ML20198E942

Forwards Request for Addl Info & Containment Sys Branch Technical Position Csb 6-1, Min Containment Pressure Model for PWR ECCS Performance Evaluation, Per Review of Containment Pressure Calculations

ML20198E942
Person / Time
Site:	Washington Public Power Supply System
Issue date:	07/07/1975
From:	Tedesco R Office of Nuclear Reactor Regulation
To:	Stello V Office of Nuclear Reactor Regulation
References
CON-WNP-1075 NUDOCS 8605280362
Download: ML20198E942 (12)

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--q j ! 4.i J JUl. 7 TIIS NRR Reading File. CS Reading File CSB Reading File Dochet Nos. 50-460/513 D ket File MS 2M V. Stallo, Assistant Director for Reactor Safety. TR REQUEST POR ADDITIONAL IMPOEMATION C010CEENING THE WFPS 1 & 4 ECG EVALUATICEI - i CORITAIMMENT PRESSURE Plant Names WPPS 1-4 4 l Docket Nos.: 50-460/513 Licsasing $tages yCF.: NSSS Supplier: Rebeeck & Wilcox - Architect Engineer: United Engineers & Constructors Responsible Branch & Project Manager: RSB, G. Masetis; LWR 2-3, T. Cox Raquested Completion Date: July 7, 1975 Applicant's Esspense Dates Review Status: Incomplate h Centainmaat Systems Branch is reviewing the containment pressure calcar-laticas used for the ECCS.evelaation of WPPS 1 & 4. h applicant references Topical Report "ECCS Evalastion of B&W's 205-FA NSS" BAW-10102, for its ECCS emination. h containment pressure calenlations used in this evaluation were dame using imput parameters for the Bellefonte plants. The analysis is not in accordance with our Branch Technical Position 6-1 since ao justification was given for use of the Bellefonta contain==nt parameters for the WPPS plants. Enclosed is a list'of required additional information and a copy of our Branch Technical Position, CSB 6-1, "16minum _Containssent Pressere Medal for PWR ECCS Performance Evaluation, which should be used by the applicant in his analysis. These are the essentially sees comments provided you in our review of BAW-10102 my memo dated July 3, 1975. bb4 / original, iced by: [ Bobert I. Telums i Robert L. Tedesco, Assists:t Director 3 for Contain==nt Safety Division of Technical Review

Enclosures:

As stated cc: S. Hanauer J. Glynn T. Greene D. Eisenhet J. Kudrick S. Vargs F. Schroeder J. Shapaker W. Jensen i C. Masatis A. Giaubusso T. Novak W. Mcdonald A. Schwencer T. Cox l 4 .2.. TR: CS TR:CSD. ......TR: SE... R:C .* rie =

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REQUEST FOR ADDITIONAL INFORMATION WPPS 1 & 4 DOCKET NOS. 50-460 & 50-513 The ECCS evaluation for WPPS 1 & 4 is referenced to BAR-10102. The containment input values used in the containment pressure calculations of BAR-10102 are not for your plants. We re. quire that an appropriately conservative containment analysis be performed for your plant in accordance with Appendix K of the Co= mission's Regulations. The input values for the containment should be selected and appropriately justified as discussed in -our Branch Technical Position CSB 6-1, which is enclosed. 1. Provide an analysis of the containment pressure in the containment for the most severe break size in accordance with Branch Technical Position CSB 6-1 using containment input assumptions applicable to the WPPS plan ts. The containment internal passive heat sinks should be calculated in accordance with the method given in CSB 6-1 for CP applications. 2. Provide a comparison of the pressure calculated under item 1 with the containment pressure used in the core reflooding calculations of BAR-10102, 3. Provide justification of the following input parameters used in the contain-ment pressure calculations for WPPS. a. Net Free Containment Volume - Justification should include the total gross internal containment volume and the internal structures and equipment and their volumes which are subtracted to obtain the net free containment volume. A discussion of the uncertainties should be provided.

..-..~-...........c. ~_.. _ a b. Starting Time of Containment Cooling System (s) - Discuss the factors that show that the start time (s) assumed in the containment response analysis represent the earliest possible initiation of system (s) operation. c. Containment Initial Conditions - Compare the initial values of temperature, pressure and relative humidity in tite containment with the range of values that will be permitted during plant operation. d. Mass and Energy Release - For the most severe break size provide a table of mass and energy releass rates to the containment as a function of time during the blowdown, refill and reflooding periods of the accident. Include any spilled ECCS water. e. Containment Spray Water Temperature - Show that the value of contain-ment spray water temperature used in the containment response analysis is the lower bound temperature consistent with plant operating conditions. f. Passive Heat Sinks - At the operating license stage we will require a comparison of the containment passive heat sinks used in this analysis to those that exist in the plant. _.,,.-.-..,,,r-. e

1 Branch Technical Position CSB 6-1 MINIMUM CONTAINMENT PRESSURE l@ DEL t POR PWR ECCS PERFORMANCE EVALUATION l A. BACKGROUND Paragraph I.D.2 of Appendix K to 10 CFR Part 50 (Ref. 1) requires that the containment pressure used to evaluate the performance capability of a pressurized water reactor (PWR) emergency core cooling system (ECCS) not exceed a pressure calculated conservatively for that pur-pose. It further requires that the calculation include the effects of operation of all installed pressure-reducing systems and processes. i Therefore, the following branch technical position has been developed to provide guidance in the performance of minimum containment pressure analysis. The approach described below applies only to the ECCS-related containment pressure evaluation and not to the containment functional capability evaluation for postulated design basis accidents. B. BRANCH TECHNICAL POSITION 1. Input Information for Model a. Initial Containment Internal Conditions The minimum containment gas temperature, minimum containment pressura, and marimum humidity that may be encountered under limiting normal operating conditions should be used. l I b. Initial Outside Containment Ambient Conditions A reasonably low ambient temperature external to the containment should be used. l c. Containment Volume I The maximum net free containment volume should be used. This maximum free volume should be determined from the gross contain-ment volume minus the volumes of internal structures such as walls and floors, structural steel, major equipment and piping. The individual volume calculations should reflect the uncertainty in the component volumes. (

. 2. Active Heat Sinks a. Spray and Fan Cooling Systems The operation of all engineered safety feature containment heat removal systems operating at maximum heat removal capacity; i.e., with all contain==nt spray trains operating at maximum flow con-ditions and all emergency fan cooler units operating, should be assumed. In addition, the minimum temperature of the stored water for the spray cooling system and the cooling water supplied to the fan coolers, based on technical specification limits, should be assumed. Deviations from the foregoing will be accepted if it can be shown 1 that the worst conditions rei;arding a single active failure, stored water temperature, and cooling water temperature have been selected from the standpoint of the overall ECCS model. b. Containment Steam Mixing With Spilled ECCS Water The spillage of subcooled ECCS water into the containment pro-vides an additional heat sink as the subcooled ECCS water mixes 1 with the steam in the containment. The effect of the steam-water j mixing should be considered in the containment pressure calculations. l 1 c. Containment Steam Mixing With Water from Ice Melt The water resulting from ice melting in an ice condenser contain-ment provides an additional heat sink as the subcooled water mixes with the steam while draining from the ice condenser into the lower containment volume. The effect of the steam-water mixing should be considered in the containment pressure calcu-lations. 3. Passive Heat Sinks a. Identification The passive heat sinks that should be included in the containment evaluation model should be established by identifying those structures and components within the containment that could

influence the pressure response. The kinds of structures and components that should be included are listed in Table 1. Data on passive heat sinks have been compiled from previous reviews and have been used as a basis for the simplified model outlined below. This model is acceptable for minimum containment pressure analyses for construction permit applications, and until such time (i.e., at the operating license review) that a complete identification of available heat sinks can be made. This simplified approach has also been followed for operating plants by licensees complying with Section 50.46 (a)(2) of 10 CFR Part 50. For such cases, and for construction permit reviews, where a detailed listing of heat sinks within the containment often cannot be provided, the following procedure may be used to model the passive heat sinks within the containment: (1) Use the surface area and thickness of the primary containment steel shall or steel liner and associated anchors and concrete, as appropriate. (2) Estimate the exposed surface area of other steel heat sinks in acccr fance with Figure 1 and assume an average thickness of 3/8 inch. (3) Model the internal concrete structures as a slab with a 2 thickness of 1 foot and exposed surface of 160,000 ft The heat sink thermophysical properties that would be acceptable are shown in Table 2. At the operating license stage, applicants should provide a detailed list of passive heat sinks, with appropriate dimensions and properties. b. Heat Transfer Coefficients The follow:ng conservative condensing heat transfer coefficients for heat transfer to the exposed passive heat sinks during the

. blowdown and post-blowdown phases of the loss-of-coolant accident should be used (See Figure 2): (1) During the blowdown phase, assume a linear increase in the condensing heat transfer coefficient from h d" 2 8 Btu /hr-f t _.F. at t = 0, to a peak value four times greater than the maximum calculated condensing heat transfer coefficient at the end of blowdown, using the Tagami correlation (Ref. 2), F0 r0.62 h = 72.5 max Vt lP" 2 where h = maximum heat transfer coefficient, Btu /hr-ft

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= primary coolant energy, Btu 3 V = net free containment volume, ft t = time interval to end of blowdown, sec. (2) During the long-term post-blowdown phase of the accident, characterized by low turbulence in the containment atmosphere, assume condensing heat transfer coefficients 1.2 times greater than those predicted by the Uchida data (Ref. 3) and given in Table 3. (3) During the trar.sition phase' of the accident, between the end of blowdown and the long-term post-blowdown phase, a reasonab'ly conservative exponential transition in the condensing heat transfer coefficient should be assumed (See Figure 2). The calculated condensing heat transfer coefficients based on the above method should be applied to all exposed passive heat sinks both metal and concrete, and for both painted and unpainted sur' aces. f Heat transfer between adjoining materials in passive heat sinks should be based on the assumption of no resistance to heat flow at the material interfac2s. An avample of this is the containment liner to concrete interface. ~,

. C.. REFERENCES 1. 10 CFR Section 50.46, " Acceptance Criteria for Emergency Core Cooling Systems for Light Water Nuclear Power Reactors," and 10 CFR Part 50, Appendix K, "ECCS Evaluation Models." 2. T. Tagami, " Interim Report on Safety Assessments and Facilities Establishment Project in Japan for Period Ending June 1965 (No.1)," ~ prepared for the National Reactor Testing Station, February 28, 1966 (unpublished work). 3. H. Uchida, A. Oyama, and Y. Toga, " Evaluation of Post-Incident Cooling Systems of Light Water Power Reactors," Proc. Third Inter-national Conference on the Peaceful Uses of Atomic Energy, Volume 13, Session 3.9, United Nations, Geneva (1964). i l { l [ l l

TABLE 1 IDENTIFICATION OF CONTAINMENT HEAT SINKS 1. Contain= ant Building (e.g., liner plate and external concrete walls, floor, and sump, and liner anchors). 2. Containment Internal Structures (e.g., internal separation walls and floors, refueling pool and fuel transfer pit walls, and shielding walls). 3. Supports (e.g., reactor vessel, steam generator, pumps, tanks, major components, pipe supports, and storage racks). 4. Uninsulated Systems and Components (e.g., cold water systems, heating ventilation, and air conditioning systems, pumps, motors, fan coolers, recombiners, and ts:aka). 5. Miscellaneous Equipment (e.g., ladders, gratings, electrical cable trays, and cranes). l

TABLE 2 HEAT SINK THERM 0 PHYSICAL PROPERTIES Specific Thermal Heat Conductivity Densigy lb/ft Btu /lb *F Btu /hr-ft *F Material Concrete 145 0.156 0.92 Steel 490 0.12 27.0 P e O D i 1 4 l 1 l

TABLE 3 UCHIDA HEAT TRANSFER COEFFICIENTS Mass Heat Transfer Mass Heat Transfer Ratio Coefficient Ratio Coefficient 2 2 (1b air /lb steam) (Btu /hr-ft _*F) (1b air /lb steam) (Btu /hr-ft _ep) 50 2 3 29 20 8 2.3 37 18 9 1.8 46 14 10 1.3 63 10 14 0.8 98 7 17 0.5 140 5 21 0.1 280 4 24 f l

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