ML19242B411
| ML19242B411 | |
| Person / Time | |
|---|---|
| Site: | Point Beach  |
| Issue date: | 08/01/1979 |
| From: | Burstein S WISCONSIN ELECTRIC POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| NUDOCS 7908080475 | |
| Download: ML19242B411 (36) | |
Text
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O Wisconsin Electnc roata couran<
231 W MICHIGAN. P.O. B0: 2046. MILWAUKEE WI 53201 August 1, 1979 dr. J. G. /,eprier. Director Offica of Inspecticn and Enforcement Region III S. S. lWCl. EAR RESULtTORY CC?t!ISSICl 799 Roosevelt Road Glen illyn, Illimis 6C137 Jear Mr. .<eppler:
SOCKET .:0S, 50-266 AliD 50-331
- nSP0aSt To 1E. 50LLETId i9-14 POIhT TEACH aLCLEAR plani, ualis 1 MD 2 On July 2,1979, the Office of Nuclear Reactor Regulation issued IE Bulletin 79-14 which is entitlea, " Seismic Analyses for As-Built Safety-Related ?iping Systems". De bulletin requires that licensees verify that the seismic analysis perfomed for sa'ety-related piping systems appliu to the as-built configuration of the pi;:ing system. Revision i of this bulletin, issued on July 20, 1979, clarifies the application of the original tulletin requirenents to piping 21/2 inches in diameter and greater and to all Seisnic Category I piping which was dynamically analyzed by ccmputer.
Bulletin 79-14 requires three licensee responses wnich can be sumarized as follows:
- a. Within 30 days, submit a detailed listing of tne design basis for these systems and ider,tify the inspection elements for verifying acceptatility of installed piping systems.
- b. Within 60 days, submit a reDort of the inspections performed on normally accessible systems; and
- c. Within.120 days, submit a report of the inspections perfomed on the remaining systems.
This submittal constitutes Wisconsin Electric's first response to IE Bulletin 79-14. The enclosure to this letter presents the requested detailed listing of the design basis used for the safety related Mping systems.
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Mr. J. G. Keppler - Page Two t'Jgust 1, 1979 As you are aware, a substantial industry effort is presently onc;oing in ocerating plants to respond to iRC IE Eulletin 79-02. Also, in olcer operating plants such as the Point Beach liuclear Plant rany areas are act nort.:aily accessible except during extended unit cutages such as refuelings. Our inspection plan is to inspect all accessible piping as sacn as practicable and to inspect the piping systems inside the Unit 1 containment curir.. the Fall 1979 refueling. The piping systems inside the Unit 2 containment will te inspected during Qe Spring 1930 refueling anless a unit scutdown, during which teaningful inspections could be performed, occurs ecrlier. This plan should enable us to provide most of the requested infomation, except for the piping systems inride the Unit 2 containment, within the bulletin specified time intervalr.
We trust that you will f'nd cnis inspection plan satisfactory.
Very truly yours, r ) -
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Sol Burstein Executive Vice president Enclosure cc: Office of Inspection and Enforecaent Division of Reactor Operations Inspection Office of Huclear Reactor Regulation Attention: Mr. A. Schwencer 504 002
ENCLOSURE e
RESP 0 HSE TO NRC IE BULLETIN 79-14 August 1,1979 This enclosure provides Wisconsin Electric Power Company's first response to IE Bulletin No. 79-14 entitled, " Seismic Analyses for As-Built Safety-Relatec Piping Systems". This enclosure responds to Item 1 of the bulletin w;.ich is as follows:
- 1. Identify inspection elements to be used in verifying that the seismic analysis input information conforms to the actual configuraticn of safety-related systems. For each safety-related system, submit a list of design documents, including ti .le, identification number, revision, and date, which were suurces of input infonnation for the seismic analyses. /lso submit a description of the seismic analysis input infor ation which is contained in each document.
Identify svstems or portions of systems which are planned to be inspected during each sequential inspection identified in Items 2 and 3. Submit all of this information within 30 days of the date of this bulletin.
RESPONSE
The inspection elements that will be used tc verify conformance of the piping systerc.s will include plant plan drawings, pipe hanger and support drawings, valve drawings, and the stress isometric model sketches.
The inspections will be performed on a system basis to the maximum extent possille. Inspection documentation, containing the above elements, will be developed for each system to be inspected. The inspection will verify, or record the actual condition of all pertinent dimensions of the hanger and support locations as well as the piping geometry, pipe attachments, supports, and other pertinent information. Additional inspectio.n items will include verification of pipe ncminal size, piping dimensional lengths, existence of branch connections, insulation parameters, valve locations, valve type and mark numbers, valve operators if applicable, and additional piping system concentrated weights (such as flanges).
The piping lines that are to be inspected are identified in Appendix A. The listing in Appendix A identifies the nominal pipe diameter, denotes the accessibility and redundancy of the piping system, and the piping that is common to both ur its.
The Point Beach Nuclear Plant spent fuel pool cooling system is not included in the Appendix A listing. During the licensing of the first spent fuel storage ra;k modification for Point Beach Nuclear Plant (completed in 1975), Wisconsin Electric committed to modifying the spent fuel pool cooling system. The new cooling system was designed as an ASME Section IIi, Class 3 Seismic Category I system by Stone and Webster Engineering Corgaration.
Construction of the system was completed in early 1978 and the system has been appropriatoly "N" stamped. Attached is a Certificate of Conformance provided to Wisconsin Electric by the mechanical contractor for this plant modification.
All discrepancies between the design and "as-built" conditions have been resolved and there is adequate documentation to demonstrate the acceptability of this system.
The NRC safety evaluation report for the spent fuel pool cooling system was issued on April 18, 1978, and revised cooling system flow diagrams have been incorporated into the Point Beach Nuclear Plant Final Facility Description and Safety Analysis Report by Amencment No. 24.
Appendix B hereto provides a listing and description of the original design documentation for each of the piping lines identified in Appendix A.
Included in Appendix B are: -
- a generalized desc- tion of the type of design information -
contained in the esign documents a listing of applicable piping and pipe support drawings whicn provides the drawing number and title.
- a listing which identifies the specific design documentation applicable to each piping line contained in Appendix A. This preliminary listing will be ccmpleted and retransmitted with Wisconsia Electric's next submittal with respect to NRC IE Bulletin 79-14.
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10 May 1978 Wisconsi.n Electric Power Company 231 West Michigan Pilwaukee, Wisconsin 53201 .
CERTIFICATE OF CC:!F0FllA::CE The Phillips,.Getschow Company, hereby certifies, to the best of its knowledge, that the aork performed under Contract A-4'80Cl4 and described in Stone & Webster Specification P275B has purchased, fabricated, insta-led, adjusted and tested in compliance with the specification and all attendant drawings, codes and strad-ards or instructions authorized by the Client's engineering re-presentative.
Where, during the course o'. construction, this specification, drawings, codes and standards have been deviated frca, the Phillips, Getschow Company has, to the best of its ability, ach-
. ieved timely resolve of such deviations through the Client's engineering representative.
Additionally, we hereby certify that drawings and documentation provided the Client at the completion of the work contain actual "as-built" data and sufficient information to justify design in-
.cgrity and provide basis for reconciliation of design E.nd stress reports.
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v ary L. Marquardt Manager-Quality Assurance Phillips, Getschow Company I
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APPEtlDIX A POIfiT BEACH fiUCLEAR PLA:iT SEISMIC CATEGORY I LItiES FOR IriSPECTIO?! PER flRC IE BULLETIll 79-14 August 1, 1979 504 006
POINT BEACH SEISMIC CATEGORY I LINES FOR NRC IE BULLETIN 79-14 NOM. DIA. INSPECTION LINE NO. INCHES SERVICE TYPE
- CH-2502R-1 3 Charging Pump Disch. to Valves 186-289-290 NR-A 3 Charging Pump Disch. Crossover Line to NR-A Seal Injection Syst' , (up to 2 Inch piping)
-3 3 Charging Pump Disch. Valves 286-289-290 to NR-I&A Regenerative Heat Exchanger RC-250lR-1 3 Spray Line from Primary Loop to Pressurizer R-I
-2 4, 3 Relief Line from Pressurizer through PCV NR-I 430 and 431C
-3 4 Safety Valve Line from Pressurizer to R-I PCV 434 and 435
-5 6 Injection into Reactor Vessel R-I
-6 6 Hot leg Loop A Injection Line R-I -
-7" 10 Cold Leg Loop A Inject :n Line d
R-I
-8 10 Cold Leg Loop B Injection Line - R-I
-9 6 Hot Leg Loop B Injection Line (Stub only) NR-I
-12 3 Charging Line from CH-250lR-4 (Valve 295) NR-I to Loop A Cold Leg
-16 10 Residual Heat Removal Line to MOV 700 NR-!
RC-250lR-X 30 Primary Coolant System, Loop A including R-I connections;
-14 4 Drain 3 RTP manifold (flow into RCP) to Valve 560A RC-250lR-Y 30 Primary Coolant System, Loop B R-I
-14 4 Drain
-10 8 Stub for connections to Drain Tank (2") and Letdown Line (2")
-14 3 RTD manifold (flow into RCP) to Valve 560B RC-250lR-Z 10 Pressurizer Surge Line from Loop B to NR-I Pressurizer 504 00/
Page 1 of 6
fl0M.D I A. IflSPECTI0tl LIf;E !!0. IftCHES SERVICE TYPE
- SI-250lR-1 10 Accumulator (Valve 841) to Cold Leg R-I Loops A & B (thru Valves 842 and 867)
-2 10 Residual. Heat Exchanger Supply to Cold flR-I Leg Injection Line (from MOV 720)
-3 6 Hot Leg (Loop A & B) Injection Line from R-I 2x6 expander thru Valve 877
-4 6 Residual Heat Exchanger to Reactor Vessel R-I from MV 852A (recundant with R-5 line)
-5 6 Reactor Vessel Injection Line from MOV 8528 R-I
- Inspection type is defined as follows:
R - Redundant A - Accessible (outside containment) liR - flan-reduncant I - Inaccessible (inside containment)
- Indicates a piping line which is comt.,an to both Units 1 and 2.
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NOM. DIA. INSPECTION
~LINE NO. INCHES SERVICE _ TYPE
CH-250l R-4 3 Charging Line from Regenerative NR-I Heat Exchanger to Valve 295 SI-150lR-1 6, 4 Safety Injection Pump Disch. to Injection - R-A Line F.E. 924 and 925
-2 4 Safety Injection from F.E. 924 to Pipe R-I&A Reduction to ,ich diameter (redundant with R-3 line)
-3 4 Safety Injection Disch. from F.E. 925 to R-I&A Pipe Reduction to 2 inch diameter AC-60lR-1 10 From MOVs 851 A and B (Centainment Sump B) R-A to RHR suction (60lR-3)
-2 10, 8 Hot Leg Loop A from MOV-701 to Residual NR-I&A__
Heat Removal Pump Suction (R-3)
-3 10 Suction Lines to Residual Heat Removal Pump R-I&A Suction
-4 8 Residual Heat Removal Pump to Residual Heat R-A Exchanger including crosstie
-5 6 Bypass around Residual He. t Exchanger (from NR-A R-4 to R-6)
-6 10, 8, 6 Residual Heat Exchangc: discharge to Valve R-I&A 720 to loop B cold leg; to valve 742 (RWST); to MOV 871B (spray pumps)
SI-60lR-1 10 Refueling Water Storage Tank from MOV 856A R-A and B to Residual Heat Remcyal Pump Suction (to AC-60lR-3)
-2 6 From Residual Heat Removal System to Reactor R-I&A Vessel SIS Injection Line to MV 852A or B and valve 720 (redundant to AC-60lR-6)
CH-60lR-1 10, 3 Nonregenerative Heat Exchanger Pipe and NR-I&A Decay Pipe Inside Containment SI-30lR-1 6 Discharge from Containment Spray Pump to R-I&A Spray Nozzles AC-151R-10 4 Spent Fuel Pool Transfer Canal to and from NR-A Recirculation Pump 504 uG9 Page 2 cf 6
NOM. DIA. INSPECTION LINE t10. INCHES SERVICE TYPE
- CH-151R-1 4, 3 Volume Control Tank to Charging Pumps NR-A suction
-4 4, 3 Recirc. Pump Discnarge Back to Holdup Tanks N R- A
-8 3 In Letdown Piping - from valve 253 thru NR-I&A Deborating Demineralizers, thru reactor coolant fi ter (including bypass), and to Volume ;ntrol Tank
-23 8 Boric Acid Tanks to S.I. Pumps (only to R-A valve 827)
SI-151R-2 16, 12, 10 Suction from RWST to Safety Injection Pumps NR-A 6 R-A
-3 6 Suction from 151R-2 (RWST) to Containment R-A Spray Pumps
-4 10 Suction from 151R-2 (RWST) to Residual N R- A Heat Removal Pumps Upstream of MOVs 856 A and B
-5 6 Residual Heat Exchangers to Safety Injection R-A Pump Suction Downstream of Valves 857 A and B
-6 4 RWST to Charging Pump Suction Upstream of R-A LCV-ll2B
-7 8 Boric Acid Tanks to Safety Injection Pumps NR-A Suction Line - Downstream of Valves 827 A and B to 151R-2
-X 10 From Containment Sump B (Valve 850 A and B) R-I&A to MOVs 851 A and B (AC-60lR-1)
-23 4 Component Cooling Surge Tanks and Ho~ dup NR-A Tanks Relief Valve Discharge to Waste Holdup Tanks AC-152N-1 14, 10 Component Cooling Pump Discharge to R-A Component Cooling Heat Exch.
-2 14, 10 Component Cooling Wate: from Comp. Cooling R-A Heat Exch. to Comp. Cooling Water Supply Header (fi-3)
-3 14 Component Cooling Water Supply Header NR-A
-4 6, 4, 3 Comp. Cooling Water through Primary R-ISA Coolant Puma from Supply Header (U-3) to Return Header (N-7) } ('j [j (} { O Pa e 3 of 6
NOM. DIA. INSPECTION LINE NO. INCHES SERVICE _ TYPE
-7 14 Component Cooling Return Header to CCW NR-A Pump Suction (N-15)
-10 6 Comoonent Cooling Water through Non- NR-A regenerative Heat Exchangers (Back to N-7)
-11 6 Component Cooling Water through Boric NR-A Acid Evap. (Back to N-7)
-12 3 Component Cooling Water through Waste Evap. N R- A and Waste Gas Compressor (Back to N-7)
- -15 10 Return to Component Cooling Pump Suction R-A from N-7, and Unit 2 connection to Valve 722A
-16 4 Surge Line to Surge Tank (N-15 to tank) NR-A 0B-1 20, 16 Boiler Feedwater Pumps to Containment R-A Isolation Valves (CV 466 and 476) to EB-9; not Seismic Category I
-3 4, 1 Emergency FW from Pumps tc MOVs 4000 and R-A 4001 and to EB-10, and cross tie between P38A and B EB-1 30, 6 Main Steam from Steam Generator thru contain- R-I&A ment to Non-return check valve; including R. Valve Header and atmospheric discharge to CVs 2015 and 2016 EB-1 24 Main Steam Outside Containment to HP Turbine R-A Control Valves; not Seismic Category I
-8 3 Main Steam to Aux. FW Pump (from EB-1) NR-A
-9 16 Boiler FW from Cont. Isolation Valves R-I&A (see DR-1) to Steam Generators
-10 3 Emergency FW from DB-3, into Containment R-I&A to Main FW (ES-9)
- HB-19 30, 24, 16, Service Water Supply Header R-A 14, 8, 6
-29 22 Diesel Generator Exhaust inside Turbine R-A B.iilding only J G-4 10, 8, Aux. FW Pump Suction from Condensate R-A 6, 4 Storage Tanks Page 4 of 6 504 01
N0M. DIA. INSPECTION LINE NO. INCHES SERVICE TYPE *
- JB-2 20, 14 Service Water Return Header to Circulating R-A Water Discharge
- Gas Striocer System (S&W Cwg.12137-FM-6A)
CH-4-152 2-1/2 From Gas Stripper Trim Coolers to CH-18-152Q NR-A (Valve GW72AQ)
CH-18-152Q 2-1/2 Fron. CH-4-152 thru Valve VDW-15YZ to NR-A CHG-24-152Q CHG-24-152Q 3 Tie frcm CH-18-152Q to CH-151P,-8 from the NR-A Reactor Coolant Filter CH-21-152 Supply to Gas Stripper (HX-130A) NR-A CH-1-152 '
. From Gas Stripper A to G.S. Recirculating N R- A Pump (P-130A)
GR-28-152Q 3, 4 From Gas Stripper A to GR-29-152 NR-A GR-29-152 6, 4 From GR-28-152Q to WD-151R-23 (to Waste NR-A Holdup Tank, T-19)
The folicwing line nutters provide the duplicate piping runs (in order) for Loop B of this system which serves Unit 2.
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CH-ll-152 CH-19-152Q CHG-25-152Q CH-23-152 CH-8-152 GR-30-152Q GR-31-152 (ties into GR-29-152)
Additional equipment invo'.ied in the gaseous waste disposal system designed by Stone & Webster Engineering Corporation includes tne Cryogenic Gas Separation System (D&W Dwg.12137-FM-7A), steam supply for the evaporators, and service water for coeling.
While the cryogenic system design basis 's Seismic Category I, the piping is all 3/4-inch diameter or less.
The steam supply system (S&W dwg.12137-FM-8A) is not safety-related.
Auxiliary Coolant and Service Water Flow Diagram (S&W Dwg.12137-FM-9A)
SW-1-121 8 Service Water Supply (HB-19) to Blowdown NR-A Evaporator Overhead Concenser (HX-142)
SW-2-121 8 SW Discharge from HX-142 to JB-2 NR-A bU$ b$2 Page 5 of 6
NOM. DIA. INSPECTION
'LINE NO. INCHES SERVICE TYPE
- AC-1-121 6 Cooling Water Supply (from AC-152N-3) to Gas NR-A Stripper Equi, ent AC-2-121 6 Cooling Water Discnarge from Gas Stripper NR-A Equipment (to AC-152N-7)
These four pipelines were inspected ano c.oluated in April 1979 in response to NRC IE Bulletin 79-07; see Wisconsin Electri 's letter of May 2,1979. Accordingly, ne, action is required with respect to IE 'ulletin 79-14.
Condenser Air Removal Cecay System (S&W Dwg.12137-FM-10A)
This system is seismic category III (see FFDSAR, page 11.3-2) and no action is required with respect to IE Bulletin 79-14.
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APPEiiDIX B POIf4T BEACH liUCLEAR PLAtlT LISTI!1G OF ORIGI:lAL DESIG?l DOCU!tEriTATIO:1 APPLICABLE TO SEISMIC CATEGORY I SAFETY RELATED PIPI:iG SYSTEMS August 1, 1979
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POINT BEACH DOCUMENT DESCRIPTION
- 1. PIPING AND INSTRUMENTATION DIAGRAMS (P&ID'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 P&ID serves as the primary record of system requirements for piping, duet wort, valves, dampers, instruments and related equipment. The tollowing items are schematically represented on P&ID'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 o Piping and ductc o Vent and drain (including valves) o Special fittings o Sampling lines o Permanent startup and flushing connections
- e. InforLation included o Instrument designations o Equipment names and number o Piping identification o Duct work identification o Valve identification and size, where different from line o Direction of flow o Interfaces for line and duct class change o Interconnection references including grid references o Identification of components furnished by others.
- 2. PIPING AREA DRAWINGS These are scale (k in = 1 f t) drawing dimensionally representing all mechanical equipment and piping 2\ inches and larger. The designation " piping" includes pipe, fittings (elbows, tees, flanges, reducers, etc.), valves, headers, expansion joints, EIl/;
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c a Valve flow nozzles and other components in the piping system.
orientation is also shown.
- 3. PIPING CLASS SUIC1ARY for use in defining the This provides a single source document requirements noted below for each process piping line in the plant.
- a. Line icentification including class and line number
- b. Line description
- c. Design / service ratings it pressure and temperatures
- d. P&ID number
- e. Seismic category
- f. Insulation Class
- 4. PIPING CLASS SHEETS The pipir.g class sheets define the characteristics of uniquecon-The information material classes within the piping system.
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 is shown.
- c. Fittings - The fitting material specification is speci-fied, 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 flarge face.
- f. Bolting - The bolt and associated nut material are specified.
- g. Valves - The valve rating and applicable valve type is specified.
- h. Joints - The applicable drawing showing the weld .
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end preparation and weld end transition is referenced.
- i. Branch connection - The drawing of acceptable branch connections is included.
- 5. PIPIllG CLASS
SUMMARY
This provides a single source document for use in defining the requirements noted below for each process piping line in the plant.
- 1) Line identification including class and line number
- 2) Line description
- 3) Design / service ratings in pressure and temperatures
- 4) P&ID number
- 5) Seismic category
- 6) Insulation Classification and thickness
- 6. WESTINGHOUSE FLOW DIAGRAM These are flow diagrams of the NSSS piping system that are similar to the Bechtel P&ID's. Bechtel did not prepare P&ID's for the NSSS piping system but used the Westinghouse flow diagrams. The primary difference is that the Westinghouse flow diagrmas do not show tne functional relationship of the instrumentation.
There are no Westinghouse flow diagrams for systems having Bechtel P&ID's.
. TUBEC0 FABRICATION IS0 METRICS These are isometric presentations of a process piping system in the configuration of the plant. These isometrics were primarily prepared by TUBECO (pipe fabricator at Point Beach) and was used for fabrication and construction. The isometrics were prepared from the area drawings described previously.
- 8. FAILURE AND SEISMIC RESTRAINT AREA DRAWINGS For Point Beach the seismic and failure restraint locations were drawn on a set of piping area drawings for seismic Category I piping system outside containment. These drawings do not include the pipe supports. For piping inside containment a similar set of drawings were prepared except these also included the pipe supports.
- 9. VALVE AND FLOW ELEMENT VENDOR DRAWINGS Vendor drawings of valves and other flow control devices, such as restriction orifices, contain design data such as weiorts and end-to-end dimensions.
- 10. STRESS IS0 METRICS These were sketches precared by Bechtel or subcontractor to stress analyze the piping system. They were based on the area drawings.
POINT BEACH L AW ING LIST PIPING AREA DRAWINGS Drawing Ti tle Number M-20 Area 1 Turb Bldg piping area dwg. plan operating flr M-21 Area'l Turb Bldg piping area dwg. plan / intermed ia te flr M-22 Area 1 Turb Bldg piping area dwg . plan / ground flr M-23 Area 1 Turb Bldg piping area dwg . Section A-A, B-B, C-C and de tail s M-24 Area 1 Turb Bldg piping area dwg. Section D-D M-25 Area 1 Turb Bldg piping area Sections E-E, F-F & G-G M-26 Area 2 Turbine Bldg plan operating flr M-27 Area 2 Turbine Bldg plan intermediate flr M-28 Area 2 Turbine Bldg plan ground flr M-29 Area 2 Turbine Bldg plan Section A-A, C-C -
M-30 Area 2 TLrbine Bldg plan Section D-D, E-E M-31 Area 2 Turbine Bldg plan Section B-B, F-F M-32 Area 2 Turbine Bldg plan Section G-G M-33 Piping area dwg. Crea #3 Turbine Bldg plan, Section &
Control Roca A/C piping M-34 Piping area dwg . area 4 3 Turbine Bldg plan intermediate floor M-35 Piping area dwg. area #3 Turbine Bldg plan ground floor M-36 Piping area dwg . area #3 Turbine Bldg plan Sections, A-A, B-B, E-E, F-F, a nd G-G M-37 Piping area dwg . area # 3 Turbine Bldg plan Sections, C-C, K-K, L-L, M-M, and N-N M-38 Piping area dwg. area #3 Turbine Bldg plan Sections, D-D and H-H M-39 Area 4 Aux Bldg South M-81 Misc . uppe r floor M-40 Area 4 Aux Bldg South plan o~perating floor M-41 Area 4 Aux Blds South plan intermediate floor M-42 Aria 4 Aux Bldg South plan ground floor M-4 3 Area 4 Aux Bldg Scuth plan Section A-A M-44 Area 4 Aux Bldg South plan Section B-B M-4 5 Area 4 Aux Bldg South Misc . Sections M-4f Area 4 Aux Bldg S.outh Misc. Sec tions and L-L and M-M M-47 Area 5 Aux Bldg East plan operating floor (M-76, 77, 78, 79, and 98)
M-43 Area 5 Aux Bldg East plan intermedia te floor M-49 Area 5 Aux Bldg Ea s t plan ground floor M-50 Area 5 Aux Bldg East Section A-A M-11 Area 5 Aux Bldg East Section B-B M-52 Area 5 Aux Bldg East Sections C-C, D-D, and H-H U, 4i-)
504 I
POINT BEACH DRAWING LIST PIPING AREA DRAWINGS Drawing Title Number M-53 Area 6 Aux Bldg North plan oper. , misc . upped floor North (M-75, 81, and M-99)
M-54 Plan operationg floor M-55 Plan inte rmedia te floor M-56 Area 7 containment plan ground floor M-57 Section A-A M-58 Section B-B M-59 Area 7 containment De tails of coolant loop conn's M-60 Area 7 containment plan above El 66'0" M-61 Area 7 containment plan 46'0" to 66'0" M-62 Area 7 containment plan El 21'0" to 46'0" M-63 Area 7 containment plan celow El 21'0" M-64 Area 7 containment Section A-A M-65 Area 7 containment Section B-B M-66 Area 7 containment Misc. Sections M-67 Area 7 containment Clg. wtr piping from Hdrs to Clg coils M-68 Area 8 Aux Bldg West plan operating floor M-69 Area 8 Aux Bldg West plan inte rmedia te floor M-70 Area 8 Aux Bldg West plan ground floor M-71 Area 8 Aux Bldg West Sections A-A, D-D, E-E, F-F and H M-72 Area 8 Aux Bldg West Section B-B M-73 Area 8 Aux Bldg West Section C-C M-74 Area 8 Aux Bldg West Misc. sections and partial plans M-75 Area 8 Aux Bldg West Misc. sections M-76 Pipeway # 2 upper plan and sections M-77 Pipeway 42 lower plan and sections M-78 Area 5 sections E-E, F-F, a nd G-G M-80 Area 7 plan and misc. sect. con t' d . spray M-81 Areas 4, 6, 7, and 11 misc . de tails PIPING AND INSTRUMENTATICN DIAGRAMS M-200 Unit 1 piping and iristr . diagram Legend M-201 Unit 1 piping and inst. diagram Main and Reheat S tm .
M-202 Unit 1 piping and inst. diagram Cond. and Feedwa te r M-207 Service water M-209 Instr. and Se rv ice Air M-217 Aux. Feedwater system M-218 Station service wa ter flow rey.
M-219 Fuel oil system ru' i O>
504
POI'IT BEACH DRAWING LIST PIPE SUt PORTS Drawing Title Number M-410 Critical piping failure and Seismic restraints _
details Sheets 1 thru 15 M-411 Area #4 plan ground floor M-412 Area #4 plan intermediate filor M-415 Area #5 plan ground floor M-416 Area #5 and 8 Operating floor M-420 Area 6 ground floor M-425 Pipeway #2 upper plan and sections _
M-426 Pipeway #2 lower plan and sections M-427 Fipeway #3 uppor plan and sections M-428 Pipeway 43 lower plan and sections M-423 Area 3 plan ground floor M-430 Area 3 intermediate floor M-431 M-433 Area 8 intermediate floor M-434 Area 8 plan 9 (-) 19'3", (-) 5'3", and 8'0" M-435 Area 8 Aux. Bldg partial plan and misc. sections M-436 Failure and Seismic restraints Area 6 Misc. upper floor North M-437 Failure and Seismic restraints Area 4 Misc. upper floor South PIPING AREA DRAWINGS M-2030 Area 10 Turbine Building plan operating floor M-2021 Area 10 Turbine Building plan intermediate floor M-2022 Area 10 Turbine Building grotnd floor M-2023 Area 10 Turbine Building Sections A-A and B-B M-2024 Area 10 Turbine Building Section M-2025 Area 10 Turbine Building Sections D-D, F-F, G-G and H-H M-2026 Area 9 Turbine Building plan operating floor M-2027 Area 9 Turbine Building plan in te rmedia te floor M-2028 Area 9 Turbine Building plan ground floor M-2059 Piping Area Drawing Area 11 containment loop conn's.
Details of coolant M-2060 Plan El. 66'0" M-2061 11an El. 46'0" M-2062 tlan frca El. 21'0" to 46'0" M-2063 P an El. 8'0" -
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POI:iT EEACH DPE4IiG LIST PIPING AREA DPEJI:71S M-20Ch Section A-A M-2C65 Elevaticn 3-3 M-2066 Mice. sections M-2C67 Clg. WTR. piping frc= Hrds to cig. coils M-207o, Pipeway 73 upper M-2077 #3 lower M-2C80 Area 11 Plc.n & Mice. sect. ccn't spray M-22C0 Piping and inctrument legend M-22Cl thin a reheat ctec M-2207 Service water
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M-22C9 Instrument & service air M-2213 Lube oil system PIPE SUPPCRTS M-24CO Critical piping support acceablies fabrication &" erection" Sh. #1 Sh. $2 M d 11 ft fl ff 11 ff Sh. m3 M M ft tf M ll it ff Sh. e4}
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- ff 3 ff 11 T1 TT It Sh. m5 Sh. #6 Sh. #7 M-2kC1 Hanger Guidance & Erection dwg. eent. vent 1 coat. spray 2 El. +66'0" Sh. 3 M-24C2 frcs El #46'0" to 66'0" M-2403 21'0" to h6'0" M-2kC4 plan El A-A M-2405 El B-B M-2kC6 above El 66'0" M-2hC7 Misc. El M-2408 Main Steam Harger Guidance & Erection Support assemblies Sh. 1 Sh. 2 M-2hC9 Stea::: gen. feedwater hanger guidance & erection pipe support assemblies Sh. 1 Sh. 2 OTHER CCCUMENTS M-3320 Pipir; Class Su .ary - Eechtel M-3321 Piping Class Su=ary - Westinghouse , . n n.
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WECTI:ECUCE DCCU'CiTC llCE017 Safety Injecticn Sycten Unit 1 11CE018 Auxiliary Ccolant Cyctem Unit 1 SklFC9h Chemical & 7olume Centrol System 541Fo91 Reactor Ccolant Syctem Unit 1 68kJ961 Chemical a Volume Centrol Unit I llCE0E9 Auxiliary Ccolant System Unit 2 lloE035 Safety Injection System U.. 2 5klF4k5 Reactor Coolant System Unit 2 Chemical & Volwne Control Uni', 2 5klFk50 -
085J175 Chemical & Volume Control Unit 2 IJf.l, d. O'L_2
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