ML19294C073

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Forwards Addl Info on Natural Circulation Cooling & Resolution of Review Comments
ML19294C073
Person / Time
Issue date: 06/08/1979
From: Bickel J
Advisory Committee on Reactor Safeguards
To:
Advisory Committee on Reactor Safeguards
References
ACRS-SM-0153, ACRS-SM-153, NUDOCS 8003060641
Download: ML19294C073 (14)
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{{#Wiki_filter:n etcgo .e UNITED STATE NUCLEAR REGULATORY g ( /255m - o /s'3 f',Vf 'g c ADVISORY COMMITTEE ON REA b [ W ASHINGTON. D. C.f M S/#7d o, A s..... s t I June 8, 1979 ACRS Members TRANSMITTAL OF ADDITIONAL INFORMATION ON NATURAL CIRCULATION COOLING AND RESOLUTION OF REVIEW COMMENTS

Reference:

J. H. Bickel, " Background Information for ACRS Members on the Natural Circulation Cooling Mode," May 15, 1979 Following issuance of the initial report on natural circulation cooling for emergency decay heat removal (Reference 1) a number of coments and inquiries were received. The purpose of this memo is to address these coments and to transmit additional information. Dr. Kerr has requested an opinion regarding the usefulness of existing startup test data as a mechanism for verifying assumptions made in the Safety Analysis regarding natural circulation capability. A generally accepted technical position is that startup test verification should be performed to verify the conservatism of certain critical assumptions made in the Safety Analysis which may not be verified to a high degree of precision using analytical techniques. (Examples of these types of assumptions are: control rod SCRAM times during reactor trip and pump coastoown flow decay curves during loss of pump motor A.C.) The effectiveness and availability of natural circulation as a mechanism for decay heat removal (for the complete loss of A.C.) is just such an assumption usually made in the Safety Analysis. Verifying the effectiveness and availability of natural circulation during startup testing is not technically possible, however. This is because startup testing is performed prior to the accumulation of a sufficient fission product (and activation product) inventory needed to produce appreciable decay heat. Reactor operators and designers have attempted to circumvent this difficulty by performing a natural circulation test by operating the reactor at low power and tripping the coolant pumps. Natural circulation is thus observed by using instantaneous fission power as a heat source. This technique clearly demonstrates the effectiveness of natural circulation for heat removal in the range of 1%-8% thermal power for steady states. However this does not demonstrate transient heat removal capabi nty for core heat fluxes decaying from near full power to the decay heat level. This is not to imply an area of non-conservatism, because pump flywheels are generally designed to assure transient heat removal by maintaining a sufficiently long free wheeling coast-down times. Another type of test performed to demonstrate the effectiveness of natural circulation is to simultaneously trip the reactor and coolant pumps from an intermediate-power level (25-40". power). This type of test more closely demonstrates transient heat removal capability but it suffers from the inability to observe sustained heat removal in the 5-7% power range typical of decay heat produced in cores with E.0.C. fission and activation product inventories. 80 030 co6 i / 6

l As a personal opinion the most "optimium" way to verify the actual natu h following circulation assumed in the Safety Analysis would be to perform t e test: ascertain experimentally what portion of the control rods i i must be SCRAMMED from full power to achieve an instantaneous fiss o First: (A) power in the 5-7% power range. simultaneously trip this portion of the control rods and g (Shutdown control rods would be maintained (B) Second: ) available for complete reactor trip should this become necessary. the coolant pumps. and availability of natural This type of test demonstrates the effectiveness ther circulation as assumed in the Safety Analysis in an integrated f ashion It would also appear prudent to examine than by a piecemeal fashion.sensitSities of natural circulation to exter gener;.cor pressure and steam generator level. as supplemented by test data. d res Mr. Ebersole noted that the simplified analysis did not discuss the proc This is for establishing natural circulation when subcooling is lost.If Pressurizer as quickly as possible either via High Pressure Safety Inj correct. heaters. Diesel Generators. t ral Mr. Etherington requested an assessment of whether coolant flows 0 6 - a circulation were in the turbulent regime, thereby, justifying the useThe attac differential pressure loss term proportional to d':The flow will be turbulent if it is generator if it is greater than 2.0% and in a U-tube steam gen t ould clarify this point. h greater than 1.25%. difficult due to the distribution of design flows through the c cut it appears flows greater than 2.3% will be turbulent. flow values (to assure turbulence) have a net dec ith increasing temperature. John H. Bickel ACRS Fellow Attachmant: Evaluation of Limiting Flow Regions for Ttrblent vs. Transitional Flow

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