ML19331B634

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Forwards Util Responses to 10 of 11 Action Items Re Design of Util Interim Distribution Ignition Sys for Control of Hydrogen in Facility Containment Per 800729 Request
ML19331B634
Person / Time
Site: Sequoyah 
Issue date: 08/08/1980
From: Mills L
TENNESSEE VALLEY AUTHORITY
To: Schwencer A
Office of Nuclear Reactor Regulation
References
NUDOCS 8008120518
Download: ML19331B634 (41)
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Text

{{#Wiki_filter:. s-e.. e TENNESSEE VALLEY AUTHORITY CHATTANOOGA. TENNESSEE 374ot 400 Chestnut Street Tower II August 8, 1980 Director of Nuclear Reactor Regulation Attention: Mr. A. Schwencer, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Schwencer:

In the Matter of the Application of ) Docket No. 50-327 Tennessee Valley Authority ) A TVA-NRC meeting was held on July 29, 1980, to discuss the design of the TVA interim distributed ignition system for control of hydrogen in the Sequoyah Nuclear Plant containment. Enclosed are TVA's complete responses to 10 of the 11 action items requested of TVA during the July 29, 1980, meeting. Enclosure 1 is a list of the action items with a summary of the TVA response. Action item 7b, an analysis of heat fluence delivered to equipment and resultant equipment temperature environment will be submitted on or before August 12,19M. TVA was also requested to provide operational testing data on the igniters. This testing data will be submitted as soon as available. Very truly yours, TENNESSEE VALLEY AUTHORITY . M. Mills, Ma ger Nuclear Regulation and Safety Enclosure 3 owl

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l I!I THIS DOCUMENT CONTAINS P00R QUhUTY PAGES No3is g0 0B l An Equal Opportunity Employer

ENCL 0fURE 1 TVA ACTION ITEMS FROM JULY 29, 1980, MEETING ON INTERIM DISTRIBUTED IGNITION SYSTEM 1. Commitment to Use General Motors Glow Plug - TVA commits to the use of the General Motors Glow Plug as the igniter in the interim distributed ignition system for the Sequoyah Nuclear Plant. 2. Location Drawings - Attached are the location drawings, figures 1 to 6 for each elevation. 3. Mounting Details - Attached is a drawing s,howing mounting details, figure 14. 4. Location'of Igniter Switch Panel - Figure 5 shows the location of the lighting switch panel LS-4 which controls the igniters. Sa. Location of Hydrogen Monitors - See figure 7. Sb. Location of Hydrogen Monitor Intakes - See figures 1-6. 6. Hydrogen Monitor Description - See Enclosure 2. 7a. List of Components Required after Hydrogen Burns - Sea Enclosure 3. 7b. Analysis of Expected Equipment Environment - An analysis of expected temperature and assumed heat fluence will be provided on or before August 11, 1980. 8. Containment Cooling System Capability - See Enclosure 4. 9. Radiative Heat Calculations - See Enclosure 5. 10. Analysis of a Burn without Ice Condenser Benefits - See Enclosure 6. 11. Presentation by R. Bruce, OPS, on July 29, 1980 - See Enclosure 7. e

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s 1 ENCLOSURE 2 Description of Hydrogen Analyzer System at Sequoyah Nuclear Plant The hydrogen analyzer system installed in each unit of Sequoyah Nuclear Plant consists of two independently-trained, redundant, hydrogen analyzers and is designed to sample the' containment atmosphere for the presence of hydrogen and relay the measured atmospheric hydrogen concentrations to the main control room. Systent design calls for continuous operation during an accident under containment conditions of 2 to 50 psig and 40 to 290 F. The sampling system is seismic category I, and conforms to ASME Section III, Class 2, and Section IX requirements: ANSI B16.5, B16.11, N45.2, and B46.1 requirements; and the applicable requirements of the ASE, IEEE, etc. Each analyzer has a single 3/8" input sampling line.which branches into two 3/8" lines immediately before entering primary containment - one line penetrating into the upper compartment and the other into the lower compartment. See Figure 7. Each branch line is equipped with a normally closed, air operated, remote manually controlled, isolation valve. Upon actuation of the system the containment atmosphere is drawn through a series of sample conditioners including a trap, moisture separator, and filter before entering the analyzer. The sample is returned to primary containment via a 3/8" line. The return line is also equipped with a remote manually controlled isolation valve, normally closed. The analyzer is designed to operate under the conditions of pressure, temperature, humidity and radiation associated with a LOCA.. Each analyzer is calibrated to measure ..mm.- ---..----e-,--.n --.,n,,,-,n,-- w

hydrogen concentrations between 0 and 10 percent with an accuracy ) of one percent full scale. A schematic drawing of an analyzer is given in Figures 8 and 9 Sample suction and expulsion locations are shown in Figures 10, J1,12, and 13 Analysis is accomplished by utilizing the technology for thermal conductivity measurements of gases. The analysis technique utilizes a hot filament fixed in the center of a temperature controlled metal cavity. The filament temperature is determined by the amount of heat conducted to the cavity wall by the gas present. Thermal conductivity varies with gas species, thus causing ~The filament temperature to change as the gas in the cavity changes. Since filament resistance changes with temperature; by using two filaments in separate cavities and connecting them in an electrical bridge, the difference in thermal conductivity of gases in the separate cavities may be determined electrically. Electrical zero is set by first introducing the same gas to both cavities and then, adjusting the bridge so that the bridge will be balanced, resulting in zero output. Then, as different gases .are introduced to the two individual cavities, the bridge will become unbalanced, and the electrical output will increase with increasing differences in themal conductivity of the gases used. T'he measurement of hydrogen in the presence of nitrogen, oxygen, and water vapor is possible because the thermal conductivity of hydrogen is approximately seven times greater than nitrogen, oxygen, or water j vapor, which have nearly identical thermal conductivities at the filament operation temperature of approximately 500 F. Hydrogen measurement is accogplished by using a thermal conductivity 9 .. e y. g 7, e.. par,e rwm.eu.w ef ym,,, _ ..a y e m r r e- .-.r., $\\ZC2 Y 3 k'

measurement cell and a catalytic reactor. The sample first flows through the reference section of the cell, then passes through the catalytic converted where free oxygen is catalytically recombined with hydrogen to form water vapor, and finally flows through the sample section of the measuring cell. The hydrogen content is indicated by the difference in ther=al conductivity between the sample and reference sides of the cell. The hydrogen analyzers will be in the " stand-by" mode at all times during normal operation. Upon occurrance of an accident, the reactor operator opens the isolation valves and switches the analyzer to the "0N" mode to obtain hydrogen concentration information. b E20217.02 O

ENCLOSURE 3 Components Required After Hydrogen Burns Location Component, inside Containment Punction Limit switches Upper and lower FCV67-87, -95, -103, Lower compartment Lower containment cooler -111 discharge FCV67-295, -296, -297, Upper compart=ent Upper containment vent -298 cooler FCV70-87 Lower compartment RCP thermal barrier FCV7-89 Lower compartment RCP oil cooler LT3-148, -156, -164, Lower compartment steam generator level -171, -172, -173, transmitters (narrow -174, -175 range) 30-1AA, 30-13B Lower compartment containment air return rans Penetrations Medium voltage power, low voltage power, and control and instrumentation i Splices Junction boxes Lower compart=ent RTD connections to measure TCS temperature FCV62-61 Lower compartment Valve motor operator FCV63-67, -80, -98, Lower comparteent valve motor operator -118, -172 TE68-2A&B, -14, -25, Lower compartment Narrow range RTD's l -37, -44, -56, -67, l -79 (-410, 411, 420, 421, 430, 431, 440, 441). TE68-1, -18, -24, -41, Lower compartment Wide range RTD's -43, -60, -65, -83 (413, 423, 433, 443) NC41, 42, 43, 44 Lower compartment Excore neutron detectors H re mbiners . Upper compartment 2

H I PT68-322 -323, -334, Lower compartment Pressurizer pressure -340 (455, 456, 457, transmitters 458) PT68-320, 335, 339 Lower compartment Pressurizer level (459, 460, 461) transmitters PT68-66 (403) Lower compartment RCS wide range pressure transmitter LT3-56, -111 (502, Lower compartment Steam generator level 504) transmitters (wide range) FT1-3A&B, -10A&B, Lower compartment Steam flow transmitters -21 A&B, -28A&B (512, 513, 522, 532, 533, 542, 543) LT3-43, 98 (501, 503) Lower compart=ent Steam generator level transmitters (wide range) LT3-38 -39, 42, -51, Lower compartment stema generator leve -52, -55, -93, -94, transmitters (narrow -97, -106, -107, -110, range) -111 (517, 518, 519, [ 527, 528, 529, 537, 538, 539, 547, 548, 549) O t 1 l

ENCLOSURE 4 ASSESSMENT OF THE CAPABILITY OF THE NORMAL CONTAINMENT COOLING

8. There are eight normal reactor building coolers, four in the lower compart-ment and four in the upper compartment.

The lower compartment coolers have a capacity of eight million Btu /hr, and the upper compartment coolers provide an additional eight hundred thousand Btu /hr. This total capacity of 8.8 million Btu /hr is based on an affirmed atmospheric temperature of 327*F and river temperature of 83*F. The coolers are located above the maximum expected post-LOCA water level, are seismically qualified with full QA, and are supplied with ERCW. These coolers would be of some benefit in removing heat from hydrogen burns although n'o credit has been taken for them. Several conditions tend to limit the effectiveness of the coolers: After unit 2 startup, offsite power and the new ERCW pumping station a. must be available or there will be insufficient ERCW to meet plant requirements for one unit in hot standby with a LOCA in the other unit. b. Present containment isolation logic isolates the ERCW lines to the coolers when the containment pressure exceeds three psig. This would require modifications for the coolers to be of benefit during degraded core events. The CRDM coolers were also considered in assessing the capability of normal cooling systems. These coolers are located on the lower compartment floor and are therefore flooded early in a LOCA. It has been concluded that no credit can be taken for these coolers. o 9

ENCLOSURE 5 ESTIMTE OF C0!iTAlfM,EliT SHEj.L' TEMPERATURE DtE j TO HYOROGEN BURN IN THE L0k'ER CORPARTPENT, ~ A.n estimata was made of the temperature rise in the containment shell due to hydrogen burning in the lower cc:.partn:-ant. It was assumed that the gas will lose heat to the contain::,ent shell by radiation and convectiosa and to the ice condenser.. Due to the relatively low temperature of the gas iin the dead-ended compa'rtrent, it was assumed that only the water vapor e:nitted and absorbed radiation. The containment shell will reradiate a portion of the ' energy it. receives from the gas, so.e of which will be absorbed by the gas. Simple finite difference equations were'used to represent the heat balances for the contaf6-rrent'shell and gas for a time increment at. The. gas and shell temperatures were updated at the end of each time step and the calculation repeated until thermal equilibrium was reached. For a single burn of 103 pounds of hydrog' en in the lower cc:npart:[x:nt. the average te:nperature of a l" thick steel containment she increased by approxirately 8 F. Asstering a similar temperature rise for each of the<nine burns'for the 5 0 accident scenario, the mea'n temperature of the shell 2 should increase by m ughly 72'F. This corresponds tSa total energy deposition in the wall of about 4.5 x 106 ~ BTU. The'one inch thick containment shell was modelled as a one-disnensional stab The 6 total heat input of 4.5 x 10 BTU was added to the shell over a 200 second time l interval which corresponds to a surface heat fluk of about 5370 BTU /Hr-Ft. 2 The TAP-A computer program was utilized to conpute the transient temperature distribution in the shell. The maximum temperature difference in the wall froca inner surface to outer surface was approximately 21.4 F. The' corresponding U temperature difference from the inner surface of the shell to the center of the shell was mughly 15.7. F.

ENCLOSURE 6 EST1PATE OF CONTAINMENT SHELL TEPPERATURE DOE. TO HYDROGEN SWN IN LOWERTffWARTPINT NO_~ vs ~ ICE _ IM ICE C'fj!OENSER AFTER FIRST TWO BURNS An estimate was r.ade of the temperature rise in the contairrent. shell. due to hydrogen burning in the icwer co:3part.ent. The accident scenario is similar to that for the $ D base case except that no ice remains in 2 the ice condenser after the first two burns. The calculational asstasp-tions are similar to ttose used in making the pre'vious estimate of the' shell te=perature rise for the S D base case. 2 l l Since ice is available for the first two burns. it was asstaaed that the average temperature of 1" thick. stael shell increased by 8*F for each burn as previously calculated. When no ice is available in the ice condenser the average shell.te:qperature increases by approximately 17'F I per burn. There are a total of-seven burns, two with ice and five with no ice. The total terperature rise in the shell is. esticated to-be 101*F' (2 X 8 + 5 X 17). This corresponds to a total enedor deposition in thb ~ 6 ~ wall of about 6.3 X 10 BTU.- it was asse:ted that this amount of heat is added to the containment shell l over a 200 second tire interval which corresponds to a heat flux of approxi :-- l nutely 7520 STU/HR-FT. The TAP-A co;9 uter program was utilized to computen ' 2 the transient temperature distribution in the shell. The maximca temperature-difference in the shcIl fro;n inner surface to outer surface was approximately 32*F. The corresponding tescperaturN: difference frai the inner surface of-the shell to the center of the shell was roughly 22*F. e ~ m..._...........__.,........_.~....._._......,~._.._., mu

ENCLOSURE 7 ,1 l BASE CASE PARAMETERS 1. . INITIAL CONDITIONS: VOLUMES TEMPERATURES -PRESSURES LOTIC ICE MASS ICE HEAT TRANSFER AREA d '2. BURN PARAMETERS: H FOR IGNITION 10 V/0* 2 [... r...i'~ H FOR PROPAGATIO. N ". :.: ~; 10 V/0 2 02 FOR IGNITION 5 V/0 0 TO SUPPORT COMBUSTION 0 V/0 ,..c 2 1 .w FLAME SPEED 6 FPS ~~ 3. AIR RETURN FANS: NUMBER OF FA.NS ~ J. 2 . ? ,. n...... CAPACITY 0F EACH FAN.. 40000 CFM . c.. : 4. SPRAY SYSTEM:. f e.,. FLOW RATE .._7 ..s 6000 GPM .v.. ;S. : e ;.. w. 4, #,. T s.... a... .,.. i.:...,......., _. y L -..

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