ML19221A284

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Forwards Plan for Placing TMI in long-term Stable Mode. Recommends Steaming Down a Generator to Decrease Primary Plant Temp for Natural Circulation Transition
ML19221A284
Person / Time
Site: Crane 
Issue date: 04/12/1979
From: Wilson R
GENERAL PUBLIC UTILITIES CORP.
To:
References
NUDOCS 7905210193
Download: ML19221A284 (21)
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Text

{{#Wiki_filter:Inter-Office Memorandum

ate ^ April 12, 1979

~~' [ = TSG 016 Q[ {h utiect Cooldown of TMI-2 0' R. C. Arnold Locahort Three Mile Island As part of the overall plan for placing TMI-2 in a long term stable mode, the reactor will be placed into natural circulation. Preliminary to the natural circulation transition, a decrease in primary plant temperature will be required. It is proposed that the initial step in this direcelon be taken immediately by steaming down on the A generator by opening further the turbine bypass valve. It is anticipated the primary system would be cooled from its present 28 5

  • to approximately 2 20* - 2 3 0*.

The attachment to this memo briefly reviews several of the considera-tions relating to the steamdown. The end point configuration of the reactor does not appear to result in any additional risk, current emergency procedures should be adequate and the system will be in a stable mode. Y. L R. F. WSlson B&W Concbrrence RFW/al ATT cc: T. M. Crimmins s H. F.. Dieckamp J. G. Herbein R. W. Keaten J. McMillen 150 EIR .203 7905210/?3 GPU Screce Ccrporaten is a sub.cary ct Gmeral Pubc Uh:: Des Cor;crancn

~ 1700 .TMI-2 Recovery UASE CASE

SUMMARY

(Revision 2) - - @c @B QO /CCO RC Pressure 3) (psi) ,r / O, R l t 220 RC Temp ( F) (1) Degas at A. Lower pressure ( A -- A ' ) while degassing, then return to A. (2) Continue design / installation of static & active systems for primary makeup / level control and secondary cooling system for S/G "B". (3) Reduce temperature ( A-+B) by steaming on "A" S/G. Verify oI'erability of secondary cooling system for "B" S/G. (4) At B, establish solid cooling to "B" S/G, and when stable, isolate "A" S/G. (5) Reduce temperature ( B -* C) with S/G "B". As soon as possible, start solid operation with "A" S/G, with modification pkg to be determined. (6) At C, trip PC Pump "A" and establish natural circulation in "A" and. "B" loops. (7) Reduce primary prensure to value to be determined (C-7 D ). (3) Take primary system solid - activate new MU/ pressure control system. END POINT Primary: Natural circulation, solid water, long term P/V control Secondary: Solid water, long term heat dump system APPROVED FOR ISSUE: R. C. Arncld 150 205

PROPOSAL Cooldown (A-B) of TMI-2 While Steaming on A Steam Generator 1. Method: a) Steam from S/G A to the main condenser controlling flow with the turbine bypass valves. b) A slow cooldown rate less than 10 F/ hour will be specified. c) Maintain pressure at about 1000 psi. Controlled depressuriza-tion is permitted to check gas concentration. d) Continue degassing at maximum rate. e) Monitor core thermocouples, neutron monitors and noise levels to determine any anomol.

output.

S 150 206

2.- Technical Issues a. Effect on Shutdown Margin & Boron The reduction in RC temperature from 280* to 230 F will slightly decrease the core shutdown margin. However, the expected change in reactivity is small in comparison with the amount of excess boron concentration in the coolant. For example, for a clean core with all rods at zero power, the required boron concentra-tions are as follows: Temperature Keff Boron Conc. Ppm 7 0* F 0.99 1057 532*F 0.99 741 A = 4 62* F A= 316 ppm Thus, an increase of only about 50/462 x 316 ~ 34 ppm boron should compensate for the temperature reduction. In actuality, the boron concentration is currently in the 2600 - 3400 ppm range, such that adequate shutdown margin will be maintained (calculations from FS AR). B&W analysis on TMI-2 criticality evaluatas a broad spectrum of fuel configurations ranging from the intact core to homogenous solutions of uranium and water (references B&W submittal to Met-Ed entitled, " Safety Evaluation Information for Transition to Natural Circulation Cooling", dated 4/11/79, Section~3.9). The conservative calculations and the assumptions on the core configuration have led B&W to recommend a boron concentration of 3000 ppm. They have confirmed that lowering temperature from 280*F to about 230*F does not affect their recommendations on criticality or boron concentration. Further, nuclear instrumentacion will be monitored during cool-down to confirm that adequate shutdown margin is maintained. The effect of reducing RC temperature from 2 8 0* F to about 230 F will be to decrease the boron solubility in the coolant.

However,

'in the temperature range of interest (280' - 230*F) the boron solubility is more than a factor of ten greater than expected boron concentra tions. (e.g., boron solubility at 200*F is about 44000 ppm) As a result, the temperature reduction should have no significant effect'on boron precipitation. Calculations by GPUSC indicate that in the temperature and boron concentration rarge of interest, decreasing temperature 280 230'F decreases reactivity. The reason for this is that in this temperature range the change in cross section (s greater than the change in moderation due to density change. 150 207

b. System Gas Considerations 1) Since pressure has been as low as about 300 psia and conserva-tivelv assuming that the RC was saturated with non-condensibles at 300 psia, 280 F, the concentration of H2 would be about 52 0 ppm. At 1000 psia, 280 F, the concentration would be 175 ppm 0 if saturated, and at 1000 psia, 230 F, the saturated concentra-tion would be 115 ppm. Clearly a decrease in temperature from 0 2800F to 230 F would not cause non-conder.sibles to come out of solution since the existing H2 concentration is below the satura-0 tion' concentration at 1000 psia and 230 F.* 2) Reducing RC temperature from 2800 0 F to 230 F would tend toward reducing solubility of H2 in the makeup tank which would improve degassing effectiveness. 3) Lower RC temperature would tend to reduce clashing and amount of gases coming out of solution in the let wn Jine. Assuming the major pressure drop is across the letdt-n coolers, two phase flow could exist in downstream piping and filters. This will reduce total mass flow rate due to the high volumetric flow associated with the two phase condition. A reduction in tempera-ture would therefore tend to increase mass flow rate and improve the degascing effectiveness. 4) Solubility of N2, 2, 0 and H is shown in the attached figure. 2 0 Note that in each case a reduction in temperature from 280 F 0 to 230 F would result in a reduction in gas solubility in the makeup tank. Multiply ppm by 11.2 to obtain cc/kg. T50 200

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c. Vessel Pressure - Temperature Limits

Reference:

D. A. Roy memo to E. Rogers dated 4/10/79 (transmittal W154) - 8:35 p.m. B&W has evaluated the reactor vessel using conservative flow size assumptions (1/4 of vessel shell or nozzle thickness) and, in accordance with the ASME Code, Section III, Appendix G and has provided Met Ed with allowable RCS pressure as a function of system temperature. (See attached curve from referenced memo. ) The curve shows that for temperatures above 160'F, the system pressure can rise to the setpoint of the pressurizer safety reliefs (2500 psi) without concern. The range of temperatures during this evolution (28 0* F down to about 200* F or whatever lower temperature can be achieved by steaming) are covered by this limit (2500 psi) and, therefore, no special precautions need be considered to limit pressure. B&W has confirmed that cooldown rates equal or less than 10* F/hr have no adverse effect on vessel or system integrity. 150 2i0

DOCL V EN-oneI F /7 C7 ?LLLED ANC).,9 ono e NO. OF PAGES 5 REASON: % PAGE ILLEGIBLE: C HARD COPY FILED AT: PDR OTHER C BETTER COPY REQUESTED ON / / O PAGE TOO LARGE TO FILM: C HARD COPY FILED AT: PDR CF OTHER C FILMED ON APERTURE CARD NO. l50 211

~ d. Impact on contingency Plans A review of the existing contingency plans prepared or under prepara-tion for the current plant conditions (1000 psig, 285"F, steaming on "A" steam generator, 1 RCP running in the "A" loop) was made, and it was concluded that no changes need be made to accommodate the change from 280* F to about 220*F (or whatever minimum temperature can be achieved while steaming). Contingency plans will be revised to reflect future changes in state not covered in this proposal (such as changing the cooling mode from steaming to solid water, changing pressure from forced to natural circula tion). Contingency plans are constantly being updated to reflect improving knowledge of the expected plant behavior in each mode of operation. d 150 212

i e. Core Flood Tanks t The core flood tanks should not be affected by this cooldown. They should remain in their existing condition, valved out with N2 overpressure. t t i 150 213

f. Thermal Considerations General thermal considerations relating to the core cooldown under forced circulation include the following: 1. Increased subcooling would improve core heat transfer and reduce the degree of nucleate boiling that may be occurring in the core. It is considered preferrable to keep fuel rods of uncertain mechanical condition immersed in subcooled water than to permit local boiling which could lead to the possibility of pockets of steam in obstructed regions.. 2. Lower RCS temperature reduces the risk of flashing in the event that an unexpected pressure reduction occurs. Flashing could have adverse consequences in a core of uncertain mechanical stability. 3. Reduced temperature should provide some minor reduction in the general stress on system components subject to RCS and contain-ment environment. 4. In the case of an RCP trip, a lower temperature provides a greater system heat sink capability (primary and secondary water and system materials) and, therefore, provides more time for action. The additional margin to saturation (as long as pressure is held constant) also provides additional time for emergency response. In terms of natural circulation, a lower temperature starting point provides a greater margin to hot leg boiling, thus maximizing the potential for preservation of natural circulation. 5. Lower temperatures in the RCS present no siginificant disadvantage in terms of the emergency initiation of natural circulation. 150 214

g. Reversibility If there are any unexpected results from this cooldown, the evolution is completely reversible by reducing or eliminating the steam flow to the condenser letting the RCS heat up. The slow rate of cooldown permits easy identification of problems and time to react should problems occur. 150 215

.s h. Pressurizer Level Calibration l Current activities to develop correlations so that pressurizer level can be inferred from other measurable plant parameters should not be affected by this minor change in plant temperature. Pressurizer level must be maintained during the cooldown by adding makeup to the system to compensate for thermal contraction. If pressurizer level becomes unavailable, the cooldown should be halted until the actions necessary to infer pressurizer level can be done or pressurizer level indication can be restored. When the cooldown to about 220 F is completed, the test used to estab-lish the correlation between rate of change of pressure as a function of pressurizer level will be repeated to ensure the data base for inferring pressurizer level is still applicable. e i i 1 i { l l I 5 150 210

i. Primary Coolant Leakage Primary coolant leakage is not expected to be affected notice-ably by the proposed cooldown. t 150 21/ ~

3. Precautions a) A procedure to accomplish this evolution will be provided. b) A slow cooldown rate of nominally 2 - 4*F will be specified based on the judgement that moving slowly is in no way a disadvantage and has several~ advantages including ready recognition of changes in conditions and easy reversibility. c) Source range instrumentation will be monitored for criticality, noise monitors will be monitored for abnormal indications, and core thermocouples will be monitored for abnormal temperature fluctua tions. Specific gaidance on action le'rels will be provided in the procedure for cooldown. / / ~ 150 218

Today the NRC staff has authorized Metropolitan Edison Company to initiate a phased cooldown of the primary system of Three Mi f e Island Unit 2. During the initial steps of the cooldown the primary coolant system temperature will be reduced from its present level of 280 F to about 230 F. This phase of the cooldown process is a part of the overall program to bring the reactor to an operati.ig candition for eventual use of natural circulation cooling of the reactor through the steam generators. Degassing of the fr'imary coolant system has been underway for the past sesaral days. While it is possible to establish cooling by natural circulation at the present time there are several further steps considered to be desirable to optimize the process of reaching natural circulation cooling for long term conditions. These steps consist of-1. Modification to the "B" steam generator to provide additional redundancy for natural circulation. 2. Cont inued cooldown of the primary system to an optimum temperature to be established for natural circulation. 3 Adj us t ing other system condi tions to the most desirable state and initiate natural circulation. The NRC has not yet approved a detailed timetable for each of these planned actions. NRC will review carefully each phase of the cocidown operation. 150 219 c,

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