!!

l

.a ORIGINAL' SUPPORT DETAILS - BP 951 Thru 957. BP 395, BP 397 Thru 408, BP 1750 BP 1752 hru 1756, 2000, 2002 Thru 2007 ORIGINAL RANGER LOCATION DRAVING - GE729E152, 731E872, 729E401, BP 396, 1751-2, 2001 ESTIMA~ED SUPPORTS UNIT 1 - 36 UNIT 2 - 40 UNIT 3 - 36 e

4 I

e I

/h C.3 DNE:

: 3cA

SYSTEM NAME - Cond. Storage and Supply FLOW DIAGRAM - 47W818-1 yr PHYSICAL DRAWINGS - 47W553-Series BILL OF MATERIAL - 47BM553-Series ANALYSIS ISOMETRIC DRAWING - 47W553 - (200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER s 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-002-2R 1,2,3 A

N1-102-1R 200, 201 N

1 A

N1-202-1R 202, 203 N

2 A

N1-302-1R 3

A

[

ORIGINAL ISOME RIC - 47W335-19

[

ORIGINAL LOAD TA.iLES - 473553-21. -31

.z

$*Q ORIGINAL SUPPOR' LETAILS - 47A553-51 Thru -147

.a ORIGDIAL HANGER LOCATION DRAWING - 47W553-H-1, -2 ESTIF#2 SL??ORM UNIT 1 - 30 UNIT 2 - 30 ON;T 3 - 30

\\

I 1

4 t

I l

1 j

.h

\\

14 l

i C. !-

DNIl - 1130A

/

SYSTEM NAME - leactor Drains 6 Vents FLOW DIAGRAM - 47W817-1 PHYSICAL DRAWINGS - 47W46S-Series BILL OF MATERIAL - 47BH465-Series ANALYSIS ISOMEnIC DRAWING - 47W465 - (200 Series. See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-110-1RA 1

I N1-210-1RA 200 N

2 I

N1-310-IRA e.

..a 3

I N1-110-2R 1

IA N1-210-2R 210 N

2 IA N1-310-2R 3._,

I/g, _

ORIGINAL ISOME3IC'- None

~

/>

W.

ORIGINAI. EOAD. TABLES /.4:47Be6S-2I,W223 r' 7 sp?.

CRIGINAL SUPPORT DETAILS - 47A465-Series ORIGINAL HANGER LOCATION DRAWING - 47W46S-H Series ESTIMA*ED SUPPORTS UNIT 1 - 10 LHIT 2 - 10 UNIT 3 - 20 l

e i

j I

g 2..

I i

C.5 DNE - 1130A

~

e

/

SYS EM NA".E - Fuel Oil-

':$f FLOW DIAGRAM - 47W840-1 PHYSICAL DRAWINGS - 47W588-Series, 47W586-Series BILL OF MATERIAL - 47BM588-Series, 47BM586-Series ANALYSIS ISOMETRIC DRAWING - 47W588 - (200 Series), 47W586- (200 Series)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-018-1D 1&2 A

N1-318-1D 3

A N1-018-2D 1&2 A

N1-318-2D 3

A N1-018-3D 1&2 A

N1-318-3D 3

A ORIGINAL ISOME~RIC - None

..h 1

.nt.;Q ORIGINAL LOAD TABLES - None

':y ORIGINAL SUPPORT DETAILS - None ORIGINAL EANGER LOCATION DRAWING - None ESTIMATED SUPPORTS UNIT 1 -

UNIT 2 -

J UNIT 3 -

a l

i i

d

.a l

C.6 DNI: - ::3cA l

SYSTEM NAME - RHR Service Water (In Reactor Bldg.)

Ib,

'!g FLOW DIAGRAM - 47W858-1 PHYSICAL DRAWINGS - 47W450-Series BILL OF MATERIAL - 47BM435-26, 47BM450-Series ANALYSIS ISOME*RIC DRAWING - 47W450 - (200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-123-1R 200 N

1 A

N1-223-1R 205 N

2 A

N1-323-1R 203 N

3 A

N1-123-2R 1

A N1-223-2R 205 N

2 A

N1-323-2R 204 N

3 A

N1-123-3R 1

A N1-223-3R 206 N

2 A

N1-323-3R 203 N

3 A

N1-123-4R 1

A N1-223-4R 206 N

2 A

,s

'[.k,Tj N1-343-4R 202 N

3 A

1; N1-123-5R 1

A N1-223-5R 207 N

2 A

N1-323-5R 201 N

3 A

N1-123-6R 1

A N1-223-6R 208 N

2 A

N1-323-6R 202 N

3 A

ORIGINAL ISOME~RIC - 47W450-5,

-6,

-7 ORIGINAL LOAD TABLES - 47B450-8 "tru -14

-19 ORIGINAL SUPPORT DE~ AILS - 478450-16, -17

-18 & -20 niru -40 CRIGINAL HANGER LOCATION DRAWING - 47W450-Series ESE! MATED SUPPORTS UNIT 1 - 50 UNIT 2 - 46 UNIT 3 - 46 i

i C.7 DNE - 1:30A 1

SYSTEH NAME - RMR Service Water Pumping Station W'

PLOW DIAGRAM -

e PHYSICAL DRAWINGS - 37W205-Series BILL OF MATERIAL -

ANALYSIS ISOMEntIC DRAWING - 37V205 - (200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-023-1R 200 Y

1,2,3 A

N1-023-2R 201 N

1,2,?

A N1-023-3R 202 Y

1,2,3 A

N1-023-4R 203 Y

1,2,3 A

N1-023-5R 204 Y

1,2,3 A

N1-023-6R 204 Y

1,2,3 A

N1-023-7R

,204 Y

1,2,3 A

N1-023-8R 204 Y

1.2.3 A

ORIGINAL ISOME2RIC -

g

. ~wr V

ORIGINAL LOAD TABLES -

ORIGINAL SUPPORT DETAILS -

ORIGkNALHANGERLOCATIONDRAVING-ESTIMATED SUPPORTS UNIT 1 -

UNIT 2 -

UNIT 3 -

4 b

l

@hE

?'

m-l C.S WE! - 1:3CA

?

SYSTEM NAME - RHR Service Water Tunnel Piping (One Tunnel Each Unit)

FLOV DIAGRAM -

PHYSICAL DRAVINGS -

BILL OF MATERIAL -

ANALYSIS ISOME"RIC DRAVING - /... ;

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-123-7R

. 3.3 A

N1-223-7R

r; 1.2.!

A N1-323-7R 102 7

1.3.3 A

N1-123-8R

-1 A

N1-223-8R

'2, A

N1-323-8R

?--

.3,,

A N1-123-9R

.~

3 A

N1-223-9R

r. -

2 A

N1-323-9R 3

A N1-123-10R 1

A N1-223-10R 2

A ff,#[$

N1-323-10R 3

'A

'.:tr N1-123-11R..... :/._, -

1 A

N1-223-11R 2

A N1-323-11R 3

A N1-123-12R 1

A N1-223-12R 2

A N1-323-12R 3

A N1-123-13R 1

A N1-223-13R 2

A N1-323-13R 3

A N1-123-14R 1

A N1-223-14R 2

A N1-323-14R 3

A N1-323-15R 3

A N1-323-16R 3

A ORIGINAL ISOMETRIC -

~ ~.

CRIGINAL LOAD TABLES ORIGINAL SUPPORT DE* AIL'S -

ORIGINAL HANGER LOCATION DRAWING -

nr..

EST:MA*ED SUPPORTS UNIT 1 -

l.N!j UNIT 2 -

,v UNIT 3 -

C.9 DNE1 - 1120A

SYSTEM NAME - Control Bay Air o

FLOW DIAGMM - 47W866-7, -3 PHYSICAL DRAWINGS - 47W935-Series BILL OF MATERIAL - 47BM935-Series ANALYSIS ISOMETRIC DRAWING - 47W935-(200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSLT.D?

UNIT ACCESSIBILITY.

1 N1-031-2RA 200, 201, 202 Y

1&2 A

N1-031-3RA 200, 201, 202 Y

1&2 A

3 N1-031-3R 1&2 A

i N1-031-4R 1&2 A

N1-031-5R 1&2 A

l N1-031-6R 1&2 A

N1-331-3R 3

A N1-221-4R 3

A N1-331-5R 3

A N1-331-6R 3

A sw N1-331-7R 3

A WM N1-331-8R 3'

A I

'W ORIGINAL ISOMETRIC - None 2

^

ORIGINAL LOAD TABLES - None ORIGINAL SUPPORT DETAILS - Nont i

t ORIGINAL EANGER LOCATION DRAWING - 47W935-Series ESTIMATED SUPPORTS UNIT 1 -

4 i

UNIT 2 -

UNIT 3 -

1 i

4@T-I C.10 DNE: - 1:3e(

SYS'"EM NAME - CO: Storage. T.P.

FLOW DIAGRAM - 47W843-1 PHYSICAL DRAWINGS - 47W950-Series BILL OF MATERIAL - 47BM591-Series 47BM590-Series ANALYSIS ISOMETRIC DRAWING - 47W590-(200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILI'"I N1-039-1C.s 1,2,3 A

s...

N1-039-2D 1,2,3 A

.-?7;

..i ;

ORIGINALiISOMETRIC - None ORIGINAL

LOAD TABLES.- 47B591-1, 47B590-1 bkIb A SUPPORT DETAILS - 47B590-2, -3 & 591-2, -3 ORIGINAL' HANGER LOCATION DRAWING - 47W590-1, 47W591-1 J.,W~,}

' '?

ESTIMATED SUPPORTS UNIT 1 -

v.

UNIT 3 -

..e e

4 C. 1 DNE1 - 1:3cs

S.

SYS EM NAME - Standby Liquid Control

'g%

.J TLOW DIAGRAM - 47W854-1 PHYSICAL DRAWINGS - 47W462-Series BILL OF MATERIAL - 47BM462-Series ANALYSIS ISOMETRIC DRAING - 47W462-(200 Series. See Below)

INSULATION / MODE -

ANALYSIS PROBLEM

- NLHBIR 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-163-1R 202, 203 N

1 PA N1-263-1R 204, 20S N

2 PA N1-363-1R 200, 201 N

3 PA N1-163-2R 1

IA N1-263-2R 206 N

2 IA N1-363-2R 3

IA N1-163-3R 1

A N1-263-3R 207 N

2 A

N1-363-3R 3

A ORIGINAL ISOMETRIC - 47W462-4 CRIGINAL LOAD TABLES - 478462-1, -2,

-3 ORIG!NAL SUPPORT DETAILS - 47B462-4 Thru -11 ORIGINAL RANGER LOCATION DRAWING - 47W462-Series ESTIMATED SUPPORTS UNIT 1 - 76 UNIT 2 - 76 UNIT 3 - 76

)

l 1

i

.:ns h'h w

\\

1 1

C.12 ent: - )?ina 1

SYSTEM NAME - EECW Ti,.7 TLOW DIAGRAM - 47W859-1, -2 PHYSICAL DRAWINGS - 47W451-Series BILL OT MATIRIAL - 47BM435-30, 47BM451-Series ANALYSIS ISOMETRIC DRAWING - 47W451-(200 Series See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NLHBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-DGB-Al 223~

Y 1,2,3 iA N1-167-1RA 200,201

-Y 1

A N1-167-1RB 202 N

1 A

N1-267-IR 222 N

2

,A N1-367-1R 3

A N1-167-2RA 203 N

1

A N1-167-2RS

.204 N

1 A

N1-367.2R 3

A N1-167-3RA 1

A N1-167-3R3 1.

A N1-267-3RA 2

A

_x g4 N1-267-3R3

~

- : 7..

2 A

~1f N1-367-3RA 214 N

3 A

i N1-367-3R3

", r.'.he 215 4

.-N 3

A N1-167-4RA 207 N

1 A

N1-167-4R3 208 N

1 A

{

N1-167-4RC 212 N

1 A

N1-167-4RD 213 N

1 A

N1-267-4RA 2

A N1-267-4RS i

2 A

N1-267-4RO 232.233 Y

2 A

N1-267-4RD 2

A N1-367-4RA 216,221 N

3 A

N1-367-4RS 217 N

3 A

N1-367-4RO 218, 219 N

3 A

N1-367-4RD 220 N

3 A

N1-167-5EA 209 Y

1 A

N1-167-SC3 1

A N1-367-5R N1-167-6RA

~~

3 A,

1 A

N1-167-6F3 1

A N1-167-6RC 1

A N1-167-6RD 1

A N1-367-6R 3

A N1-367-7R 3

A

+

'k~3r

?

1 C.13-ONI1

-!!30A J

~

SYSTEM NAME - EECW

.g i

'g, FLOW DIAGRAM - 47W859-1, -2 PHYSICAL DRAWINGS - 47W451-Series t

BILL OF MATERIAL - 47BM435-30, 47BM451-Series t

ANALYSIS ISOMI3IC DRAWING - 47W451-(200 Series See Below)

INSUI.ATION/ MODE -

I ANALYSIS PROBLDt NLHBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-DGB-Al 223 Y

1,2,3 iA N1-167-IRA 200,201.

Y 1

A N1-167-1RB 202 N

1 A

N1-267-1R 222 N

2

.A N1-367-IR 3

A N1-167-2RA 203 N

1

A i

N1-167-2RB

' *.204 N

1 A

N1-367-2R 3

A N1-167-3RA 1

A N1-167-3RB' 1

A i

N1-267-3RA 2

A i

$t N1-26 7 -3RB. ~ u. - C..

2 A

N1-367-3RA 214 N

3 A

N1-367-3R3

" T.I2.: 215 4-

.-.N 3

A i

N1-167-4RA 207 N

1 A

1' N1-167-4R3 208 N

1 A

l N1-167-4RC 212 N

1 A

N1-167-4RD 213 N

1 A

4 ll!

N1-267-4RA 2

A i

N1-267-4RS 2

A N1-267-4RC 232.233 Y

2 A

N1-267-4RD 2

A N1-367*-4RA 216.221 N

3 A

N1-367-4RS 217 N

3 A

i N1-367-4RO 218, 219 N

3 A

N1-367-4RD 220 N

3 A

N1-167-5EA 209 Y

1 A

N1-167-5CB 1

A j

N1-367-5R 3

A N1-167-6RA

~~

1 A

I N1-167-6RB i

1 A

N1-167-6RC 1

A N1-167-6RD 1

A N1-367-6R 3

A N1-367-7R 3

A C.13 Ont!. :*sna

ANALYSIS PROBLEM

.A NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY qq w

N1-367-8R 3-A N1-367-8RS 3

A N1-367-8RC 3

A N1-367-8RD 3

A N1-167-9R 211 N

3 A

ORIGINAL ISOMERIC - 47W451-8. -9 ORIGINAL LOAD TABLES - 47B451-Series

(

ORIGINAL SUPPORT DETAILS - 48N1217-Series, 47A451-Series ORIGINAL HANGER LOCATION DRAWING - 47W451-Series ESTIMATED SUPPORTS UNIT 1 - 269 UNIT 2 - 269 UNIT 3 - 269 h

4 tic 4$

C.11.

ONr1 - 3:3ns

SYS~EM NAME - Recirculation Loop

,% 8 rn,g TLOW DIAGRAM - 47W817-1 PHYSICAL DRAWINGS - 3E153F754 BILL OF MATERIAL - Contract 90744, 91750 h

ANALYSIS ISOME3IC DRAWING - 47W403-(200 Series See Below)

~~~

~ ' ~ ~ ' ' ~

lNSNL TION / MODE -

ANALYSIS PROBLEM NUMBER.

79-14 ISO T.

ISSUED?

UNIT ACCESSIBILITY N1-168-1R 200,201,202*

Y 1

IA N1-268-1R

.T

. 203,204,**

?N 2

IA N1-368-1R 3

IA r

. - u -

ORIGINAL ISOMETRIf

. None -

l'.'

ORIGINAL LOAD TA3LES - GE729E461 t

ORIGINAL SUPPORT DETAILS - 47A465-200 & Grinnell SK. 200 Thru 211 i ;

ORIGINAL HANGER LOCATION DRAWING - GE729E462, GE729E461

~

ESTIMATID SUPPORTS UNIT 1 - 61 UNIT 2 - 39 UNIT 3 - 61 i

1

Also 47W452-269 Y

- Alse 47W452-270 N k

.s57 C.15 p.;r i.

,.,n,

SYSTEM NAME - RWCU FLOW DIAGRAM - 47W810-1 PHYSICAL DRAWINGS - 47W406-Series BILL OF MATERIAL - 47BM406-Series ANALYSIS ISOME3 IC DRAWING - 47W406-(200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-169-1R 202, 203 Y,N 1

IA N1-169-2R 200 N

1 A

N1-269-2R 204 N

2 A

N1-369-2R 201 N

3 A

N1-169-4R 205 N

1 PA N1-269-4R 206 N

2 PA N1-369-4R 3

PA i

ORIGINAL ISOMI3IC - 47W335-14

.I.5 37, ORIGINAL LOAD TABLES - None m,f ORIGINAL SUPPORT DETAILS - 47A406-Series CRIGINAL HANOER LOCATION DRAWING - 47W406 Series ES IMATED SUPPORTS UNIT 1 - 15 UNIT 2 - 7 l

j UNIT 3 - 14 r

)

1 r

i l

4 4

J l

i i

a I

l C.16 mrt:.. 3e,

~

s SYSTEw. NAME - RSCCW mh.

TLOW DIAGRAM - 47W822-1

~m, PHYSICAL DRAWINGS - 47W464-Series BILL OF MATERIAL - 47BM464-Series ANALYSIS ISOME'IRIC DP/ RING - 47W464-(200 Series, See Below) i INSUI> TION / MODE -

ANALYSIS PROBLEM NL'MBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-170-1R 204, 205

.N 1

IA N1-270-1R 221, 222 N

2 IA N1-370-1R 200, 201 N

3 IA N1-170-2R 202, 203 N

1 IA N1-270-2R 219, 220 N

2 IA N1-370-2R 206, 207 N

3 IA N1-170-3R

-212, 213 N

1 A

N1-270-3R,.._,

.. _.. 223, 224 N

2

.A N1-370-3R 208, 209 N

3 A

N1;-170-4R!? ^9I' - 2111'-:-

N 1

A N1-270-4R 225, 226 N

2 A

JM.S N1-370-4R

.... 210, 216 N

3 A

'7/

N1-170-5R 214, 215 N

1 A

N1' 270-5R

'?*

7 228, 229

. -. ;N 2

A N1-370-5R 217, 218 N

3 A

N1-170-6R 1

A N1-270-6R 2

A N1-370- 6R 3

A N1-170-7R 1

IA N1-270-7R 1

IA N1-370-7R 3

IA N1-270-8R 2

IA N1-270-9R 2

IA ORIGINAL ISOMETRIC - 47W464-15 Thru -18 ORIGINAL LOAD TABLES - 47B464-31 ORIGINAL SUPPORT DE AILS - 47B464-21, 47A464-Series ORIGINAL HANOIR LOCATIO[DPMING - 47W464-3 Series ES~IMA~ED SUPPORTS UNIT 1 - 184 UNIT 2 - 184 UNIT 3 - 184 w

1 C.17 veri..

sn,

SYSTEM NAME - RCIC dh qf FLOW DIAGRAM - 47W813-1 PHYSICAL DRAWINGS - 47W456-Series BILL OF HATERIAL - 47BM456-Series, 47BM435-0,

-1,

-4,

-5,

-10 & -29 ANALYSIS ISOME3 IC DRAWING - 47WL56-(200 Series, See Below)

INSULATION / MODE -

i ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-171-4R 212 N

1 PA j

N1-271-4R 214 N

2 PA N1-371-4R 3

PA i

N1-171-5R 213 N

1 PA N1-271-5R 215, 216 N

2 PA '

N1-371-SR 3

PA ORIGINAL ISOMI RIC - 47W335-16. -17

. g.s ORIGINAL LOAD TABLES - 47B456-21, -22. -23, -31

'M'r

,'9?

ORIGINAL SUPPORT DETAILS - 47A456 Series.

ORIGINAL HANGER LOCATION DRAWING - 47W456-H Series ESTIMATED SUPPORTS UNIT 1 - 77 UNIT 2 - 77 UNIT 3 - 77 l

f f

1 2

1 i

i i

i a

1 i

i I

,. e i

l t

C. S DNI: - 1:30s l

l

~

SYSTEM NAME - HPOI 3

%g FLOW DIAGRAM - 47W812-1 1

PHYSICAL DRAWINGS - 47W455 Series I

BILL OF MATERIAL - 47BM435-0.

-1,

-3,

-4

-5, -7.

-9, 47BM455 Series ANALYSIS ISOME3!C DRAWING - 47W455-(200 Series. See Belcw)

INSULATION / MODE -

i ANALYSIS PROBLEM i

NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-173-6R 211, 212 N

1 PA N1-273-6R 216, 217, 218 N

2 PA 1

N1-373-6R 3

PA i

i N1-173-8R 200 N

1

'A i

l N1-273-8R 219 N

2 A

l!

N1-373-8R 3

'A N1-273-9R 2

A l

)

N1'-173!104

'"~' '200 N

1 IA i

~~

~

N1-273-10*

215 Y

2 IA 4

N1-373-10*

3 IA 4

i=.x J

ORIGINAL ISOME3IC.47W335-9 Thru -13.

ORIGINAL LOAD TABLES - 47B455-21 Tc.ru -27. -31. -32 ORIGINAL SUPPORT DETAILS - 47A455 Series i

ORIGINAL HANGER LOCATION DRAVING - 47V455-H Series EST!MA~ED SUPPORTS UNIT 1 - 132 UNIT 2 - 132 UNIT 3 - 132 i

COMPLE"'ELY LAPPED BY N1-201-2P3 IS PROB. NECESSARY?

4 6

l 1

l i,

~ $,

i

~

i

.=

]

v j

i C.19 2Nt1 - 1; xx

l t

F SYSTEM NAME - RER i

TLOW DIAGRAM - 472811-1 PHYSICAL DRAWINGS - 47WL52-Series BILL OF MATERIAL - 47BM435-1,

-3,

-5,

-8,

-10. -11, 14

-29, 47BML52-Series ANALYSIS ISOME3IC DRAVING - 47WL52-(200 Series. See Below)

INSULATION / MODE -

F ANALYSIS PROBLEM l

NUMBER 79-14 ISO ISSUED 7 UNIT

/CCESSIBILI"Y 1

N1-174-1R 250, 261 N

1 A

I N1-274-IR 281 Y

2 A

I N1-374-1R 3

A i

N1-174-5R 249, 257 N

1 A

3 N1-274-5R 280 N

2 A

N1 374-5R 3

A N1-174-6R

. 256 N

1 A

N1-174-7R 253, 256 N

1 A

N1-374-7R 3

A N1-174-8R 252 N

1 A

i N1-174-9R 258, 259 N

1 IA g,{gi N1-274-9R 284, 286 N

2 IA

't.7 N1-374-9R 3

IA

^

N1-174-10R 275 N

1 A

l N1-374-10R 264, 278 N

3 A

j N1-174-11R 255, 279 Y,N 1

IA a

N1-274-11R 273 Y

2 A

)

N1-374-11R 272 Y

3 A

N1-374-12R 265 N

3 A

N1-174-14R 251 N

1 A

N1-374-14R 266 N

3 A

1

]

N1-174-16R 277 N

1 A

N1-17!.-17R 267 N

1 A

N1-274-17R l

N1-17a-18R 268 N

1 A

N1-274-18R 2

A

~

N1-174-19R 1

A N1-274-23R 2

A 1

i ORIG!!ML ISOME3IC - 47W335-4 ~hru -8

.1 1

ORIGINAL LOAD TABLES - 47B452-21 ~hru -37 J

l ORIGINAL SUPPORT DE AILS - 47B452-38, 47A.52-Series I

g ORIO!NAL HANGER LOCATION DRAWING - 47Wa52-X Series em 2

\\T ES*IPX"ED SUPPORTS UNIT 1 - 296. UNIT 2 - 296. UNIT 3 - 296 2Nt1 - 1:3cx C.20 J.

r I

t l

SYSTEM NAME - RHR X TIE lG).

.ps.*

TLCW DIAGRAM - 47W811-1 20 PHYSICAL DI: 2INGS - E21. E55. 148, 171,*:hru 174 BILL OF MATERIAL - E21. E32, E56. E57, 144, 173. 176 ANALYSIS ISOMETRIC DRAWING - 47W452-(200 Series See Below)

INSU MTION/ MODE -

ANALYSIS PROBLEM l

NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-274-7R 282 N

2 A

N1-274-14R 283 N

2 A

7

.. m -

.,.v.

ORIGINAL ISOMETRIC - None CRIGINAL' LOAD TA3LES ENone l

ORIGINAL SUPPCRT DETAILS - E32. E56. E57, 117C. 475.52-79 ORIGINAL RANGER LOCATION DRAWING - ES2, E56. ES7, 117C

'l.;,

..4 2h

.?

2 I.*,

'2 ESTIMATED SUPPORTS UNIT 1 - 16 I

IA

\\

. - *. -~

yy: g 1s UNIT 3 - 16 l

I 1

iA l

C.21

?;I:

sn,

~

SYSTEM NAME - DSH TLOV DIAGRAM - 47V811-1 PHYSICAL DRAVINGS - E21. E55, 148, 171, 172, 173, 174 BILL OT MATERIAL - E21 E32, E56. E57. 148, 173, 174 ANALYSIS ISOMER IC DRAVING - 47W452-(200 Series. See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED 7 UNIT ACCESSIBILITY j

N1-174-20R 1

Ik l

N1-174-21R I

1 IA N1-274-20R 2

IA N1-274-21R 2

IA j

N1-374-20R 3

IA N1-374-21R 3

IA t

ORIGINAL ISOME3IC - None ORIGINAL LOAD TABLES - None i.

N,gE

~ rf ORIGINAL SUPPORT DETAILS - E32 E56. E57, 117C 473452-39 a

ORIGINAL RANGER LOCATION DRAVING - E32. E56. E57, 117C ESTIMA~ID SUPPORTS UNIT 1 - 12 UNIT 2 - 8 UNIT 3 - 16 t

i I

d i

i l

j l

\\

i e

I a

41 3 p.y M

i C.22 1

Ogg:. g;3eg 1

l

f SYSTEM NAME - CORE SPRAY TLOW DIAGRAM - 47W814-1 l

PHYSICAL DRAWINGS - 47W458-Series i

BILL OT MATERIAL - 47BM458-Series, 47BM435-1,

-3, -5. -8. -10. -11 l

ANALYSIS ISOMETRIC DRAWING - 47W458-(200 Series. See Below) i i

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY l

l N1-175-4RA 222 Y

1 IA N1-275-4RA 224 N'

2 IA N1-375-4RA 226 N

3 IA N1-175-4R3 223 Y

1 IA N1-275-4RS 225 N

2 IA N1-375-4K3 227 N

3 IA QRIGINAL ISOME~RIC - 47W335-15 i

.s.h.

ORIGINAL LOAD TA3LES - 47B458-21. -22. -23. -31 "I.;193.f' 13RIGINAL SUPPORT DETAILS - 47A458;-

i.

ti<

'..5-3?

L CRIGINAL RANGER LOCATION DRAWING - 47VA58-N-Series l

ES*! MATED SUPPORTS UNIT 1 - 160 mil! 2 - 160 mil! 3 - 160 t

i

{

l

-4 s

3 f(:?.W.

i S4 j

C.23 2NE1 -::39 i

SYSTEM NMI - RADUAS~E a

'{f TLOW DIACRAM - 47W852-1, -2 t

w PHYSICAL DRAWINGS - 472482-Series BILL OF MATERIAL - 47BM482-Series ANALYSIS ISOME3!C DRAVING - 47W482-(200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM N"MBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-177-1R 200, 205 N

1 IA I

N1-277-1R 208, 209 N

2 A

1 r

N1-377-1R 3

A N1-177-2R 1

IA N1-277-2R 210, 211 N

2 IA N1-377-2R r

3 IA N1-177-3R 1

A i

N1-277-3R 2

A N1-377-3R 3

A l

N1-177-4R 1

IA

+,

N1-277-4R 2

IA l

O..*-

N1-377-4R

'N N1-177-5R 3

IA 1

A N1-277-5R 2

A N1-377-5R 3

A I

?

ORIGINAL ISOME3IC - None ORIGINAL LOAD TABLES - 47B482-1, -2 ORIGINAL SUPPORT DETAILS - 47B482-3, -4 t

ORIGINAL RANGER LOCATION DRAWING - 47Wa82 Series ES*IMATED SUPPORTS UNIT 1 - 73

?

UNIT 2 - 73 UNIT 3 - 73 i

I f

4 i

i

^

2'.%

I

'A.s'i"A. -

I 0.04 met: - :+= 4

~

SYSTE". NAME - FPCS

"[b.s FLOW DIAGRAM - 47W855-1 PHYSICAL DRAWINGS - 47W454-Series BILL OF MATERIAL - 47BMI-54-Series ANALYSIS ISOME RIC DRAWING - 47W454-(200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED 7 UNIT ACCESSIBILITY N1-178-IR 200, 201 N

1 PA N1-278-1R 210, 211 N-2 PA N1-378-1R 227, 228 N

3 PA N1-178-2RA 213 "tru 217 N

1 PA N1-278-2RA 2

PA N1-378-2RA 220 Thru 224 N

3 FA N1-178-2RB 1

IA N1-223-2RB 2

IA N1-378-3R3 3

IA N1-178-2RC 1

IA N1-278-2RC REk N1-378-2RC 2

IA 3

IA 5 f-N1-176-2RD 1

IA N1-278-2RD 2

IA N1-378-2RD 3

IA N1-178-2RE 1

IA N1-278-2RI 2

IA N1-378-2RE 3

IA N1-178-3R 206 N

1 A

N1-278-3R 219 N

2 A

N1-378-3R 226 N

3 A

N1-278-4R 219 N

2 A

N1-378-4R 3

A ORIGINAL ISOMETRIC - None ORIGINAL LOAD TABLES - 47B454-1,

-2, -16 ORIGINAL SUPPORT DETAILS - 473454-5 2.ru -15 & -17 Thru -28 ORIGINALHANGERLOCATION[ DRAWING-47W454-Series ESTIMATED SUPPORTS UNIT I - 134 LWII 2 - 134 UNIT 3 - 118 0,@

C.25 DNE! -

2**^t

~

SYSTLi NAMF - C0!CROL ROD DRIVE (RL)

b.h

.,',p't FLOW DIAGRAM - 47W820-2 PHYSICAL DRAWINGS - 47W468-Series BILL or ;'.'.trRIAL - 47BM600-23 ANALYSIS ISOME3 IC DRAWING - 47W468-(200 Series See Below)

INSULATION / MODE -

MIALYSIS PROBLEM NUMBER 79-14 ISO ITSUED?

UNIT ACCESSIBILITY

.11-185-IR 218 N

1 PA N1-285-1R 2

PA N1-385-1R 216 N

3 PA CRIGINAL ISOMETRIC - None ORIGINALLOADTABLE[-None ORIGINAL SUPPORT DETAILS - 47W600-72 idh ORIGINAL HANGER LOCATION DRAWING - 47W600-72

'4'3?

ESTIMATED SUPPORTS UNIT 1 - 100 UNIT 2 - 106 UNIT 3 - 89 1

l

7. w.

C.26 Dnt: - ::,na

SYSTEM NAME - C0tiIROL ROD DRI'v'E (SDM)

/k

-j.g TLOW DIAGRAM - 47W823-2

. PHYSICAL DRAWINGS - 47W468-Series BILL OF MATERIAL - 47BM600-23 ANALYSIS ISOMETRIC DRAWING - 47W468-(200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM NUMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-185-2R 200 Thru 202, 207 Y

1 hl-285-2R 203 Thru 206 Y'

2 N1-385-2R 210 Thru 212 Y

3 ORIGINAL ISOMETRIC - None ORIGINAL LOAD TABLES - None ORIGINAL SUPPORT DETAILS - 47W600-72

.f.s.

7g.3 ORIGINAL HANGER LOCATION DRAWING - 47W600-72 y

ESTIMATED SUPPORTS UNIT 1 - 100 UNIT 2 - 106 UNIT 3 - 89 l

.l

My 5h.p-I C.27 DNE! - 2:30A 1

SYS~T.M NAME - DRYWELL COVI7t0L AIR

-Ip FLOW DIAGRAM - 47W847-4,

-5, -5A PHYSICAL DRAWINGS - 47W400-Series BILL OF MATERIAL - 47BM600-Scries ANALYSIS ISOME 7 TIC DRAWING - 47W600-(200 Series, See Below)

INSULATION / MODE -

ANALYSIS PROBLEM

.WMBER 79-14 ISO ISSUED?

UNIT ACCESSIBILITY N1-132-1R 260 Y

1 A

N1-232-1R 262 Y

2 A

N1-332-1R 261 Y

3 A

ORIGINAL ISOMEUIC - None ORIGINAL LOAD TABLES'- None ORIGINAL SUPPORT DETAILS - 47W600-ISS f.ff5J ORIGINAL HANGER LOCATION DRAWING - 47W600-116

..:c ESTIMATED SUPPORTS MJIT 1 - 41 UNIT 2 - 41 WiIT 3 - 41 1

i

'+

.Y-2 C.2S ong _ ;;3ng

(

-

ML20147E392

Contents

Text

Title:

5.0 REFERENCES

References:

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ML20147E392

Text

Title:

5.0 REFERENCES

References:

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