ML19221A430

Task 6B: Reactor Coolant Pressure Control Sys Design Ctriteria-Makeup Portion, Revision 3

ML19221A430
Person / Time
Site:	Crane
Issue date:	04/23/1979
From:	Lu T, Zanis L GENERAL PUBLIC UTILITIES CORP.
To:
Shared Package
ML19221A429	List: ML19221A428 ML19221A430
References
TASK-6B, NUDOCS 7905230010
Download: ML19221A430 (11)

Text

{{#Wiki_filter:1 THREE MILE ISLAND - L? LIT No. 2 REACTOR COOLANT ?RESSURI CONTROL SYSTEM DESIGN CRITERIA - S'J.KEUP PLATION TASK 6E Revisica Date Prepared By Approved By Rev. 3 4/23/79 L. Zanis/T. Lu D. "re eher er/G. Capodanno T. U [# / \\62 208 7 905 23 0 C/ C /

• REACTOR COOLANT PRESSURE CONTROL SYSIE.M DESICS CRITERIA 1.

Scope: To establish the design criteria for a reactor coolant (RC) pressure control syste= to be used while the reactor is continuously cooled for 2 years. The syste= shall =aintain a mini =u= RC pressure $rith the pressurizer filled solid with water and without pressurizet neaters. te=perature changes It shall be capable of =cking up reactor coolant as cause water contraction and/or certain volu=e losses causing decrease in pri=ary syste= pressure. The reactor coolant pressure control syste= consists of passive pressure control co=ponents as well as active pressure control cc=- ponents. The passive pressure control portion of the syste relies on =anual operations only for initial fill. The active pressure control portion would allow for re=ote operaticn of motor-driven fill (che=ical or makeup) pu=ps. The passive pressure control syste= will be designed se that it can be an integral part of the active pressure control systen. The passive pres are control syste= is defined as a series of surge tanks supplied..th a nitrogen owerpressure fro = an automatically regulated bank of nitrogen cylinders. The active prepsure control syste= is defined as the passive pressure control syste= coupled with charging pu=ps and associated 6cgassed borated water supply. Phase I of the reactor coolant pressure control syste= will involve the installation of a =anual syste= controlled by a locally stationed operator. Phase II will involve additional instru=entation and control equipment required to auto = ate the =akeup portion of the syste= and allow control and onitoring of the syste fro = the TMI Unit 2 control room. 162 M 2.

== Introduction:== The Reactor Building is presently radioactively contaninated to the degree where it is anticipated to render cuch of the electrical equip-cent and instru=entation inoperative, such as pressurizer heaters. There is also water leakage f rom the RC Syste= into the Reactor Building which is and cay continue to cause flooding of and failure of instru=en-tation at the lower levels. The lower level instru=entation include pressurizer level, steam generator level, and others. The loss in instru=en tation will not allow the pressurizer to be reliably used for RC Systes pressure control, and will require that the pressuri:cr be kept in a solid water status for continued reactor core cooling operation. The long ter cooling = ode for the RC Syste= will rely upon operating the steam generators A & B as water to water heat exchangers and establishing pri=ary coolant flow via natural circulation. The pri=ary objective of the pressure control syste= shall be to: (1) =aintain the RC System in a solid water condition for natural circulation core cooling operations; (2) provide adequate NPSH to the RC pumps should it prove necessary to use one; (3) absorb volu=etric reductions in the coolant systes to =aintain syste= pressure within control licits, and (4) centrol the che=Istry of the fill fluid. R3 In developing the syste require =ents for the third objective, the following transients were considered for the long ters steady-state operation (for design data see Attach =ent A)'. t a. Loss of natural circulation in ene loop while the other loop is still running. b. Introduction of 5000 gpm of 30 F (feedwater) to an idle OTSG. c. Stopping one RC pu=p. d. Starting either the skid =ounted RHR or the originally installed R3 Decay Heat Re= oval Syste=. The starting of a reactor coolant pu=p following " natural circulatien abort" =ust be covered by the co=bination of this systen and the "=akeup" pu=p (MU PlA,h"J --PlS, or MU-P lc,or o ther ac tive inj ec tion pu=ps. Inadvertent and sustained feed of cold water to the RC System following high (> 2500F) te=perature RC System operation requires that this syste= " akeup" pu=p s (MU-PlA,B,C) or be supple =ented by injection frc: the = other active inj ection pu=ps. In lieu of'this provision, ad=inistrative controls consisting of " locked out" breakers or locked closed valves shall be adhered to to preclude rapid cooling of the RC Syste=, \\ 6,c o\\o L

. 3.0 Functional and Design Recuirements 3.1 Passive Pressure Control System 3.1.1 Functional require =ents for the system shall be as follows: 3.1.1.a The normal system operating pressure is less than or equal to 750 psig. During steady state

• operation (no seal injection, no RC pumps running), the system shall be capable of main-
• aining the RC System at a controlled pressure with an accuracy of +10% over the range of 50 psig to 900,psig, accounting for gage error.

(The selected operating pressure for a RC System te=perature shall be determined by utilizing a pressure in the region enveloped by Tables A and 3 (attached). R3 Table A provides the allowable pressure operating curve for pressure as a function of measured temperature and dissolved gas concentration and Table 3 provides the allowable pressure operating curve for pressure as a function of RC Syste= temperature recognizing NDT limits. 3.1.1.b The syste= shall be designed to have the provisions for supplying degassed borated water to the RC Syste=. 3.1.1.c The surge capacity of the.ystem shall be sufficient to meet the =akeup requirement of % gpm to the RC System for S hours or the design transients in Paragraph 2. 3.1.1.d 7he system shall be designed to operate continuously for a mini =u= of 2 years. 3.1.1.e Syste= shall have a design pressure of 1000 psig or higher as required by interconnections with existing syste=s. 3.1.1.f Assu=ing an initial reactor coolant system pressure of 750 psig, the regulator must be capable of =aintaining a minimum nitrogen gas space pressure of 645 psig to cause a 500 gpm injection rate. (to be confir=ed by syste= analysis utilizing known line loss values). 3.1.2 Design requirements for the system shall be as follows: 9 3.1.2.a The system shall not rely on any instrumentation or active valving within the Reactor Building except for RCS tempera-ture and pressure instrumentation which cay be utilized while R3 available. The system shall minimize the use of active ce=ponents outside the Reactor Building. 3.1.2.b The syste= shall be designed to li=it in accordance with Paragraph 3.9 the entry of non-condensible s, such as N, and '}h2 2k\\ 0, into the RC System. 2 3.1.2.c At least one surge tank shall be provided with pressurized N blanket to =aintain the desired system set pressure. 2 3.1.2.d Control and monitoring of the system shall be done locally during Phase I and fro = the TMI Unit 2 control root durin-R3 Phase II. Steady state =eans solid, natural circulation, pressure less than or equal to 750 psig.

. 3.1.2.e The surge line shall be sized to acco==odate the 500 gp= surge R3 flow rate fro = 3.1.1.f. 3.1.2.f Liquid lines and co=penents should be designed to handle fluids with particles 0.1 inches in dia=eter. 3.1.2.g Trovision shall bc =ade to refill the surge tanks with degassed borated water while =aintaining RC Syste= pressure. 3.1.2.1 Syste= co=ponents should preferably be designed to ASMI B & PV Code, Section III require =ents. If they are not available, co=ponents designed to the following codes are acceptabic: Piping - ANSI B 31.1 R3 Tanks - ASME B & PV Code, Section VIII or API Valves - ANSI B 16.5 and B 16.34 Supports and Hangers - ANSI B 31.1 3.1.3.j Syste= shall be provided with vents for filling and drains for draining. These shall have provisions to be piped to the rad-waste syste=. 3.1.2.k Provisions shall be =ade to acco==odate the addition of LiGH, NaOH, boric acid, H, de=ineralized water and hydrazine. 2 3.1.2.1 Syste= design loads should include syste= pressure, pu=p vibra-l tions, co=ponent and fluid weight, and pressure surges. There e is no seis=ic require =ent. l 3.1.2.= Welded construction should be used as =uch as possible. 3.1.2.n The syste= shall be designed such that in the event of inad-l vertent depressurization of the reactor coolant syste=, the j surge tanks shall be auto =atically isolated fro = the new l charging pu=ps and the reactor coolant syste=. The isolation shall be based on low level in the surge tank closest to the reactor coolant syste=. This isolation shall prevent inser-tion of N2 into the reactor coolant system while =aintaining the water injection function of the new charging pu=ps. When this isolation valve is not fully open, an alarm shall be R3 provided to alert the operators of an abnor=al valve position. The alar = shall have both local and control roo= annunciation. 3.1.2.o Tne pressure control syste: piping fro = the RPI =akeup line back through the second isolation check valve shall have a design pressure of 1500 psig provided the =ake-up pu=p dis-charge pressure is li=ited to 1000 psig. 3.2 Active Pressure Control Syste= (See Phase 11 definition on Page 1) \\(1 . \\. R3 1 L Functicnal and design require =ents for the active pressure control._ syste= are the same as those for the cassive pressure control system with the following additions:

3.2.1 The system shall be provided with redundant standby pumps which will (1) fill the surge tank in response to tank level reduction, and (2) permit gradual addition c2 water to the RC System. 3.2.2 Motor-operated valves where provided shall have an auxiliary handwheel shielded and accessible, if required. 3.2.3 Alarm shall be provided to indicate a differential pressure greater than 50 psi between the reactor coolant system (if available) and surge tanks. FJ 3.2.4 A variable capacity (0-10 gpm) pump shall be provided in parallel with the redundant ptmps provided. Provisions shall bc made for addition of a chemical addition flask on the discharge of the variable capacity pu=p. 3.3 Functional Limitations 3.3.1 The system will not be designed to maintain pressure during either HPI or LPI syste= operation. 3.3.2 The system will not provide seal injection water to RC pu=ps. It is assumed that the seal water, if required, is supplied by one of the three makeup pu=ps. The syste= shall be able to accommodate the 900 psig static syste= pressure condition required to run one reactor coolant pump. This R3 is an abnormal condition in that 900 psig is currently ,' required to provide letdown flow equal to the RCP seal injection flow to the reactor coolant system. 3.4 Interfaces 3.4.1 This syste= shall not defeat or degrade the functional capabilities of other existing systems. 3.4.2 This system shall be independent of other TM1-2 plant syste=s except for electrical service, sources of clean, reactor grade, de:ineralized water, and the use of existing piping from outside the reactor building to the RC System. 3.4.3 The system shall be designed to preclude the possibility of actions in other systems from inadvertently causing a loss of system surge capability. 3.5 Reliability The system shall be designed to provide redundant capability for all active components and instrumentation. 3.6 Maintainability 162 213 The system cc,ponents shall be located to limit radiation levels to 100 ar/ hour in areas where maintenance or operation is required. Further, the system design shall preclude backflow of reactor coolant (radioactive fluid) into the system.

. 3.7 Electrical Eecuirerents All electrical equipment and instrumentation required to operate the syste= shall have an energency alternate power supply that does not rely on off-site power. 3.7.1 The charging pumps shall be capable of being started and operated from an on-site diesel generator set in the event of a loss of off-site power. The charging pu=ps shall be sequenced on to the diese1' generator set manually. Criteria shall be established for the maximum allowable time to restore voltage ifter a loss of off-site pover. 3.7.2 Electrical classification of the system is non-class IE. 3.7.3 Motor feeders sha 1 be protected cor:sistent eith original plant design and ormal trips for overload, etc., shall be g3 used. 3.7.4 The preferred power sources are as follows: a) Charging water storage tank heater - 100 kw - bus 2-45 b) Charging pump A-1CO hp - Mce bus 2-32A c) Charging pu=p B - 100 hp - Mcc bus 2-42A d) Pauking pumps - 1/5 hp - as convenient e) Variable capacity pu=p - - as convenient f) Borated water transfer pump - - as convenient p) Borated water batching tank heater - - as convenient j 3.7.5 " Criteria for General Modification to the ECP Electrical Systen" are applicable. Also refer to " Criteria for Loss of Off-Site l BOP Electrical Power." 1 3.5 Instrumentation Instrument power shall be obtained froc the -egulated voltage power R3 supply panels 2-12R and 2 -22R. The systec shall be designed to be able to conitor the following para-seters: 3.8.1 Surge tank level (all tanks) 3.8.2 Charging water storage tank level and te=perature R3 3.8.3 Surge tank discharge pressure 3.8.4 Reactor coolant syste= pressure and temperature (frc= existing instrumentation if available). 3.8.5 Charging pu=p suction and discharge pressure and pump flow. R3

3. 8. 6 '

Nitrogen supply pressure h} \\

3.9 Chemistrv 3.9.1 The syste= shall be capable of adjusting the RC fill system water chemistry to the following: pH E7.5; Dissolved gas 5-15 Std. cc/kg H

• 2 Baron 2200-4000 ppo; F, Cl 51 pps (one ppm)

R 3.9.2 The RC design gross activity shall be assumed to be 0.5 Curies /=1. 3.9.3 For Phase I the cakeup water shall be degassed to a level of not greater than 15 Std. cc/kg. For Phase II, the cakeup water de-gassification cbjective shall be 5 Std. cc/kg. 3.10 Materials All maerials having contact with makeup water shall be compatible with R water at 200*F and 4000 ppm boron as boric acid. The caterials shall be stainless steel or carbon steel with stainless steel cladding. Carbon steel and copper alloys =ay be used in nitergen supply syste=. 3.11 Environ = ental Conditions ~ Design ambient te=perature: 40 - 120*F Design ambient relative humidity: 100: 3.12 Testing l The system shall be tested, hydrostatically and precperationally, before being placed into operation.

• Residual hydrazine may be provided in lieu of H. Hydra:ine in this application =ust 7

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