ML21055A261

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3 to Updated Final Safety Analysis Report, Drawing 6I721-2400-25, Post Accident Sampling System - P & Id Sh. 1
ML21055A261
Person / Time
Site: Fermi, 07200071  
Issue date: 02/02/2021
From:
DTE Electric Company
To:
Office of Nuclear Reactor Regulation, Office of Nuclear Material Safety and Safeguards
Shared Package
ML21055A091 List: ... further results
References
NRC-21-0002
Download: ML21055A261 (1)
v • d • e


Text

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OTHER REVISIONS: CHANGED INC. CODE TO 'U' GAS SAMPLE REFRIGERATION UNIT LIQUID CHILLER IP3400D010 I

THIS DRAWING WAS REFORllA'.!'TED BY AUTOCAD AT REVISION F. AlL PREVIOUS APPROVAL SIGNATURES ARE ON FD..E ON MICROFCLM IN DOCUMENT CONTROL TC A PORTION OF 'l'Hl5 DRAWING JS AFFECTED BY THE FOU.OlflNG; CBAJ,IGE DOCUMENT I

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1 NOTES:

1.

FOR SIZING, DESIGN PRESSURE AND TEMPERATURE REQUIREMENTS, SEE THE G.E. DESIGN SPECIFICATION #23A4090 AND 61721-2400-11.

2.

HEAT TRACE ALL GAS SAMPLE LINES FULL LENGTH, EXCEPT SECONDARY CONTAINMENT ATMOS.

3.

ALL OPERATED VALVES SHOWN IN THE DE-ENERGIZED POSITION.

4, THE SAMPLER STATION IS COMPRISED OF THE LIQUID SAMPLER, GAS SAMPLER AND ENCLOSURE.

5.

THE SAMPLE STATION SHALL HAVE A VARIABLE DAMPER OR VENT ON THE ENCLOSURE TO FACILTATE AIR FLOW THROUGH THE STATION.

6.

UNLESS OTHERWISE SPECIFIED, ALL NUMBERS ARE PREFEXED WITH P3400.

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SUPPLEMENTAL DOCUMENTS UNDER THE FOLLOWING IDENTITIES ARE TO BE USED IN CONJUNCTION WITH THIS DRAWING.

1. REACTOR RECIRCULATION SYSTEM (BWR/6)--B31-1010 NUCLEAR BOILER SYSTEM (BWR/4&5)-----B21-1010
2. RESIDUAL REMOVAL SYSTEM-----------E11/E12-1010
3. POST ACCIDENT SAMPLING SYSTEM DESIGN SPECIFICATION---------------D24-4010
4. PIPING AND INSTRUMENT SYMBOLS-------A41/A42-1010
5. G.E. OPERATION & MAINTENANCE MANUAL---G.E.K. 83344 (DSN T-1911)

LEGEND:

HEAT TRACE LINE INSULATION 5 WAY VALVE REFERENCE DRAWINGS:

61721-2400 ELECTRICAL SCHEMATIC DIAGRAM GENERIC BWR LOCA SAMPLER 61721-2400-22 '

61721-2400-23 61721-2400-24 ELECTRICAL CONNECTTION DIAGRAM GENERIC BWR LOCA SAMPLER 61721-2400 PIPING INTERCONNECTION DIAGRAM 61721-2400 LOCATION PLAN POST ACCIDENT SAMPLING SYSTEM EQUIPMENT.

61721-2400 PIPING ARRANGEMENT POST ACCIDENT SAMPLING SYSTEM 61721-2400 PENETRATION DETAILS SECONDARY CONTAINMENT WALL POST ACCIDENT SAMPLING SYSTEM 61721-2400 PIPING STAND DETAILS POST ACCIDENT SAMPLING SYSTEM 61721-2400 REACTOR COOLANT SAMPLE LINE SUPPORTS AND SHIELDING DETAILS 61721 -2831 INSTRUMENT TUBING INSTALLATION 61721-2400 POST ACCIDENT SAMPLING SYSTEM P & ID (SHEET 2) 61721-2400 PASS ARRANGEMENT & TABULATION PNL P34-P001.

INC.CODE u

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'NON-NUCLEAR SAFETY RELATED' TITLS THIS IS AN AUTOCAD PRODUCED DRAWING.

CHANGES OR REVISIONS MUST BE BROUGHT TO THE ATTENTION OF THE PLANT ENGINEERING DESIGN GROUP TO ENSURE THAT CONFIGURATION CONTROL IS MAINTAINED.

Detroit Edison Fermi 2 PRZPARED BY DATE POST ACCIDENT SAMPLING SYSTEM -

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CHECKED BY DATE r,:=F'!:=RT=u=,..=-=-cARD=:-=nTLE==------------------; A P&ID POST ACCIDENT SAMPLING SYS APPROVED PLANT IDENTll"ICATION SYSTEM NUMBER P3400 ARMS RECJPll!:NT #

NUC OPS FILE NO.

DATE ISSUED....... TO lS c2. -I -V/:i' REV.

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