ML19207B871

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Rept NSP-37-005,Revision 1, IE Bulletin 79-14, Safety-Related Piping Sys Insp Plan,Monticello Nuclear Generating Plant
ML19207B871
Person / Time
Site: Monticello, Quad Cities  
Issue date: 08/30/1979
From: Mcwilliams D, Vogel T
NUTECH ENGINEERS, INC.
To:
Shared Package
ML112900902 List:
References
NSP-37-005, NSP-37-5, NUDOCS 7909050452
Download: ML19207B871 (100)


Text

.

NSP-37-005 Revision 1 August 30, 1979 30.0237.0018 IE BULLETIN 79-14 SAFETY-RELATED PIPING SYSTEMS INSPECTION PLAN MONTICELLO NUCLEAR GENERATING PLANT Prepared for:

Northern States Power Company Prepared by:

Nuclear Technology, Inc.

Prepared by:

Issued by:

} lf /?? W A. B.Hig[idbotham, P D.f.McWilliams,P.E.

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iii nutech NSP-37-005 Revision 1 LIST 0F TABLES Page TABLE 2.1 PIPING SYSTEMS TO BE CONSIDERED 2-3 TABLE 3.1 INSPECTION DATA. 3-4 TABLE 3.2 INSPECTION CORRELATION TOLERANCES 3-5 TABLE B.1 BECHTEL DOCUMENT LIST B-7 TABLE B.2 NAVC0 DOCUMENT LIST. B-11 TABLE B.3 GE DOCUMENT LIST B-15 LIST 0F FIGURES FIGURE 4.1 NONCONFORMANCF REPORT. 4-4 Y$A000* iV nutech NSP-37-005 Revision 1

1.0 INTRODUCTION

Recently, the United States Nuclear Regulatory Commission (NRC) identified a series of generic issues which could potentially cause the seismic analysis of safety-related piping systems to yield inaccurate results.

One of these issues involves the correlation of the as-built piping configuration to the information used for the seismic anal-ysis of the piping systems.

Due to this concern, the NRC published IE Bulletin 79-14 (Reference 1), and the subsequent supplement to the Bulletin (Reference 5) which require that an inspection be conducted to verify that the input information for the seismic analysis of safety-related piping systems reflect as-built configurations.

Further, the Bulletin requires that, where deviations from seismic analysis input information are found, the licensee must consider the need tc reevaluate the seismic analyses to the as-built configuration or modify the hardware.

This report describes the inspection to be conducted on the Seismic Category I and safety-relateu piping systems at Northern States Power Company's Monticello Nuclear Generating Plant in response to IE Bulletin 79-14.

The inspection will compare the as-built configuration to the information which is required for the seismic analysis of 014179 nutech 1-1

NSP-37-005 the piping, e.g.,

piping rize and wall thickness, piping configuration geometry, valve locations, valve operator orientations, and support locations, and type of support.

The inspection covers the Seismic Category I and safety-related piping systems defined in Section 2.0.

Resolution of identified discrepancies will consist of the following three approaches as allowed by the one Bulletin:

1.

An engineering evaluation of the discrepancies to show the original analyses are still valid.

2.

A reanalysis of the as-built configuration, or 3.

Modification of hardware to comply with the input information for the seismic analysis.

The final resolution of all discrepancies will be documented in a final report which will confirm that the as-built piping configuration is in conformance with the require-ments of the Final Safety Analysis Report (Reference 2) for the plant.

3111S0

~2 nutech

NSP-37-005 2.0 APPLICABLE SYSTEMS AND REPORTING SCHEDULE NUTECH, with support from Northern States Power Company (NSP) and Bechtel Power Corporation (Bechtel), will conduct an inspection of the safety-related piping systems for the Monticello Nuclear Generating Plant.

The purpose of the inspection is to compare the as-built piping configurations to the information used as input to the piping seismic analyses.

Any discrepancies found during the inspection will be resolved as described in Section 4.0.

All work associated with the inspection will be in accordance with the requirements of IE Bulletin 79-14.

The piping systems to be inspected consist of all Seismic Category I systems which were dynamically analyzed by computer and all safety-related systems with outside diameters of 2 -inches or greater.

The list of the Seismic Category I and safety-related systems to be considered is given in Table 2.1 along with the applicable line segments and isometric drawing numbers as available at this point in time.

The inspection of the piping systems will be conducted in two phases.

The Phase 1 inspection will cover, as a minimum, one system in each set of redundang normally accessible systems and all non-redundant accessible systems where accessible systems are defined to be those systems located e a4 o,,k k.

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nutech 2-1

NSP-37-005 Revision 1 in areas of the plant which can be entered during reactor operation.

The remaining redundant systems and the inaccessible systems will be inspected in Phase 2.

The inspection phase in which each line segment is to be in-spected is provided in Table 2.1.

The Phase 1 inspections are to be completed and results reported to the NRC on or before September 21, 1979.

The results of the inspections of the Phase 2 piping systems will be reported on or before October 8, 1979, for the accessible systems and October 30, 1979, for the inaccessible piping.

3I4103 nutech 2-:

NSP-3'-005 Revision 1 TABLE 2.1 PIPING SYSTEMS TO BE CONSIDERED APPLICABLE REFERENCL INSPECTION SYSTEM LINE.

^ '-

SEGMi.NIS DRAWING NUMBER PRIMARY CP1-18HE FIELD RUN ---

CONTAINMENT AND CP2-18HE 1

CP3-18HE 1

NO DRAWINGS.

ATMOSPHERIC CP4A-20HE y

CP4B-20HE 1

CONTROL CP4-20HE 1

CP5-18HE 1

TW12-8GE, HE 1

TW13-2 GE, HE 6425, 6354 1

TW6-12HE 6350

.1 CORE TW7-10GE 5815, 6400 1, 2 TW7-8ED, EF 5815, 6400 1, 2 TW8-8GE, HE 6400, 6353 1

SPRAY TW9-2hGE, HE 6411, 6354 1

TW10-12HE 6350 1

TWil-10GE 6405 1

TW11-8ED, EF 6405 1

C16-14HE 6402 1

PS18-8ED E 33 1, 2 RS2-18HE 6349 1

RS2-16HE 6349 1

RS2-20HE 6349 1

SC16-8ED 6351 1

HPCI SC16 - 811B 6351 1

TW1-14HE 5458 1

TW3-12ED 5458, 5466, 6414 1 (panial 2)

TW4-4ED, HE 5466 1

V52-16HE 6349, 5463 1

RV46-2hHE 1

PS17-3ED 6417 1 (Partial 2)

RCIC RS3-8HE 6349 1

TW5-6HE 5462, 6415 1

nutech 23 am:sa

NSP-37-005 Revision 1 TABLE 2.1 (Continued)

PIPING SYSTEMS TO BE CONSIDERED APPLICABLE REFE RENCE INSPECTION SYSTEM LINE PHASE SEGMENTS DRAWING NUMBER TW20-16DB,DC 6348,5821 2

TW20-18DC' 2

TW21-3HE 6425,6353 2

TW22-14GE 6347 2

TW23-12GE 6425,6353 2

TW23-10GE 6425,6353 2

TW24-12GE,HE 2

TW25-4GE,HE 2

TW27-20HE 6347 2

TW28-20HE 1

TW30-14GE 5467,5821,6400 1

TW30-16GE,DB 1

TW14A-18HE (Valve)6347 2

2 TW14A-20HE (Valve) ""

TW14B-18HE 1

TW!4B-20HE 1

TW15-14HE 2

TW17-14HE 2

TW19-10GE 2

RHR TW19-14GE 2

TW16-14HE 6347 1

TW18-14HE 6347 1

TW29-10GE 6425,5465 1

TW29-14GE 6425,5465 1

TW20-14GE 6348,5821 2

TW20-16GE 2

TW30-16DB,DC 5467,5821,6400 2

TW30-18DC 2

TW31-3HE 1

TW33-12GE 5467,6411,6401 1

TW33-10GE 1

TW34-12GE 6411 1

TW34-10HE 1

TW35-4GE,HE 1

TW3C.-4GE,HD 1,2 TW37-4GE,HC 1,2 REW10- 18EF,ED,HE 2,2,1 (partial 2)

REW11-8HE 1 (Partial 2)-

FPW12-8GE 1

SW9-8GE 1 (partial 2)

D82-3"HE SK-L-285 1

D8 3-3 "HB 1

D84-3GE,HB SK-L-285 1

RV54-4"HB 1

RV55-4"HB 1

SC10-3"HB 6425 1

SC29-3"HB 6425 1

Flu OCh 2-4 gg I

NSP-3~-Ou5 Revision 1 TABLE 2.1 (Continued)

PIPING SYSTEstS TO BE CONSIDERED APPLICABLE REFERENCE INSPECTION SYS1EM LINE PHAS~L

_ SEGMENTS DrtAWI NG NUMBER SW9-12-GF 545.2,6342,6429,6422 1

SW9-18-GF 1

SW9-16-GF 1

RHR SW9-18 -GF,GE 1

SERVICE SW11-16GF 1

WATER SW10-12GF 5451,5460,6424,6429 2

SW10-18GF 2

SW10-16GF 2

SW12-16GF 6346 2

SW57-36GF 1

SW58-16GF 1

SW57-18GF 1

1 SW58-18GF SW13-4HF 6401,6431 1

1 SW30A-3HF 6446,6431 2

SW25-4HF 6401,6431 2

EMERGENCY SW30B-3HF 6446,6431 SERVICE SW21-4HF 6431,6447 1,2 WATER SW27-3HF 6420,6443,5447 1,2 SW59-4HF 1

REACTOR REW3-4EF 6433 2

WATER REW3-4ED (partial 2)

CLEANUP REW6-3DB 6423 2

2 REW6-3ED STANDBY CH1-2 1/2HS 6440 1

s LIQUID CONTROL CONTROL CRD13 A-4DB 6451 1

ROD CRD13B-4DB 6451 1

1 DRIVE CRD14A-6DB CRD14B-6DB 6451 1

1 CRD15A-4DB CRD15B-4DB 6451 1

CRD16A-6DB M-274 1

CRD16B-6DB M-249 1

CRD18-12DB M-234 1

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NSP-3

-.J3 Revision 1 TABLE 2.1 (Concluded)_

PIPING SYSTEMS TO BE CONSIDERED APPLICABLE REFERENCE INSPECTION SYSTEM LINE PHASt SEGMENTS DRAWING NUMBER OFF OG27-18HC 1

GAS FEEDWATER FW2A-14DE,ED 6426 2

FW2B-14DE,ED 6427 2

FW2A-10ED 6426 2

FW2B-10ED 6427 2

FW5-4ED 6404 2

PRIMARY PS1-18ED 6407 2

REACTOR PS2-18ED 6408 2

STEAM PS3-18ED 6409 2

PS4-18ED 6410 2

PS15-3ED 6416 2

REW32-22"GE 2

REW13A-28"GE 2

REW13B-28"GE 2

REW14-12"GE 2

REACTOR REU15-12"GE 161F277 2

RECIRCULATION REW16-12"GE 2

REW17-12"GE 6

2 REW18-12 "GE 9

REW19-12"GE 729E909

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REW20-12"GE 2

REW21-12"GE 2

REW22-12"GE 2

REW23-12"GE 2

REW24-4"GE 2

REW25-4"GE 2

REW26-4"GE 2

REW27-4"GE 2

3 M1.M nutech 2-6 t

NSP-37-005

3.0 DESCRIPTION

OF INSPECTION The actual inspection consists of three separate tasks.

(1) an as-built inspection of the piping systems at the plant site, (2) a compilation of the input data for the piping analyses, and (3) a correlation of the results from Tasks 1 and 2 above to show conformance/nonconfor-mance between the installed and analyzed piping.

The details associated with each task are described in the following sections.

3.1 As-Built Inspection NUTECH, wi'h support from NSP, is responsible for completing the as-buitt inspection of the piping systems.

The inspection will consist of measuring and recording physical dimensions and hardware information in enough detail to allow a complete comparison with the analysis input data.

The actual information to be gathered at the site and the methods used to obtain the data are provided in Table 3.1.

Prior to the inspection, data books will be prepared by NUTECH for each system.

A sample data book is provided in Appendix A.

As can be seen, this book specifies the dimensions and other inforn.ation to be gathered at the site.

The information contained in the data books is DL* : n 1 3

.v a nutech 31

NSp-37-005 based on the drawings listed in Table 2.1.

Additional sources of information relating to the piping systems and specific data for each source are provided in Appendix B.

The data book provides a location for signatures of the inspection team members and for the approval of the NUTECH site Proj ect Engineer, all of which are required to complete the inspection.

The work copies of the data books will be maintained at the site until completion of the inspection.

The data recorded in the work copies will be transcribed to the NUTECH office copy which will be on file at the NUTECH office in San Jose, California, and will be the basis for the work described in Section 3.3.

3.2 Compilation of Analysis Input Data Bechtel is responsible for compilation of the input data for the analysis of the piping systems.

This work effort will consist of organizing dimensions and hardware infor-mation used in the piping stress analysis (see Table 3.1) in a form easily comparable to the informr. tion obtained from the as-built inspection and recorded in the data books.

All information will be signed off and transmitted to NUTECH in accordance with approved quality assurance programs.

3111.50 nutech 3-2

NSP-37-005 Revision 1 3.3 Correlation of As-Built and Analytical Data NUTECH is responsible for correlating the results of the inspections described in Sections 3.1 and 3.2, and identifying any nonconformance which is determined.

The as-built data and the analytical data will be in conformance so long as the differences remain within the tolerances specified in Table 3.2.

These tolerances, while allowing for some deviation, are sufficiently restrictive to ensure system operability under specified earthquake loadings.

Any measurement which exceeds the specified tolerance limit will be identified as a nonconformance and will be evaluated in accordance with the requirements of Section 4.0.

In addition, any abnormal conditions which are found at the time of the site inspection will be reported immediately to NSP via the nonconformance report form provided on Page 4-4 These would include conditions such as nonfunctioning supports, e.g., damaged supports or improperly installed supports, and obvious discrepancies in piping configuration.

O1$i89 nutech 3-3

NSP-37-005 Ec s i t in: 1 TABLE 3.1 INSPECTION DATA TYPE OF METHOD OF FIELD VERIFICATION IF DATA VERIFICATION OTHER THAN FIELD I. Piping Data a.

Size Tape Measurement of OD b.

Wall Thickness Ultrasonic Digital Thickness Gage 2) c.

Configuration Tape Measurement of Len ths d.

Branch Connec-Visual Cornparison with Fab awings tion e.

Material N/A Piping Specification JI. Insulation Thickness Tape Measurement of Thickness Ill. In-Line Eqpt, a.

Valves 1.

Location Tape Measurement of Pipe Length (2) 2.

Operator Visual Inspection Orientati7n

3. Weight N/A Vendor / Vendor Dvg.

4.

Center of N/A Vendor Drawi~2/

Gravity Independen: Calc.

b. Other Large Equipment Tape Measurement of Pipe Length (2) 1.

Location 2.

Weight N/A V e n d o r / V e r. d o r Dvg.

3. Center of N/A Vendor Drawing /

Gravity Independent Cale.

IV, Supports Tape Measurement of Pipe Length (2) a.

Location b.

Type Visual Comparison with Fab.

Drawing.

c. Anchorage Tape Measurement of Diameter of Bolt or Weld Thickness.

d.

Orientation Visual Inspection e.

Size or Load Visual Comparison Capacity

f. Design and Visual Comparison Assembly De-tails.

V.

Clearwce

( 2) a.

Floor or Wal1 Visual Inspection Penetrations.

( 2)

b. Directional Visual Inspection Changes NOTE 1.

For insulated piping, data to be obtained by removing i n s u l a t i o r. and iroviding direct access to the syrtem.

NOTE 2:

Requirer determination of approximate pipe temperature

(+_ 50F ).

3t nutech os4 - un u.s: k k u. -

NSP-37-005 E e '. i s i o n 1 TABLE 3.2 I

INSPECTION CORRELATION TOLERANCES TYPE OF DATA TOLERANCE I. Piping Data 5% of OD

a. Size (Outside Diameter)

+

12% of nominal thickness

b. Wall Thickness

+

c.

Configuration Eax of 5 % of straight run length, 6" or 1 OD

d. Branch Connection Same type as piping spec.
e. Material Same type as piping spec.

II. Insulation

a. Type Same type as piping spec.
b. Thickness

+ 20% of piping spec.

III. In-Line Equipment a.

Valves 1.

Location Max of ! 5% of straight run length, 6" or 1 OD

2. Operator Orientation t 15 for operator angle
3. Weight

+ 10% of total weight

4. Center of Gravity

[ 10% of distance

b. Other Large Equipment 1.

Location Max of 5% straight run length, 6" or 1 OD

2. Weight

+ 10% of total wei ht 6

3. Center of Gravity

[ 10% of distance IV. Supports a.

Location 6" for pipe sizes < L" e pipe diameters for pipe size >4" but

< 12" 24" for pipe size > 12"

'o. lype Same type as desigt documents

c. Anchorage Same as design drawings 5* for vertical supports
d. Orientation

+

I 15 for remaining supports e.

Size or Load Capacity Same size or load capacity or larger than indicated on design drawings.

f.

Design and Assembly Same as design drawings Details V.

Clearances

a. Wall Penetration 1/8" mininue b.

Directional Changes Visually ensure no evidence of contact with adjacent items.

1.

Based on information developed and supplied by Bechtel (References 3 & 6).

3-5 3.: M.u.

nutech

NSP-37-005 Revision 1 4.0 REPORTING AND RESOLUTION OF NONCONFORMANCES NUTECH is responsible for resolution of all nonconformances subject to NSP review and approval.

In resolving each identified nonconformance, the following approach is to be taken:

1. An engineering evaluation will be made of the nonconformance to determine if the nonconformance might impair the operability of the system.

This evaluation will be performed at two levels.

The first level consists of applying engineering judgment to the nonconformance to obtain an immediate, i.e., within two (2) days, evaluation of the impact of the nonconformance on system operability.

The second-level evaluation will be made within thirty (30) days and consists of an analytical evaluation of the discrepancy.

This evaluation may require the same degree of sophistication as was utilized in the original seismic analyses or a less rigorous analysis technique may be adequate for resolution.

If it is determined at either level of the evaluation that system operability is impaired, a nonconformance report form, as shown on Page 4-4, must be completed and reported to NSP immediately to ensure timely reporting to the NRC in accordance with technical specification requirements.

SJnm nutech 4_1 I

NSP-37-005 Revision 1

2. An additional evaluation of the nonconformance will be made to determine if the analyses described in the FSAR are no longer conservative.

Where it is determined that the original analyses are conservative, no further action is required.

However, if the original analyses are found to be unconservative, then additional action is necessary and will consist of either of the following:

a.

Reanalysis of the piping system to as-built conditions will be done in cases where the nonconformances do not warrant hardware modifications.

The piping system will be reanalyzed to the as-built conditions and the design requirements given in the piping system design specification.

A revised stress report and revised drawings, reflecting the as-built conditions, will be issued to document the acceptability of the nonconformance.

b.

Installation or modification of hardware to comply with the original stress analysis will be done in cases where this approach is deemed appropriate.

Where modifications are made to the hardware, revised drawings and stress reports will be issued to document the changes.

OMS 3 nutech 42 t

NSP-37-005 Revision 1 Additional documentation in the form of summary reports will be prepared as described in the following section.

4-3 o,u.. : ua. nutech s

NSP-37-005 Revision 1 FIGURE 4.1 NONCONFORMANCE REPORT SYSTEM NONCONFORMANCE NO.

DESCRIPTION OF NONCONFORMANCT-PROPOSED RESOLUTION OF NONCONFORMANCE:

ORIGINATL,. J.

CHECKED BY<.

APPROVED BY DATE:

CORRECTIVE ACTION TAKEN:

ACTION TAKEN BY:

DATE:

PLANT COORDINATOR PLANT SUPERINTENDENT, DATE ENGINEERING / RADIATION PROTECTION 4-4 nutech

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NSP-37-005 Revision 1 5.0 DOCUMENTATION The following items will be developed during the course of the inspection program.

Together with this document they form the complete documentation for the program:

Data books for recording the as-built condition of each piping system.

Isometric drawings showing all data utilized in the original piping analyses.

Nonconformance reports for each non-conformance that is determined during the inspection program to impair system operability.

Design or stress reports for any reanalysis ':hich is performed to demonstrate acceptability of reported nonconformances.

Revised drawings to reflect actual as-built conditions including any system modifications that may be required.

A final suumary report to be provided to tha NRC which summarizes the results of the inspections and describes the resolution for the nonconformances that were identified during the inspections.

nutech 5-1 "jj liih,

NSP-37-005 Revision 1

6.0 REFERENCES

1.

IE Bulletin 79-14, " Seismic Analysis for As-Built Safety-Related Piping Systems,"

Original Issue dated July 2, 1979, and Revision 1, dated July lb, 19'9.

2.

MONTICELLO NUCLEAR GENERATING PLANT, MONTICELLO, FINAL SAFETY ANALYSIS REPORT, Northern States Power Company, Minneapolis, Minnesota.

3.

Letter from C.

B. Hogg to D. Anthony, dated July 24, 1979; Subject, " Job 10040, Monticello Nuclear Generating Plant Unit 1, Northern States Power Company, NRC IE Bulletin 79-14, As-Built lolerances."

4.

Letter from C, B.

Hogg to D. Anthony, dated July 30, 1979; Subject, " Job 10040, Monticello Nuclear Generating Plant Unit 1, Northern States Power Company, NRC IE Bulletin 79-14, Response to Item 1."

5.

Supplement to IE Bulletin 79-14, " Seismic Analysis for As-Built Safety-Related Piping Systems," dated August 15, 1979.

6.

Letter from C.

B. Hogg to D. Anthony, dated August 8, 1979; Subject, " Job 10040, Monticello Nuclear Generating Plant Unit 1, Neithern States Power Company,.4RC IE Bulletin 79-14 Revisednutech

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As-Built Tolerances."

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NSP-37-005

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File No Owner Northern State. Power Company Client Northern States Power Company CONTROLLED COPY NO.

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Prepared By/Date Checked By/Date

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nutech San Jose, California 51 nticell Nuclear Generating Plant File No 30. 0 2 3 7 Project Owner Northern States Power Company Chen:

Northern States Power Company gugyEl yQIEE n,

,j.,,

ll 8".* k Revision Page P epared By/Date of Checked By/Date

NSP-37-005 AEEEEE11 a

SUPPORTING DOCUMENTATION c4 : - o 3. 4.

. w >..-.

nutech B-1

APPENDIX B NSP-37-005 SUPPORTING DOCUMENTATION The data utilized for the inspection plan is contained in various documents developed by Bechtel, GE, and National Valve and Manufac-turing Company (NAVCO).

A general description of the data provided in each type of document is given in the following pages.

Specific document information, i.e.,

document number, revision, date of revision, and title, is listed in Tables B.1 through B.3 for the Bechtel, NAVCO, and GE supplied items, respectively.

BECHTEL DOCUMENTS 1.

PIPING AND INSTRUMENTATION DIAGRAMS (P6ID's)

A schematic representation of the piping, process control and instrumentation for a specific mechanical system and shows the functional relationship among the various components.

A PSID serves as the primary record of system requirements for piping, duct work, valves, dampers, instruments and related equipment.

The following items are schematically represented on PSID's.

a.

Mechanical equipment b.

All valves and dampers, including vent and drain valves, except instrument valves and instrument take off root valves.

c.

Local and remote instruments in sufficient detail to delineate the function (s) of the instrumentation and its interface with the process.

d.

Piping and duct work Piping and ducts Vent and drain (including valves) nutech B-2

,4. - k W.o D

.Le

NSP-37-005 Special fittings Sampling line Permanent startup and flushing connections c.

Information included Instrument designations Equipment names and number Piping identification Duct work identification Valve identification and size, where different from line Direction of flow Interfaces for line and duct class change Interconnection reference including grid references Identification of components furnished by others.

2.

PIPING AREA DRAWINGS These are scaled (1/4 in = 1 ft) drawings dimensional'.. representing all mechanical equipment and piping 2-1/2 inches and 1.rger.

The designation " piping" includes pipe, fittings (elbows, tees, flanges, reducers, etc.), valves, headers, expansion joints, flow no::les and other components in the piping system.

Valve orientation is also shown.

3.

LINE DESIGNATION TABLES The line designation tables provide a single source document for use in defining the requirements noted below for each process piping line in the plant.

a.

Line identification including pipe site, c2 ass ano line number nutech B-3 311213

NSP-37-005 b.

Line description c.

Design / ratings in pressure and temperatures d.

PGID number e.

Seismic Category f.

Insulation Class 4.

PIPING CLASS SHEETS The piping class sheets define the characteristics of unique material classes within the piping system.

The information con-tained on the piping class sheets is:

a.

Class - Classes are designated by a two letter code.

The first letter designates the primary valve and flange rating; and the second letter the type of material.

b.

Pipe - the pipe material specification is called out for all applicable sizes of pipe for the applicable class sheet.

Wall thickness for all sizes are shown.

c.

Fittings - The fitting material specification is specified, along with the type of acceptable weld connection.

d.

Flanges - The flange material specification is called out and also the type of flange to pipe joint and style of flange face.

c.

Gaskets - For all applicable sizes, the recommended gasket material is specified.

f.

Bolting - The bolt and ssociated nut material are specified.

g.

Valves - The valve rating, type of end connection, and applicable valve type are specified.

8~4 nutech S m le

NSP-3 -005 h.

Joints - The applicable drawing showing the weld end preparation and weld end transition is referenced.

i.

Branch connection - The drawing of acceptable branch connections is included.

5.

INSULATION CLASSIFICATION AND THICKNESS This is a tabulation of the insulation thickness versus pipe size for different types of insulation class.

6.

STRESS IS0 METRICS These were sketches prepared by Bechtel or subcontractor to stress analyze the piping system.

They were based on the area drawings.

NAVC0 DOCUMENTS 1.

FABRICATION ISOMETRICS These are isometric presentations of the piping system in the configuration at the plant.

These isometrics were primarily prepared by NAVC0 (pipe fabricator at Monticello) and were used for fabrication and construc tion.

The isometrics were prepared from the Bechtel area drawinrs described above.

GE DOCUMENTS 1.

PIPING AND PIPING SUPPORT DRANINGS These are drawings which provide the piping data utilized in the analysis of the Reactor Recirculation System.

The information consists of the piping configuration, pipe size, and pipe fittings.

o,, cv 1.4 )

di.'s 4.

nutech 8-5 I

NSP-37-005 In addition, the location, direction, type, and size or rating of the piping supports are also provided in these drawings.

2.

DATA SHEET This document lists the material and wall thickness requirements for the Reactor Recirculation System piping.

nutech B-6 o,,,,l k) e J A, ' 1 *'..e

1 A Bl.1 Il,1 Did ilTLL I)OCUMEN'I I.1 S1

_ _ _, _ _ _ _ _ _ _ _ _ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _.l l

DRAhlNG NUMBLP TYPl.

BEtlllLL NSP nn pale T I T I.1:.

l j

M-100 Nil-36032 3

6/05/72 PTl Diagram-Legend i

M-102 Nil-36 0 3 3 I

3/28/79 Main Steam M-106 Nil-36037 I:

4/05/79 Condensate T, Feedwater, Sheet 2 M-108 Nil-36 0 39 1.

4/09/79 Condensate f, Demineralized Water Storage System l

Piping M-ll2 Nil-366 6 4 B

7/03/79 R. II. R.

f, limergency Se rvice Wat er Sys t em M-115 Nil-36241 J

5/02/78 Nuclear Boiler System M-116 Nil-36242 I

3/05/79 Reactor Vessel Instrumentation Instr.

M-ll7 Nil-36243 li 6/05/78 Reactor Recirculation System M-ll8 Nil-36 2 4 4 F

5/20/79 Control Rod liydraulic System, Sheet 1 Diagrams M-Il9 Nil-36 2 4 5 B

7/03/79 Control Rod Ilydraulic System, Sheet 2 M-120 Nil-36 2 4 6 D

7/28/78 Residual IIcat Removal System, Sheet I tn M-121 Nil-36 2 4 7 F

7/28/78 Residual lle a t Femeval System, Sheet 2 y

M-122 Nil-36 2 4 8 B

7/20/77 Core Spray System M-123 NII-36249 E

5/25/78 liigh Pressure Coalar.t Injection System, Sheet 1 M-124 Nil-36250 C

12/03/76 liigh Pressure Coolant Injection System, Sheet 2 M-125 Nil-36251 D

11/17/76 Reactor Core Isolation Cooling System, Sheet 1 M-126 Nil-36252 C

11/17/76 Reactor Core Isolation Cooling System, Sheet 2 M-127 Nil-36253 E

10/05/78 Standby 1.iquid Control System M-128 Nil-36254 j

1 1/13/78 Reactor Water C anup System

~3 M-129 Nil-36255 C

8/14/75 Reactor Water Filter-Demin. System u

g M-130 Nil-46162 K

7/17/78 Primary Containment Ni t rogen Control Sys tem M-133 Nil-36 0 51 E

2/22/79 Diesel Oil System g

p.,

M-142 Nil-3615 9 D

8/14/75 Off-Gas System m

g b

M-143 Nil-36258 I:

3/05/76 Primary Containment Atmosphere Control 7

System y

M-145 Nil-36 8 81 B

8/16/72 Standby Gas Treatment System FF,ID M-811 Nil-3666 5 1

2/04/77 Service Water System - Intake Structure (DO7

TABLE B.1 (Continued)

BliCilTlil. DOCUMENT 1.IST DRAWING NUMBER TYPl.

HEClll EL NSP REY DATF TITI.F M-202 NF-36583 12 3/28/73 Plan Below El. 920'-0" Turbine Bldg. Area 1 M-203 NF-36584 14 3/28/73 Plan Between E1.920'-0"4 E1.930'-0"

'3IPl"E M-204 NF-36585 12 3/29/73 Plan at E1. 930'-0" f E1.931'-0" i

Area M-205 NF-36586 7

2/12/71 Operating Floor Plan at El. 951'-0" M-206 NF-36587 10 3/30/73 Section A-A Drawings M-207 NF-36588 12 2/12/71 Section B-B M-208 NF-36589 12 2/12/71 Section C-C M-209 NF-36590 12 4/07/73 Section D-D M-210 NF-36591 8

2/12/71 Section E-E M-211 NF-36592 7

2/12/71 Section F-F M-217 NF-36593 14 2/12/71 Plan Below El. 920'-0" Turbine Bldg. Area 2 M-218 NF-36594 13 4/7/73 Plan Between El. 920'-0" GE1.930'-0" to M-219 NF-36595 A

7/11/78 Plan at El. 930'-0" f El. 931'-0" i

lo M-220 NF-36596 7

2/12/71 Operating Floor Plan at El. 951'-0" M-221 NF-36597 B

7/17/78 Section A-A M-222 NF-36598 8

2/12/71 Section B-B M-223 NF-36599 14 4/17/73 Section C-C M-224 NF-36600 9

4/10/73 Section D-D M-225 NF-36601 A

7/17/78 Section E-E M-226 NF-36602 12 2/12/71 Section F-F M-227 NF-36518 7

6/16/73 Section G-G, Areas 1 and 2 M-228 NF-36436 1

2/12/71 Supplementary Piping Details - Areas 1 and 2 M-229 NF-36517 8

4/07/73 Misc. Plans and Sections - Areas 1 and 2 m~'

M-232 NF-36371 8

6/05/72 Plan Below lil. 923'-0" Reactor Bldg. Area 3 M-233 NF-36372 11 11/12/73 Plan Below El. 935'-0" u

7 M-234 NF-36513 10 11/13/74 Plan Below El. 948'-0" M-235 NF-36504 C

2/10/78 Plan Below E1. 962'-6" 8

M-236 NF-36505 8

2/12/71 Plan Below El. 985'-6" m

(.3 M-237 NF-36506 5

2/12/71 Plan Below El. 1001'-2" g

y.s M-238 NF-36507 6

2/12/71 Plan Below El. 1027'-8" M-239 NF-36508 1

2/12/71 Plan at El. 1027'-8" i-j M-240 NF-36509 11 4/26/73 Section A-A (Col S Looking North) 6 M-241 NF-36510 11 5/29/74 Section B-B (Col. N 1ooking North) g "Z;

M-242 NF-36511 12 3/12/75 Section C-C (Col. M Looking North)

O M-243 NF-36373 9

2/12/71 Section D-D (Col. 9 Looking West) f

TABl.E B.1 (Continued)

Bl.t ill i 1. DUCliMi NT 1.l ST DRAlil.V NIJMPF.R 1

T TYPE ITCli t 1;' '- f NSP E!:V 1'ilT 1ITlI l

C""3 Reac t or P.liFg_. 3_r_e_a_ _.,_

a M-244 NF-36512 12 11/18/74 Section E-E (Col. 6 looking West)

M-245 NF-36374 11 4/23/73 Section F-F (Col. 3 looking East)

M-246 NF-36669 8

3/13/75 Plans f Sectiens-ll.P.C. I. Turbine Ptap Room O

Piping M-247 NI-36693 !

6 2/12/71 Area 3 Piping 1)wg. Misc. Sects. f. Details o Er l

M-248 NF-36752 4

2/12/7.1 Area 3 Standby Liquid Control System M-249 NF-36689 3

(No date) C.R.D. Ilydraulic Piping-Plan, Eiistside Below 952'-0" Area 7M Drawings M-250 NF-36690 1

2/12/71 C.R.D. Ilydraulic Piping-Inside Drywell 2

(Concluded)

M-251 NF-36602 1

2/12/71 C.R.D. liydraulic Piping-Sect. A-A Looking North M-264 NF-36759 4

2/12/71 Area 3 - R.II.R. Piping in Drywell M-267 NF-36811 1

2/12/71 Exh. Stack liuip. Area Plan View l

M-268 NF-36782 1

2/12/ 71 Area 3-Sects. A-A, B-B, D-D, F-F above El. 1001'2" to M-273 NF-36704 2

2/12/71 CRD llydraulic Piping Section B-B f lietails i

E l

M-274 NF-36707 3

(No date)

Plan P>elow Et,952 M-275 NF-36711 2

2/12/71 Section C-C M-296 NF-36852 0

2/12/71 Main Steam Piping in Tunnel - Area 3 M-621 nil-46118 0

11/12/09 Exhaust Stack Lines Detail M-801 NF-36379 8

2/12/71 Intake Structure Plan at EL919 M-802 NF-36439 3

2/12/71 at EL934 i'

M-823 NF-36378 8

2/12/71 Section A-A and B-B M-804 NF-36440 8

2/12/71 Section C-C, D-D and E-E M-805 NF-36441 3

2/12/71 Access Tunnel

(.O i

[-

s.-

c

5. 4 M-272 NF-362 71 11 8/04/78 Main Steam P.)

M-1000 NQ-59273 5

5/13/74 RV24A-10"-ilB E

H M-1001 NQ-59274 5

5/1 3/74 RV25A-10"-IIB O

lsometrics M-1002 NQ-59276 4

5/13/74 RV26A-10"-IIB o

M-1003 NQ-59277 4

5/13/74 RV27A-10" -llB Ei M-1007 NL-59281 1

5/28/74 Pipe Support RV24A M-1008 NL-60399 3

5/28/74 Pipe Support RV24 3

l C

Main Steam Equalizer lleader Drain to Condenser P-273 g

Main Steam Analizer lirain to CRW P-277 go I

r t_

TAllLli 11.1 (Concloded)

BIT.llTI 1. I)DCll:1ENT L I ST r


- - - 1 DRAWlNG NilllmR TYl'E fiLLitTl:1 NSP RI.V DATE T ITI I' F1-100 9 NL-60333 l 2

5/28/74 Pipe Supports RV25 bl-1010 NL-60337 2

5/28/74 Pipe Supports RV25A p '.P" h!-10ll NL-60339 2

5/28/74 Pipe Supports RV26 Supports bi-1012 NL-60336 2

5/28/74 Pipe Supports RV26A hi-1013 NL-60340 2

5/28/79 Pipe Supports RV27 Drawings 5/28/74 Pipe Supports RV27A ht-1014 NL-60335 3

bl-1016 NL-60334 1

I 6/06/74 Pipe Supports PSI, PS2, PS3 an l 154 b!-1018 lNL-60341 0

12/11/73 IIPCI Vent V52A-2" Pipe Support 8

P-274 blain Steam Outside Containment Support P-275 l

blain Steam Bypass Line Support to P-276 Supports for Isonetric P-273 P-278 l

Supports for Isanetric P-277 I

I i

I Other bl-40 l

5 11/12/69 Pipe Class Sheet Specification i

E""

Documents F1-15 9 i

Insulation Summary i

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_ _ _.. _. L _ _._ _ _j.

.___u___.._.

NSP-37-005 TABLE B.2 NAVC0 DOCUMENT LIST DRAWING NUMBER NAVC0 NSP REV DATE i'

5445 NX-13142-86 0

3/25/68 5446 NX-13142-87 2

9/11/69 5447 NX-13142-88 3

9/11/69 5448 NX-13142-89 3

9/11/69 5449 NX-13142-90 3

9/11/69 5450 NX-13142-91 2

3/2/70 5451 NX-13142-92 7

4/21/70 5452 NX-13142-93 7

4/22/70 5453 NX-13142-99 1

7/12/68 5454 NX-13142-94 2

10/9/68 5455 NX-13142-95 3

1/6/70 5456 NX-13142-96 4

10/10/69 5457 NX-13142-97 3

10/19/68 5458 NX-13142-100 1

8/21/68 5459 NX-13142-98 3

2/25/70 5464 NX-13142-101 0

8/5/68 5466 NX-13142-102 2

8/12/68 5467 NX-13142-103 2

9/12/68 5468 NX-13142-104 0

9/10/68 5470 NX-13142-105 0

9/13/68 5471 NX-13142-106 1

9/16/68 5814 NX-13142-85 1

12/31/68 5816 NX-13142-107 0

9/15/68 5818 NX-13142-108 0

3/4/69 6331 NX-1314 2 - 1 1

6/26/68 6332 NX-13142-2 3

7/22/70 6333 NX-13142-3 1

4/8/68 6334 NX-13142-4 0

3/25/68 6335 NX-13142-5 1

8/12/69 6336 NX-13142-6 5

3/2/70 nutech B-11 g,,v.,..,

m I

NSP-37-005 TABLE B.2 (Continued)

NAVC0 DOCUMENT LIST DRAWING NUMBER NAVC0 NSP REV DATE 6337 NX-13142-7 4

3/2/70 6338 NX-13142-8 1

6/11/68 6339 NX-13142-9 1

6/13/68 6340 NX-13142-10 1

6/13/68 6341 NX-13142-11 2x 6/24/68 6342 NX-13142-12 6

4/21/70 6343 NX-13142-13 2

5/7/69 6344 NX-13142-14 0

4/3/68 6345 NX-13142-15 12 3/20/70 6346 NX-13142-16 4

3/3/70 6347 NX-13142-17 12 12/15/70 6348 NX-13142-18 13 12/16/70 6349 NX-13142-19 9

12/16/70 6350 NX-13142-20 11 12/16/70 6351 NX-13132-21 5

8/7/70 6352 NX-13142-22 1

3/31/69 6353 NX-13142-23 6354 NX-13142-24 6355 NX-13142-25 2

12/10/68 6400 NX-13142-26 13 4/20/70 6401 NX-13142-27 5

4/7/70 6402 NX-13142-28 4

4/20/70 6403 NX-13142-29 4

6/23/69 6404 NX-13142 n

A 11/22/74 6405 NX-13142-31 10 3/12/70 6406 NX-13142-32 1

2/5/69 6407 NX-13142-33 A

3/24/79 6408 NX-13142-34 A

3/24/79 6409 NX-13142-35 A

3/24/79 6410 NX-13142-36 A

3/24/79 6411 NX-13142-37 13 5/25/70 nutech B-12 bis I,C.'.'.9,'

I

NSP-37-005 TABLE B.2 (Continued)

NAVC0 DOCUMENT LIST DRAWING NUMBER NAVC0 NSP REV DATE 6412 NX-13142-38 2

2/27/69 6413 NX-13142-39 2

3/3/69 6414 NX-13142-40 12 4/20/70 6415 NX-13142-41 5

12/18/70 6417 NX-13142-43 13 12/21/70 6418 NX-13142-44 2

3/7/69 6419 NX-13142-45 7

12/16/70 6420 NX-13142-46 6

3/3/70 6421 NX-13142-47 4

10/16/70 6422 NX-13142-48 7

6/2/70 6423 NX-13142-49 A

12/22/77 6424 L<-13142-50 7

4/22/70 6425 CX-13142-51 8

9/30/69 6426

>(-13142-52 A

4/7/78 6427 F(-13142-53 12 5/18/70 6428 F,-13142-54 10 12/9/69 6429 NX-13142-55 14 4/9/70 6431 NX-13142-57 9

4/24/70 6432 NX-13142-58 B

2/2/78 6433 NX-13142-59 15 10/15/70 6434 NX-13142-60 2

11/24/69 6435 NX-13142-61 3

11/14/69 6436 NX-13142-62 8

6/20/70 6437 NX-13142-63 1

2/26/69 6438 NX-13142-64 1

4/4/69 6439 N?:-1314 2 - 6 5 1

3/26/69 6440 NX-13142-66 8

12/18/69 6441 NX-13142-67 3

11/14/69 6442 NX-13142-68 2

6/23/69 6443 NX-13142-69 2

6/25/70 SLC R nutech B-13

NSP-37-005 TABLE 3.2 (Concluded)

NAVC0 DOCUMENT LIST D rah'I NG NtBBER NAVC0 NSP REV DATE 6444 NX-13142-70 2

6/23/69 6445 NX-13142-71 3

8/13/69 6446 NX-13142-72 8

4/14/70 6447 NX-13142-73 1

7/7/69 6448 NX-13142-74 1

6/16/69 6449 NX-13142-75 3

8/15/69 6450 NX-13142-76 1

6/12/69 6451 NX-13142-77 3

6/2/71 6452 NX-13142-78 2

2/19/70 6453 NX-13142-79 3

2/19/70 6454 NX-13142-80 1

6/16/69 6455 NX-13142-81 1

6/23/69 6456 NX-13142-82 1

6/23/69 6457 NX-13142-83 2

2/23/70 6458 NX-13142-84 2

2/23/70 311'1,'Jd rititeac:F1 B-14 I

TABLE B.3 GE DOCUMENT LISil "b'l TYPE REV DATE TITLE IB I 161F277 1

12/22/67 Vermont Yankee Recirculation I.oop Piping Drawing 729E909 0

08/05/67 Vermont Yankee Recirculation Loop Suspension Specification 21A2100AC 4

11/11/68 Recirculation Loop Piping Data Sheet 7

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