ML19322C887

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TMI-2 Mini Decay Heat Removal Sys-Design Criteria
ML19322C887
Person / Time
Site: Crane  
Issue date: 10/30/1979
From: Dye E, Elam B
METROPOLITAN EDISON CO.
To:
Shared Package
ML19322C884 List:
References
NUDOCS 8002040546
Download: ML19322C887 (16)
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{{#Wiki_filter:o 'S. ' c. s THREE MILE ISLAND - UNIT NO. 2 MINI DECAY HEAT REMOVAL SYSTEM DESIGN CRITERIA ? g 1 l 1 8002 04 o F(f REVISION DATE PREPARED BY APPROVED BY A 7/10/79 E. C. Dye B. D. Elam ,.;;fN _ (,h, 1 ~ /. 2 8/01/79 gj g 3 8/16/79 (,d. gQ ~4 g/10/79 g,C_Lgg g4 5-9/20/79 ( - (*. t g g

THREE MILE ISLAND - UNIT NO. 2 1 MINI DECAY HEAT REMOVAL SYSTEM DESIGN CRITERIA C. I '~ 3 I i a 1 4 REVISION DATE PREPARED BY APPROVED BY 6 10/30/79 f.t'.) -88((% 3 R = as s e, m - e.- we a. w -m e -. y 7,. -pw- -,--y y-,a

MINI DECA 1 HEAT REMOVAL SYSTDi g DESIGN CRITERIA 1.0 SCOPE This document establishes the design criteria for a small scale decay heat removal system to be used to cool the reactor core for three years. The system consists of a pump / heat exchanger subloop to be in-stalled in parallel with the existing decay heat system and in paral-lel with the Westinghouse designed Alternate Decay Heat Removal Sys-tem. The system will be used to remove decay heat from the reactor core until full defueling has been performed.

2.0 INTRODUCTION

O The reactor coolant system is currently in a natural circula, tion mode with heat being removed through Steam Generator "A" in a steaming .\\ 90'. mode. In order to reduce the vulnerability of the plant cooling mode, a force circulation system with a minimum of supporting systems is preferred. A small scale decay heat system capable of removing the small amount of decay heat remaining (s;l MW) in the Unit 2 core will suit this purpose. All system components shall be enclosed in the existing Unit 2 Fuel Handling Building or Auxiliary Building to minimize the poten-tial for release of radioactivity to the environment. e 3.0 FUNCTIONAL AND DESIGN REOUIREMENTS 3.1 Performance Recuirements 3.1.1 The system shall recirculate reactor coolant through the core for removal of decay heat. The ultimate heat sink shall be river water with the Nuclear Ser-vices closed cooling loop to transfer heat from the reactor coolant to river water.

3.2 Applicable Codes and Standards Piping shall be: Manufacturing Installation Description Code Code Connection to the decay heat ASME - ANSI system downstream of DH-V3 Section III B31.7. up to and including the Class 2 Class 2 first isolation valve. Connection to the decay heat ASME - ANSI system downstream of DH-V3 Section III B31.7 from the first isolation Class 3 Class 2 1 valve up to and including the second isolation valve Connection to the decay heat ASME - ANSI system upstream of DH-V4B Section III B31.7 up to and including the Class 2 Class 2 second isolation valve l Connections to the existing Nucler.c Services closed cooling .I '; system j I. I piping up to isolation valve ANSI B31.l*. ANSI. I B31.l* lN isolation valves ASME - ANSI Section III B31.l* I Class 3 i Balance of pip'ing ANSI B31.1 ANSIB31.1l f Heat Exchangers ASME - Section VIII l TEMA Standard (ASME Section III if available) ~ Pumps Hydraulic Institute Standards (ASME i Section III if available) f , g'l " Filter ASME - Section VIII Seismically supported for Category I loadings R/ I 0 s . m '+h

o 3.3 Design Basis e 3.3.1 The portions of the system that are ANSI B31.7 Class 2 shall be seismic Category I. The remaining portions' of the system that convey reactor coolant shall be dd-R _v 3 signed to operating basis-earthquake (OBE) loads. The balance of the system can be designed as nonseismic except the NSCC tie-in lines up to the isolation valves shich shall be category I seismically supported. _'a 3.3.2 The system shall be designed to operate with a loss of offsite power. s 6 f 0 W e O

3.3.3 The system shall be equipped with test and instru-mentation connections for system pre-operational testing and normal operation. 3.3.4 The system shall be designed to supply cooled reactor coolant water to the RCS through the Decay Heat In-jection lines and receive heated coolant through the De.:ay Heat return lines. 3.3.5 The system design shall employ all welded connections to the greatest extent possible to minimize system leakage. All two inch and larger piping shall be welded except flanges at equipment connections. All connections to the* process piping shall be welded or screwed with seal weld up to the root valve. A Rev. 2 3.3.6 ne piping system and equipment sinall be provided. with adequate vent and drain connections. 3.3.7 The system design shall minimize the use of auxiliary support systems (bearing cooling water, lubrication oil and instrument air). Loss of instrument air shall not change the operating parameters (flow and tempera-ture) of the system. 3.3.8 The system shall be designed to remove the required heat load at the temperature of the cooling water shown in Section 3.4. 3.3.9 The system shall have provisions for the future in-stallation of a water purification system with the capability (resia dispeaal and shielding) to handle radioactive water. Installation and startup of this equipment shall not interrupt system function.. _. _

abf i n t wl R } D ff% D YD f h 3.3.10 Th2 system shall be provided with proper overpressure re-lief devices. The discharge of the overpressure relief h devices shall be piped such that they minimize the spread of contaminated fluids and shall be provided with some ' Rev 5 means of visual indication of leakag'e'r 3.3.11 'Ine syste:Fshall have proper connectTens and 6ther provi-- sions for flushing of new piping and croponents prior to startup. New piping and ccmponents shall be in a clean and neutralized state when installed." Chemical cleaning shall not be used af ter installation. 3.3.12 Trovisions shall be ::ade to h'andle system Icakage or drainage such as pump seal leak-of fs, f]anges, and valve Consideration shaJ1 be given to containing both stems. t' gaseous and liquid ef fluents, and safely delivering.,the wastes to CPU approved processing systems. ') 3.3.13 A recirculation line to meet the startup flow requirecents Rev. 2 4 of the pumps shall be provided. A~ system recircolation line is ' acceptable for this s'ervice. fRev. 3,, 3.3.14 'Ihe system shall be designed for long-t'erm continuous cool-ing for a minimum of three years. 3.3.15 For increased sys tem availability considera tions, the sys-tem shall have redundant heat exchangers and pumps. 3.3.16 Tne system shall be des. ed to be isolated from the exist-ing plant safety systems. Tne system, when in the isolated mode, shall not jee pardize the operability or pressure in-tegri ty of - the existing plant safe ty sys tees. Tne isola-3 tion from the Decay Haac Ratcoval System shall be. -i th double g iso 2 a tion valves.. - l. 3.3.17 The system shall have provisions for remo* 2 isolation, draining, and i, rw l = flushing to minimize radiation exposure to maintenance personnel j

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.c... Q.7 1, du a 3.3.18 The system shall have provisions for a replacable, disposable .., s. filter unit installed in the supply line 'to the MDHR system. The filter shall be capable of removing suspended particles .g .c, -J'. ~~, that may have accumulated in the decay heat drop line so that - - '. ; $.9,' l'l' ; s..* T..i.2 !- ti D = *..: ~ . '.,' k.;, %.. *. T, 1 damage,to the MDHR pumps'can be avoided..';

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3.4 Sizing Requirements 3.4.1 The system shall be designed to meet the following requirements: (a) Flow through reactor core 120 to 175 gpm (b) System inlet temp'rature 180* F e (c) System outlet temperature 130' F (d) Design Pressure $4 Coolers and pump suction 235 psis L Pump and discharge piping 235 psig Rev. 2 (e) NSCC water temperature 100* F (maximum) (f) NSCC water flow rate 200 gpm (g) Heat Exchanger duty See Curve 1 e, 3.5 Iayout Requirements 3.5.1 The system equipment shall be located to facilitate construction and future modifications and ease. of access during operation. 3.5.2 The system flow path shall consist of cooled reactor coolant entering the Decay Heat Removal System up-stream of valve DH-V4B, flowing through the reactor core and returning back to the heat exchanger through the Decay Heat Removal drop line and the new system connection downstream of DH-V3. On the cooling water side, the Nuclear Services closed cooling system shall be connected to the shell side of the new Mini Decay Heat Exchanger (refer to Figure 1, attached). 3.5.3 The ultimate heat sink shall be provided by the Nuclear Services River Water System. i _ _ _.

3.5.4 Radiation stlielding shall be provided between the Pumps and other equipment and piping to minimize the radiation exposure to maiItenance personnel while working on either of the pumps. This shall include shielding between the two pumps. Radiation shielding shall be provided to minimize the exposure to operating personnel when realign-Rev. 2 ing system valving. (The use of reach rods is anticipated). 1 t' 's g 6 I

J-D Ild: yg r, Q g g g,-, 3.6 E,ri. i,e s:..9nt.D,iu i r q.en ts, i.VJ 3.6.1 All equi;,mant shall be located inside the fuel Handling Suilding and Juxiliary Building. 3.6.2 Considaration shall be given to the integrated radia-tion exposure to all sensitive materials (electrical equipment, elastomers, etc.) over the design life of the system. If equipment cannot be satisfactorily shielded, the materials shall be compatible with expected expo-sure. 3.6.3 If area radiation levels at the pumps are expected to inhibit routine maintenance operations on the pumps, consideration shall be given to provide remote bearing lubrication to the pumps and motors. 3.7 Sampling Requirements Connections shall be provided for future sampling lines. ...(d 3.8 Materials Requirements All wetted materials

  • shall be compatible with fluids having water chemistry specified in Section 3.12.

It is expected that austenitic stainless steel type 304 or 316 shall be used. l ge+ 2 3.9 Electrical Requirements 3.9.1 Electrical equipment shall be capable of being started Lv-and powered f rom an on site lE diesel generator set in the event of a loss of off site power. Loads shall be sequenced on to the diesel' generator set manually. 3.9.2 Electrical classification of the system is non-1E, however the electrical' power to the operators on the system isola- , Rev. 5 tion valves and the pump motors shall be class lE. The instrumentation shall be powered from one class lE bus. ( i l -g_

3.9.3 '40 tor rated starting voltage shall be verified and consistent with the voltage regulation capability for the diesel generator to be used. liotor feeders shall be protected consistent with the original plant design and the normal trips for overload, etc., shall be used. 3.9.4 Electrical Load list: will be provided in the system ~ ! description. Rev. 5 3.9.5 " Criteria for General fiodification to the 80P Electri-cal System" are applicable. Also, refer to " Criteria for Loss of Offsite 80P Electrical Power?. 3.9.6 The power supply to the pump motors shall be supplied from separate IE buses. 3.9.7 T' Mini Decay Heat Removal pump motor power supplys are p to be interrupted when the installed decay heat remov- 'Rev. 5 (J al p.mps are started. This provision shall ntt inhi-bit the operation of,the decay heat fumps. 3.10 Testino Requirements . Provisions shall be made for pre ' operational testing of the sys-tem, including hydrostatic tests, flushing of.new piping, and demonstration of required pumping capability. 3.11 Instrumenta tion and Control Recuirements - 3.11.1 The system shall be designed to provide instrumentation to monitor furictionil performance requirements, includ-ing but not limited to: .' (a) Pump discharge pressure 0-300 psig " (b) Heat Exchanger inlet -and outlet 50-2500 F l

s e . d (c) Flow Rate Nominally 120 gpm Maximum 200 gpm - c (d) N.S.C.C. inlet and outlet Temperature 50-1500 F (e) Pump Suction Pressure 0-200 psig Rev. 2 3.11.2 Control circuits for existing egipment shall be re-viewed to ensure that no spurious automatic, or interlock signals will cause incorrect operation of the system. 3.11.3 Provisions shall be made for installation of ddn-I trols and remote indicators in the, Unit 2 Control. ~ Room. (It is assumed a new panel will be used). 3.11.4 Control shall be manual. The pump control switch shall have start, normal, stop and spring return to Rev. 3 normal positions. Run/off indicator lights shall be provided for motors and open/close lights shall be provided for the system isolation valves. (Both lights shall be on when valves are in intermediate position). 3.11.5 Control cables should have 50%, and preferably 100%, spare conductors to allow for future modifications. 3.11.6 Loss of system flow shall be alarmed locally and in the main control room. 3.11.7 (Deleted) gg,4

3.11.8 The isolation valve (s) on the NSCC system shall automatically close on detection of a leak, i.e., imbalance in the flow to and from the Mini Decay 4 Heat Removal cooler. 3.11.9 Area radiation monitors shall be provided and shall alarm on the local control panel and in the Control Room. 3.12 Water Chemistry pH 7.5 - 9.5 (nominal 8.5) Boron 3000 - 4000 ppa.., ', Hydrogen 5-<40 cc/Kg (nominal 15-40 cc/Kg) lev.- 2 Chloride <4 ppm e Fluoride <1 ppm Dissolved Oxygen < 0.1 ppm 1 \\ l 6 I THI-2 EXPECTED DECAY HEAT LOAD i VS. IlWE, JUNE 15 TO SEPI 18 l q 3.5 ~ ASSUMPTIONS

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