ML19224B366

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Health Physics Procedure 1720,Revision O:Hp/Chem Response to primary-to-secondary Leak
ML19224B366
Person / Time
Site: Crane Constellation icon.png
Issue date: 02/27/1978
From:
Metropolitan Edison Co
To: Mullinix W
NRC/IE
References
1720, TM-0124, TM-124, NUDOCS 7906150010
Download: ML19224B366 (7)
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Text

{{#Wiki_filter:, ]EI Doct&ENTS DOCUMENT NO: f _f._ 0F DOCUMENT PROVIDED BY COPY MADE ON METROPOLITAN EDISON COMPAh't. Wilda R. Mullinix, NRC [ 7 9 0 615 0 0 to 200 012

Revision 0

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02/27./78 THREE MILE ISLAND NUCLEAR STAT!ON {} STATION HEALTH PHYSICS PROCEDURE 1720 ~] HP/ CHEM RESPONSE TO PRIMARY-TO-SECONDARY f ~ ~ ~ Table of Effective Pages Pg Date Revision Pace Date R evision_ Page Date_ Revision _ 51.0 1.0 02/27/78 0 26.0 52.0 27.c 2.0 02/27/78 o 53.0 28.0 3.0 02/27/78 0 54.0 29.0 4.0 02/27/78 o 55.0 30.0 5.0 02/27/75 o 56.0 31.0 6.0 02/27/73 0 57.0 32.0 7.0 58.0 33.0 8.0 59.0 34.0 9.0 60.0 35.0 10.0 61.0 36.0 11.0 62.0 37.0 12.0 63.0 38.0 13.0 64.0 39.0 14.0 65.0 40.0 15.0 66.0 41.0 16.0 67.0 42.0 17.0 68.0 43.0 18.0 69.0 44.0 19.0 70.0 45.0 20.0 71.0 46.0 21.0 72.0 47.0 22.0 73.0 48.0 23.0 74.0 49.0 l 24.0 75.0 25.0 50.0 1 Unit 2 Staff ecommends A provat ' Unit 1 Staff Recnmmends Appr sal Date 11-14-77 Date 12 T? Approval I Approval n Cognizant Dept. Head Cognizant Dept. Head Unit 1 PORC Recomm Snds,tpproval Ur.it 2 PORC R ommend App aval Date I Date Chairn an a PORC Chai.ma of PC RC } PORC comme nts o' _ L_,__ included - PORC commen s of 44ncluded (da ) (date)' Date Date By By $/_ Date 2k Approvab x ; Date / / Approval / Station Supefntendent/ Mgr., O perational Unit Superintendent 2 0 0 0'N i' Quality Assurance m

J 1720 Revision 0 4 ? 02/27/78 THREE MILE ISLAND NUCLEAR STATION STATION HEALTH PHYSICS PROCEDURE 1720 f HP/ CHEM RESPONSE TO PRIMARY-TO-SECONDARY LEAK 1.0 PURPOSE This procedure describes the response daring a primary-to-secondary leak. Since it is not practicable to develop a completely detailed procedure encompassing every concernable situation, this procedure presents guidelines for the necessary assessment, protective and corrective actions taken by HP/ Chemistry personnel. 2.0 DISCUSSION 2.1 Primary-To-Secondary Leak Assessment 2.1.1 A P-S leak can be determined basically by either significant activity levels found from routine arialysis of secondary system samples, gross beta analysis of hot well water sample, or from monitoring the main condenser vacuum pump exhaust I vent. I Upon indication of a P-S leak, the magnitude and location of 2.1.2 the leak are the immediate assessment actions. j Determining the location of the P-S leak requires immediate 2.1.3 direct radiation monittring of the main steam lines to detera ne f which OTSG is leaking. 2.1.4 Determining the magnitude of the P-S leak requires both primary and 3econdary coolant sample analysis for the growth of specific radionuclides.

3.0 REFERENCES

3.1 Babcox & Wilcox Radio Chemistry Manual (B&W 1410) Procedure 8.19. ~' ee-- 200~~0i4~~ 3.0

1720 Revision 0 02/27/78 3.2 TMI Chemistry Procedure SCP 1951. 3.3 TMI Chemistry Procedure SCP 1958. 3.4 TMP HP Procedure HPP 1751. 4.0 OPERATING 'NSTRUCTIONS 4.1 P-S Leak Location Determination. 4.1.1 Upon notification of a P-S leak, meritor each of the four main steam lines outside contair, ment (l' nit I - 332'0" elevation of the Intermediate Building) 4.1.2 Using a portable Beta-Gamma Survey Meter (E-520 with HP-177 side window probe), monitor each of the main steam lines and relay contact readings to the Control Room. If gene al area radiation levels permit, take subsequent readings to determine the increase of activity levels. Complete Section I of Analysis Report. 4.2 Magnitude of Leak Rate Determination 4.2.1 Upon notification of a P-S leak, perform analysis of both primary and secondary coolant samples. Recent primary coolant sample analysis can be used if no major plant changes have occurred in the time since the analysis. 4.2.2 Secondary sauple of approximately 3.0 liters should be obtained from the moisture separator drain discharges (From CE-13). ~ 4.2.3 Na-24 activity concentration, as measured by the Ge-Li Detector System will be used in the determination of the leak rate. 4.2.4 Information on feedwater flow rate (lb/hr) and the number of moisture separator drains pumped forward can be obtained from the Control Room. ~ .~ ~200 015 2.0 e

1720 Revision 0 02/27/78 4.2.5 The P-S leak rate can be calculated using: LR = Amsd { 5.71E 9.52E-3 (X ) } F 7 fw Equation 1 A [8.34 lb/ gal) (60 min /hr) p LR = Primary-Secondary leak Rate (gal / min) A = Na-24 Activity Concentration from the moisture separator msd drains (pCi/ml) A = Na-24 Activity Concentration in the primary system p (uCi/ml) F = Feedwater flow rate (lb/hr. ) f X = # Moisture separator drains pumped forward. f 4.2.6 To obtain a more accurate determination of the P-S leak rate, a fresh sample of primary coolant should be obtained for Na-24 analysis. As a follow-up, the following equation will provide a more accurate leak rate: LR = Amsd { 5.E4E (1.19E-3(X ) - 9.73E-3(X ) } F, b f f Equation 2 A (8.34 lb/ gal) (60 min /hr) I where L.R. = Primary-Se:ondary leak Rate (Gallon:/ min) i A = Na-24 Activity Concentration from the moisture separator msd drains (pCi/ml) A = Na-24 Activity Concentration in the primary coolant p (pCi/ml) F = Feedwater flow rate (lb/hr) f X = # Moisture separator drains pumped back.to the condensor b and polisher. X = # Moisture separator drains pumped forward f 2 0 0 0.1,6 3.0 ,e-o=a- +~w-o="

1720 Revision 0 ~.: 02/27/78 4.3 Confirming Leak Rate Determination (H ) 3 3 (Tritium) determination will provide good leak rate sensitivity 4.3.1 H 1 - since the H concentration in the secondary system should 3 buildup linearly with time. The use of H as a leak rate 3 activi ty monitor, however, is recommended only when the H3 -2 level in the primary coolant is > 10 Ci/ml and only as a confirming analysis because of the time required for H3 to reach detectable levels in the secondary. 4.3.2 Upon indication of a P-S leak, obtain a sample of the secondary coolant (main steam) from CE?s and CE16 noting the time of sampling. Perform Tritium Analysis using Procedure SCP 1951 and record the H activity as the baseline for the growth 3 buildup of H ' 3 4.3.3 Af ter a suitable time for growth of H3 (s e Ngure I), oMain a sample of the secondary and a sample of the primary notir the time of sampling. Perform H rnalysis and calculate the 3 leak rate. 4.3.4 The leak rate can be determined from the growth buildup of H3 activity in the secondary: h l -Asl) LR = Vs (As2 Equation 3 Ap (T2T1 ) ~ LR = P-S Leak Rate (gal / min) V = V lume f the Secondary (gal) s A =H Activity Concentration in the secondary system main s 3 steam. (pCi/ml) A =- H Activity Concentration in the primary system (pCi/ml), p 3 ~ T = Time of sampling H Activity Concentration. _ i ~- ~ ~ 3 4.0 --..ea m_e

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1720 Revision 0 02/27/78 Form 1720-1 PRIMARY-SECONDARY LEAK RATE ANALYSIS 1. Rad-iation Monitoring Data (Main Steam Lines)

  • Time Time MS MS lA 1A MS MS 2A 2A --

MS lB 1B -- MS Mb 2B 2B

  • E520 Survey Meter - contact readings II.

Na-24 Leak Rate Determination LR = Amsd { 5.71E 9.52E-3 (X )} F lb/hr 7 7 6Ci ^p --iiii- (8. 34 1b/ gal) (60 min /hr) gal / min. III. Na-24 Leak Rate Determination - 2 LR = A 5.84E {l.19E-3(X )-9.73E-3(X }}}F lb/hr msd b f g N(8.34 lb/ gal) (60 min /hr) A ml p gal / min. I IV. H Leak Rate Verification 3 LR = V gal { (A )-(^sl )I= s s2 pC1 A iiil-~ { (T )-(T) )} 2 gal / min. e. -.4 ~' - 6.0 200 019-- ...}}

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