ML20150B630

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Evaluation of Radioiodine Measurements at Pilgrim Nuclear Power Plant
ML20150B630
Person / Time
Site: Pilgrim
Issue date: 10/31/1978
From: Cline J, Pelletier C, Voilleque P
SCIENCE APPLICATIONS INTERNATIONAL CORP. (FORMERLY
To:
References
NUREG-CR-0395, NUREG-CR-395, NUDOCS 7811020116
Download: ML20150B630 (88)


Text

NU REG /CR-0395 EVALUATION OF RADIOIODINE MEASUREMENTS AT PILGRIM NUCLEAR POWER PLANT I

C. Pelletier P. Voilleque J. Cline R. Hemphill Science Applications, Inc.

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Prepared for U.S. Nuclear Regulatory Commission 781102oli4 1

NOTICE l

This report was prepared as an account of work sponsored by

- the United States Government. Neither the United States nor the United States Nuclear Regulatory Commission,nor any of  ;

their employees, nor any of their contractors, subcontractors, or their employees,- makes any warranty, express or implied, norassumes any legalliability or responsibility for the accuracy, completeness or usefulness of any information, apparatus, pro-4 duct or process disclosed, nor represents that its use would not infringe privately owned rights.

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Available from i' National Technical Information Service Springfield, Virginia 22161

-Price: Printed Copy $6.00; Microfiche $3.00

.The price of this document for requesters outside of.the North American Continent can be obtained from the National Technical Information Service.

l NU REG /CR-0395 RR I

l EVALUATION OF RADIOIODINE MEASUREMENTS AT PILGRIM NUCLEAR POWER PLANT C. Pelletier P. Voilleque J. Cline R. Hemphill Manuscript Completed: September 1978 Date Published: October 1978 1

Science Applications, Inc.

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NES Division l Rockville, MD 20850 l l

Division of Site Safety and Environmental Analysis Office of Nuclear Reactor Regulations U.S. Nuclear Regulatory Commission Under Contract No. E4-76-C-07-1570

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ABSTRACT An evaluation of radioiodine measurements made for The Boston Edison Company at their Pilgrim Nucicar power plant is presented.

135 Measurements include the nuclides I, I and I ventilation ,

134 I Cs, exhaust air and reactor water. Concentrations of the nuclides i 137Cs, 54Mn and 60 Co in reactor water are included because they were

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readily detectable. The evaluation is made in the same manner as l evaluations of radiciodine measurements made for the Electric Power Research Institute at three other BWRs. Measurement results for the four BWRs are summarized and compared.

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TABLE OF CONTENTS 4

Page No. ,

! 1. INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 i

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! 2. METHODS OF SAMPLING AND ANALYSIS . . . . . . . . . . . . . . . . . 2 1 .

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2.1 Sampling Program. . . . . . . . . . . . . . . . . . . . . . . 2 1,

k' j 2.2 Methods of Sampling and Analysis. . . . . . . . . . . . . . . 3 1

i, 3. RESULTS AND DISCUSSION . . . . . . . . . . . . . . . . . . . . . . 11 t

3.1 Reactor Water . . . . . . . . . . . . . . . . . . . . . . . . 11 -

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i 3.2 Turbine Building. . . . . . . . . . . . . . . . . . . . . . . 12 ,

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3.3 Radwaste Area . . . . . . . . . . . . . . . . . . . . . . . . 20

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f 3.4 Reactor Building. . . . . . . . . . . . . . . . . . . . . . . 33 4

d 4 4. COMPARISON OF PILGRIM RELEASES WITH OTHER BWRs . . . . . . . . . . 37 i +

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? 4.1 Turbine Building. . . . . . . . . . . . . . . . . . . . . . . 37  ;

, 4.2 Radwaste Area . . . . . . . . . . . . . . . . . . . . . . . . 39 i 1

4.3 Reactor Building. . . . . . . . . . . . . . . . . . . . . . . 39 i

Appendix A . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43 i

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e LIST OF FIGURES Page No.

System.......... 6 Figure 1 Simplified Pilgrim Ventilation Exhaust Figure 2 Simplified Ventilation Exhaust System for Pilgrim 7 .

Turbine Building.......................................  !

Figure 3 Simplified Ventilation Exhaust System for Pilgrim 8 Radwaste Area..........................................

Figure 4 Simplified Ventilation Exhaust System for Pilgrim 9 Reactor................................................

Figure 5 131 1 and 1 Releases in Turbine Building Ventilation 13 Exhaust Air Pilgrim Plant, Jan.-Feb. 1975..............

Figure 6 1 and I Releases in Turbine Building Ventilation 14 Exhaust Air, Pilgrim Plant, Feb.-June 1975............. ,

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131 133 Figure 7 I and I Normalized Release Rates in Turbine Build-16 ing Ventilation Exhaust Air, Pilgrim, Jan.-Feb. 1975...

1 Figure 8 I Normalized Release Rates in Turbine Building Ventilation Exhaust Air, Pilgrim, Feb.-May, 1975....... 17 31 1 in Radwaste Ventilation Exhaust Air, Pilgrim Figure 9 21 Plant, Jan.-Feb. 1975..................................

Figure 10 1 I in Radwaste Ventilation Exhaust Air, Pilgrim 22 l Plant Feb.-June, 1975..................................

Figure 11 I Concentrations in Radwaste Ventilation Exhaust 25 Air, Pilgrim Plant, 1/31 through 2/6/75................

131 I Concentrations in Concentrator Room, Duct and in Figure 12 27 Hallway Outside Room...................................

i Figure 13 I Concentrations in Flatbed Filter Room Exhaust 28 Duct and at Entrance to Filter B.......................

Figure 14 I and I Releases in Reactor Building Ventilation 34 Exhau s t Air , Pilgrim , J an . - Feb . , 19 7 5. . . . . . . . . . . . . . . . . .

11 3 1 Releases in Reactor Building Ventilation Figure 15 1 and 35 Exhaust Air, Pilgrim, Feb.-June 1975...................

LIST OF TABLES Page No.

Table 1 \

Sampling Locations and Schedule Pil Pl an t , 19 7 5. . . . . . . . . . . . . . . . . . . . . .................

. . gri m 4,5 Table 2 131 1 Normalized Releases (Cf /Yr/pC1/g) In Turbine Building Ventilation Exhaust Air at Boiling Water Reactors............................. 38 Table 3 I Normalized Releases (C1/Yr./pC1/g) in i Radwaste Building Ventilation Exhaust Air at '

Boiling Water Reactors............................. 41 j

Table 4 131 I

I Normalized Release Rates (cl/yr/pC1/g) in '

Reactor Building Ventilation Exhaust Air At Boiling Water Reactors............................. 42 i

APPENDIX Table A-1 Radionuclide Concentration in Pilgrim Reactor Wa t e r 1/ 2 3-2 /16 / 75. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 43-47 Table A-2 Average concentrations of I-131 In Pilgrim Reactor Water During Sampling Periods. . . . . . . . . . . . . . 48-50 Table A-3 Daily Average Concentrations of I-131 in Pilgrim Reactor Water...................................... 51 131 Table A-4 I and I In Turbine Building Ventilation Exhaust Air, Pild rim Plant 1975....................

52-56 131 Table A-5 1 Releases in Recombiner Room Exhaust, Pil grim Plant, 1975.................................. ...... 57 Table A-6 I Releases in Ventilation Exhaust Air From the Retention Building Pilgrim, 1975................... 58 Table A-7 I In Total Ventilation Exhaust Air From Pil Radwaste Building............................. grim ..... 59-63 Table A-8 I and Cs in Feed to Concentrator......... ... 64 '

l Table A-9 I Concentrations and Release kates in Ventilation l Exhaust from Radwaste " Clean" Areas................ 65 l Table A-10 I Release Rates in Exhaust Air From Turbine Building Sumps..................................... 66

List of Tables, cont'd.

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Table A-ll I Concentrations in Radwaste Tank Vent 67 Header Exhaust.....................................

I I Release Rates in Pilgrim Table A-12 I and 68-72 Reactor Building Contaminated Exhaust..............

Table A-13 I and I Release Rates in Pilgrim Reactor 73-76 Building Clean Exhaust.............................

77 Table A-14 1 11 in Refueling Floor Exhaust....................

131 Table A-15 1 Release Rate in Ventilation Exhaust Air from 78 Cleanup Pump Room.................................. .

131 I Concentrations in the Reactor Building Table A-16 79 Backwash Receiver Tank Vent .......................

Table A-17 I Concentrations in Exhaust From Flat Bed Filter 80-82 Rooms .............................................

131 1 and 133 I Releases in Ventilation Exhaust Air Table A-18 83-85 From the Radwaste Concentrator Room ...............

131 I Concentrations in Exhaust, Room. Air and Table A-19 86 Corridor Air Outside Radwaste Concentrator Room....

131 1 Concentrations Near Entrance To Flat Bed Table A-20 87 Filter Room "B"....................................

i Table A-21 Miscellaneous Grab Samples In Radwaste Area........ 88 1

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i i SOURCES OF RADI0 IODINE AT THE PILGRIM NUCLEAR POWER PLANT i.

1. INTRODUCTION i

In January 1975 we were asked by Boston Edison Company to help i

, locate sources of airborne iodine-131 at the Pilgrim Nuclear Power Plant. The work was carried out in cooperation with Nuclear Safety Associates of Bethesda, Maryland (NSA). Measurements were begun at Pilgrim on January 23, 1975 and continued until June 18, 1975. The work dealt mainly with finding significant sources and with actions to reduce them. An oral presentation highlighting the major findings was presented by Mr. Wade Larson of Boston Edison Company to an EPRI l Advisory Group at the ANS meeting in New Orleans in June of 1975.

Since that time, the desirability of including the Pilgrim measure- i ment results in the same context as the EPRI results* has been expressed by interested parties. In December 1977, John Collins of the Nuclear Regulatory Commission asked that this work be under-t a ken . This report is an account of that work.

Section 2 summarizes the measurement program in terms of poten-tial sources sampled, sampling frequency and duration. Also described  ;

in Section 2 are the methods of analysis. Section 3 contains the j i

measurement results and a discussion of them. Section 4 contains a )

i summary of the measurements in relation to the EPRI measurements at other BWRs.

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  • C.~A. Pelletier et al., SOURCES OF RADI0 IODINE AT BOILING WATER REACTORS, EPRI NP-495, February 1978, 1

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2. MET 110DS OF SAMPLING AND ANALYSIS i 2.1 Sampling Program i

The ventilation exhaust system at Pilgrim was such that 131 I in ventilation exhaust air from major areas could be measured prior to becoming mixed and released to the reactor building vent (RBV).

{ Figure 1 shows a simplified diagram of the overall ventilation exhaust l

system with the sampling points used to measure radioiodine in the i
exhaust from each major area. Sampling was begun in the ventilation ,

1 l exhaust ducts from the turbine building and the radwaste area and in )

). the duct designated as reactor building contaminated exhaust on f January 23, 1975. Sampling of the reactor building clean exhaust and l the refueling floor exhaust was started on February 4 and February 5 l respectively. As will be shown below the exhaust from the radwaste i

  • area was found to be carrying the largest quantity of iodine-131 and t

i detailed sampling in the radwaste area was begun on January 28 to a

isolate sources. Sampling was discontinued on February 8 but started j again on February 11 and continued until February 16. Samples were taken continuously with frequent changeouts. Reactor water was also

] sampled frequently. Sampling frequencies ranged from 2 to 4 samples J l per day, and the samples were analyzed in our mobile laboratory at the '

site. In addition to more detailed sampling in the radwaste area f

i during the period, samples were taken in the exhaust from the recombiner l rooms (2/11 to 2/25) and the augmented off-gas system's retention l

building ventilation exhaust (2/11 to 2/17 and 3/4 to 3/11).

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On February 16 the sampling frequency was decreased to every 3 to 4 days until April 12 when all sampling was discontinued until April 17 when a daily sampling schedule was maintained until April 28.

During the period April 17 to 28 detailed sampling was carried out to isolate sources in the radwaste area and reactor building.

[ Prior to May 1,1975 all samples were analyzed with SAI equipment.

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Beginning on Hay 1 and continuing until June 18 when our participation d in the program ended, samples were collec'ed t daily and analyzed with Boston Edison Company equipment.

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Table 1 summarizes the locations and times samples were taken through-out the plant. Also shown are the locations and times radiciodine species were measured and when tritium was sampled in the turbine building exhaust.

Figures 2, 3 and 4 show simplified flow diagrams and sampling points for the three major areas, radwaste, turbine building and reactor building.

2.2 Methods of Sampling and Analysis With some exceptions methods of sampling and analyses were the same as those described in the EPR1 report on Sources of Radioiodine at Boiling Water Reactors (EPRI NP-495, February 1978). The exceptions were the following:

1) Small radioiodine species samplers containing one cartridge of charcoal were used to sample radioiodine throughout the program. Sampling rates varied from 0.5 to 1.0 cfm depending on the air pump used. This technique somewhat overestimated the radioiodine concentration because the iodine retained on the particulate filter was counted with an efficiency as though it were distributed over the first 1 cm of charcoal. Later 1

sampling in which the particulate filter was counted separately, showed that the turbine building exhaust contained the largest fraction (~25%) of total iodine on the particulate filter.

With 25% of the total iodine on the particulate filter the overestimation of the total iodine-131 concentration was 5%.

Turbine building concentrations have been divided by 1.05 when single charcoal cartridges were counted. The overestimation for the samples collected from other areas is less than 5% and no correction has been made.

2) Three types of sampling pumps were used. Two were of the type used in the EPR1 program and the third was a positive displace-ment pump belonging to Boston Edison Company. The positive displacement pumps were used to sample exhausts from the major areas. Toward the end of the program we noticed that our
  • To assure that breakthrough of radioiodine was not occurring, 2 charcoal cartridges were used in series at the flat bed filter exhaust location from 2/1 to 2/7. This exhaust contained a high fraction of organic iodine.

Of 11 samples collected, the average efficiency of the single cartridge was 98.7% with a high of 99.7% and a low of 95.7%.

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_ . _ . _.- ..___.._._......._.____..._..m._ ..._.....m.___..,____.= ._.m. . . . _ _ . _ . _ _ . . . _ . . _ _ . . . _ . . . ~ . _ _ . . _ _ . _ _ . . . . . . .

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l TABLE 1. SAMPLING LOCATIONS AND SCHEDULE PILGRIM PLANT, 1975.

t 2/11- 4/17-LOCATION 12/16i:

f+-1/23-2 / 8-+4 2/16-4/12 4/28  :: 4/29-6/18  :

RADWASTE AREA t

Total l '

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i Concentrator Rm. Exhaust l @A '

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l Concentrator Rm. Air  ;

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, Corridor Outside Conc. Rm. l l Flat bed Filter Rm. Exh.  ! $l l l l Air at FBF Rri. Entrance low (2' above floor) l  ; '

high (12' above floor)  ;  ;

1 Combined exhaust from Resin Storage & R. W. Sumps  :

Turbine Building Sump l Air Exhaust H R. W. Sump Area - *

  • R. W. Corridor Sampler near i Solidipak Entrance @ I I Resin Storage Vent Header Exhaust ** -'

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TABLE 1 (cont.)

2/11- 4/17-LOCATION H1/23-2/B+i 12/16:: 2/16-4/12 4/28 j: 4/29-6/18 :l RADWASTE AREA Sludge Tank Vent Header H

Liquids Concentrator Feed
  • i Feed to FBF -

" Clean" Areas  :

TURBINE BUILDING

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$l l l l l i Total Recombiner Room Exhaust  ! l A0G Retention Bldg. Exh. l j i l RFliCTOR BUILDING

" Contaminated" Exhaust l  : i Tl l l

" Clean" Exhaust  ;  ; ; Tl l l R. W. Cleanup System Back-wash Reevr Tank Vent  ;  !

Refueling Area Exhaust H R. W. Cleanup Pump Room Exh.

H a Combined R. W. Cleanup Pump, . ,

Heat Exh. & Sample Sink Exh.

@ Species sample.

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ADMINISTRATION BUILDING  ;-

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' REACTOR BUILDING VENT TURBINE BUILDING EXHAUST _

/ (184,000 cfm)

(72,000 cfm) \

REACTOR BUILDING 9 l 4 CONTAMINATED EXHAUST (25,000 cfm)

HEPA =  % I EXHAUST REACTOR BUILDING PLENUM 9

CLEAN EXHAUST (25,000 cfm) z @ ~

RADWASTE AREA 9 EXHAUST (28,000 cfm)

HEPA  :-  %

. REACTOR BUILDING 9 i

j REPUELING AREA (27,000 cfm)

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i 9 SAMPLING POINT i

i FIGURE 1 SIMPLIFIED PILGRIM VENTILATION EXHAUST SYSTEM

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i o- o O O RECOMBIt1ER ROOtiS 34000cfm(L) 38,000cfm(L)

AND DEMIN CELLS I%3400cfm Y

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1 PIGISTER 0 N15000cfm 10 EXHAUST REGISTERS @ %5000cfm MAIN STOP VALVES LOW PRESSURE TURBINES l AND CONDENSERS N3600cfml HIGH PRESSURE TURBINE I MOISTURE SEPARATERS l

L_ MVP, SAMPLE SINK AND SJAEs O- SAMPLING POINT FIGURE 2 SIMPLIFIED VENTILATION EXHAUST SYSTEM FOR PILGRIM TURBINE BUILDING l

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4 hTOTAL RADWASTE l AREA TO PLENUM l(28,000 cfm) i HEPA FILTERS I I I I I

SLUDGE TANK VENT HEADER J l l r---------  ;

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l I i l I I l I I CONCENTRATOR l l R0011_{ e 6450 cfm(T)J l

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t h HALLWAY l MONITOR TANK RMS.

! l l RECEIVER TANK RMS.

l n e 700-2900cfm(Lpl I

[~~ CHEM TANK RMS.

l I I l o l R.W. CONTROL AREA FLATBED L-------

I FILTERS 4400cfm(L) 1000cfm(T)

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i i l L SPENT RESIN STORAGE T.B. SUMP AREA SLUDGE TANKS & PUMP TANK AREA, R.W. SUMP DISTILLATE PUMP l AREA SOLIDI PACK AREA Q SAMPLING POI'fT IN EXHAUST DUCT S AREA SAMPLI.T POINT FIGURE 3 SIMPLIPIED VENTILIiTION EXHAUST SYSTEM FOR PILGRIM RADWASTE AREA 8

i R.B. CONTAMINATED EXHAUST R.B. CLEAN EXIIAUST o c o 0

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A ALL OTIIER R.B. AREAS 000cfm TIP ROOM PIPE TUNNEL g

E S# *- 23' LEVEL l

l16,400cfm R.W. BACKWASII 1000cfm i RECEIVER TANK ----*

RM. & VENT l l

LP L IIT. EXCII . RM.

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l6600cfm b

l R.W. CLEANUP Q___ IIEAT EXCII.

ROOM AND l

g SAMPLE SINK l1400cfm R.W. CLEANUP PUMP ROOM <>- S AMPLING POINT l

FIGURE 4 SIMPLIFIED VENTILATION EXIIAUST SYSTEM FOR PILGRIM REACTOR BUILDING l

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method of measuring flow rate (a rotameter) caused the flow rate on the positive displacement pumps to decrease during the j l measurement. This led to an underestimate of the volume sampled. An underestimation of the volume leads to an over-estimation of the concentration and release rate. The volume underestimation for each pump was measured by comparing the i volume measured with the rotameter readings (before and after l

sampling) and the integrated volume measured by the gas i

meter at the outlet of the air pump. The corrections to the j measured concentrations for the affected sampling points were as follows:

Radwaste total exhaust- 0.89

Turbine building total exhaust- 0.84
Reactor building contaminated j exhaust- 0.84 1 1

l< The pump used for the reactor building clean exhaust was also  !

j a positive displacement pump but the gas meter was malfunction-1

ing. The sample volumes used were those determined using the j rotameter, and the reported concentrations may be somewhat high.

i 3) After February 16 we relied on plant measurement for I i

f concentrations in reactor water and after April 28 for I

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concentrations in air samples. Prior to February 16 inter-

] comparisons between the results of SAI and plant measurements 4 were made. Intercomparisons showed comparable results.

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3. RESULTS AND DISCUSSION i

3.1 Reactor Water l

Table A-1 in Appendix A shows concentrations of I in reactor water for each sample taken from 1/23 to 2/16/75. Also shown are con- ,

133 I, 134Cs, 137Cs, 54 Mn and 60 centrations of Co. Counting schedules I 131 were used such that 1 concentrations could be determined with a ,

single sample count. Typically, this meant that decay times between sampling and counting were quite long, i.e. on the order of several days. The long decay time precluded a meaningful analysis of the shorter lived iodine nuclides like I, and I and 1 'I. All samples were analyzed with SAI counters at the site, i 131 Table A-2 shows average I concentrations in reactor water for the air sampling periods used through April 29. The averages are those used

  • 131 for normalizing I release rates later on.

Table A-3 shows daily average concentrations of 131 I up through May 17. Although air measurements were collected for another month, reactor water concentrations are not available after May 17.

Reactor water concentrations of iodine-131 and 133 are shown along with power level and release rates from turbine building and radwaste area in Figures 5 through 10. Release rates are computed by multiplying 1

the I concentratio2 in pCi/cc by the ventilation air exhaust rate in ec/sec. Figures 5 and 6 show turbine building measurements. The promin-ent feature of the time history of I concentrations in reactor water is the spiking that occurred during shutdowns and startup. During the startup on January 23 and 24 the average concentration reached 1.1 pC1/g.

One of the reasons for this unusually high concentration was the fact that during the outage the cleanup pumps malfunctioned, and the only reduction mechanism was radioactive cecay. Concentrations of iodine-131 during the spiking which occurred at the shutdown on January 30 and the startup on April 11 were 1/10 those at the January shutdown. During these later two occurrences reactor water cleanup capability was maintained.

In this regard, if the normal water cleanup capability was lost during a shutdown, it was possible to treat approximately 50 gpm of reactor water with the condensate demineralizers. This 50 gpm flow of reactor water to the condensate storage tank was maintained by the control rod drive hydraulic system. The two cleanup pumps in the normal reactor water l

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i cleanup system have a combined capacity of 220 gpm.

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3.2 Turbine Building i

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' Table A-4 summarizes the results of total turbine building release l j measurements. Figure 5 shows turbine building release rates of iodine-131 )

j and 133 for the period 1/23 through 2/18. Figure 6 shows release rates for the period 2/16 through June 18. It is clear that turbine building  !

j releases did reflect the elevated lodine-131 concentrations during the startup on 1/23 and also on 2/11. It also appears quite likely that the l spike was seen in the turbine building exhaust during the shutdown on l

4 1/30. In this later case, the iodine-133 in relation to iodine-131 was l higher than it was during power operation which suggests a different

} source for the radiolodine during the shutdown.

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i Figure 6 shows that between February 16 and 26 the release rate of l j

iodine-131 increased. This increase can be explained by a corresponding increase in reactor water concentration. lodine-131 release rates in- .

f creased further beginning on March 28. While some of this increase could '

4 have been due to increasing reactor water concentrations during the same t

period, it is likely that the leak rate may also have been increasing.

j On April 10 through April 12, tritium samples were taken to determine the j magnitude of the leak rate, Note that the tritium release rate was l, 2.8pci/sec, Samples taken on May 6 and June 10 showed higher tritium s

release rates which suggests that the overall leak rate from the turbine i building increased over this period. Tritium release rates of this i

1 magnitude are not much higher than those at Vermont Yankee (before their j 1974 refueling outage) and Oyster Creek. (EPRI NP-495) Furthermore.

{ as pointed out in the EPRI report (EPRI NP-495), iodine-131 release rates 7 from the turbine building are affected by more factors than simply the

] leak rate. For example, concentrations of iodine-131 were measured in leaks at Monticello which were higher than concentrations in bulk condensate water.

j This suggests that iodine-131 was being reconcentrated inside steam pipes, i

t prohahly during condensation on inner pipe surfaces. The result is higher than expected iodine-131 releases per unit water leakage.

i On April 26 a charcoal adsorber*was installed to treat air exhausting 4

i through a register in the condenser area near the hi;h pressure turbines 4

o l The adsorber was fabricated with aluminum window screens in the laboratory i It provided approximately \" of TEDA impregnated charcoal filtration at less than 0.1" of pressure drop.

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and main stop valves. There was good reason to believe that about 2/3 of the iodine-131 being released from the turbine building was coming from that area. As shown in Figure 2, ventilated exhaust air from the condenser area is divided and exhausted by two fans. The large duct carrying 72,000 cfm from the condenser area was in laminar flow so that exhaust air fron the high pressure side of the condenser area entered the duct and tended to remain intact. The sampler at the exhaust of the left most fan in Figure 2 typically measured I-131 concentrations that were 1.5 to 2 times those measured at the exhaust of the right most fan. The airflow through the register at the high pressure side of the condenser area was designed to be 15,000 cfm (see Figure 2). We measured and airflow of 27,000 cfm before the filter was installed and 19,000 cfm after the filter was installed.

We were unable to sample the air entering the charcoal adsorber after startup, and therefore, we were unable to measure directly the iodine-131 being removed by the filter. However, using indirect methods, we estimated that it removed 35 to 40% of the iodine-131 in the air passing through it immediately after it was installed. The removal efficiency appeared to decrease with time. We estimate that the filter reduced the iodine-131 release from the turbine building from 10% to 20% during the period 4/26 to 6/18.

To help visualize the relationship between iodine-131 in the reactor water and releases from the turbine building, Figures 7 and 8 show iodine-131 release rates divided by the average iodine-131 concen-tration in reactor water during the sampling period. The carryover factor for iodine-131 from reactor water to steam is 0.8% (T.R. Marrero,

" Airborne Releases from BWR's for Environmental Impact Evaluations, NEDO 21159-2, July 1977). The carryover factor is not used to calculate the normalized release rate in this section but it is used in section 4 when releases are compared to those measured at other plants. Hereafter, these release rates will be known as normalized release rates. The

! absolute release rate of iodine-131 shown in Figure 5 started to increase j as power was increased early on 1/24. The maximum release occurred at about 10:00 p.m. and then decreased rapidly until midnight on 1/25 at  !

l which time it decreased at a lesser rate. The absolute release rate of

iodine-133 increased until the end of 1/27 and then decreased rapidly until it increased on 1/30 presumably in response to the increase in l

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d iodine-133 at shutdown. Figure 7 shows the normalized release rates l l of iodine-131 and 133 for the same period. Even though the absolute ,

{ release follows the lodine-131 spike in the reactor water, Figure 7 f shows that, per unit reactor concentration the maximum was not reached until the end of 1/25. The fact that the maximum normalized release rate of iodine-131 was not reached for 2 days may have been due to the leak j rate being a function of power and/or due to a holdup in the appearance of the radiciodine in the ventilation exhaust air as discussed in EPR1 NP-495. The fact that the normalized release rate of iodine-133 toward I the end of 1/27, when release rates appeared to have reached an equili-j brium, was only 20% of that for iodine-131 supports the holdup theory.

The behavior of iodine-133 and 131 after the startup on February 11 also

support a holdup theory. After the startup the ratio of the iodine-133 and 131 normalized release rate was approximately 0.3, and it took 4 days
to reach that ratio.

1

As pointed out above, the absolute release rate increased from

! February 16 to 25 (see Figure 6). Figure 8 shows that the increase was due to increases in reactor water concentration. However, beginning on February 25 the normalized release rate started a gradual increase i

which lasted until April 12 when sampling was discontinued temporarily.

We can speculate that the reason for this increase was a gradual 1

! increase ir. the leak rate. It may also have been due to the slow j development of a leak from a system where iodine-131 reconcentration was j high, for example, extraction steam lines or drain lines, i A sample of the chemical form of radiciodine was collected from 4/10 to 4/11. The results were as follows:

2 4

131 133 I I 4

j Particulate filter 26.4% 33.0%

, 1 52.7% 51.4%

2 i HOI 17.1% 13.3%

l Organic 4.0% 2.4%

Total Release Rate 8.110.4(-2) '2.2 0.1(-1) l The chemical form of the radiolodine is typical of the form seen in
ventilation air from condenser areas at other BWRs (EPRI NP-495).

j Particulate and elemental were the a ajor contributors and organic j contributed only a few percent. I 18

. - ... . . . - . = - .- . . . - .

l l

Table A-5 and A-6 show the release rates of iodine-131 measured in the ventilation exhaust from the two recombiner rooms (A-5) and the building housing the charcoal delay beds known as the retention building.

The average release rate in the ventilation exhaust from the two recom-

-5 Ci/sec, and was approximately .05% of iodine-131 biner rooms was 6x10 in the total turbine building ventilation exhaust air. The iodine-131 in ventilation exhaust air from the retention building was barely close to typical detection limits (~10

~

pCi/cc) most of the time. The sample 4 taken from 3/4 to 3/5 was 10 to 50 times higher than the other 13 samples.

The average release rate for all the periods was 2.9x10' uCi/see which is approximately 2% of the iodine-131 released from the turbine building over the same period. If the 3/4 to 3/5 sample were excluded the retention building would have contributed only 0.2% of the total release. The release rate from the retention building at Vermont Yankee also was a l negligible contributor (less than 1%) to the total lodine-131 release.

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Table A-7 in the Appendix shows release rates of iodine-131 in total j l ventilation exhaust air from the radwaste area. The data are plotted as <

! a function of time'in Figures 9 and 10. During the period 1/23 through 1/30 i the radwaste area was the largest single source of iodine-131. Beginning late on 1/30 sampling was begun in the duct carrying exhaust air from the

{

i room housing the concentrator. The results of these measurements are also j shown in Figures 9 and 10.

(Measurements of iodine-131 in the concentrator 1

room duct are listed in Table A-8.) Note that from 1/31 to mid-March the iodine-131 in the concentrator room exhaust duct accounted for virtually i i

all the iodine-131 from the radwaste area. Early in February an adsorber i

of silver zeolite was installed in the vent for the noncondensibles from j

the evaporator. The vent exhausted into the room ventilation exhaust duct.

i i

After installation, the release rates of iodine-131 from the concentrator room were no lower than they were prior to installation. Therefore, the ,

vent exhaust was not a significant source of iodine-131 nor was a leak i

from anything but the clean steam heat source visible. Nonetheless the j

a concentrator was obviously the dominant source of iodine-131 in the i

radwaste area most of the time.

Note in Figure 10 that beginning in mid-March other sources of fodine-131 contributed more than the evaporator to the total release from 1 the radwaste area. This was also true for the period May 8 through May 18.

3 i Except for a sample collected on April 27, no samples were collected in the q

concentrator room exhaust duct from April 10 to May 8. However, a single I

sample was taken from the concentrator room exhaust taken on April 27, and j it showed a comparable release rate to the total exhaust. Figure 9 shows .

j that during the sampling period centering on midnight of February 3 other

} sources contributed more than the concentrator.

4. .

l Before discussing what other sources might have been significant in j

4 radwaste we should discuss the concentrator as a source. The concentrator 2, is used to treat floor drain vaste and solutions from condensate deminer-i alizer regeneration. Concentrator bottoms were pumped from their holding

tank to a Solidi pack. A Solidi Pack retains insoluble materials for '
disposal as solid waste. Soluble materials including radionuclides such 1

as cesium and fodine are returned to radwaste for further treatment. This j

4 process acted to concentrate the soluble radionuclides so that the feed to the concentrator had higher concentrations of iodine-131 (and cesium 20

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, 16 20 24 2e 4 8 12 16 20 24 2R 4 8 12 16 20 24 28 4 8 12 16 20 24 28 4 8 12 16 20 FEB RUARY ' MAFCH> APRIL MAY JUNE FIGURE 10 131 1 IN RADWASTE VENTILATION EKHAUST AIR, PILGRIM PLANT FEB. - JUNE. 1975

nuclides) than were present in reactor water alone.

Iodine spiking was also a mechanism whereby iodine-131 concentrations in the feed to the concentrator could be increased above normal levels.

Higher than normal levels were carried over during startups, and, as discussed above, it appeared that some iodine-131 was carried over to the turbine side during shutdowns. However, because of the short dura-tion of this carryover these contributions to the load of iodine-131 on the condensate demineralizers were probably small compared to that due to the need to pump a nominal 50 gpm of reactor to the hotwell to augment or replace the normal reactor water cleanup system during shut-downs. In our experience the use of condensate demineralizers for reactor water cleanup during shutdown is unique to the Pilgrim plant.

Note in Figures 9 and 10 that the highest releases from the rad-waste area occurred after shutdowns. Levels reached 0.15pci/sec three days after the startup on 1/23. During the previous shutdown reactor water levels exceeded 1 pCi/g due to the fact that no cleanup systems were in service. During the outage beginning on 1/30 the highest release rates ( .04 pCi/sec) occurred 4 to 5 days after reactor water concentrations reached 0.15 pC1/g. After the startup on 2/11 iodine-131 release rates reached about 0.1 pCi/sec about five days after the iodine-131 in reactor water peaked at 0.15 pCi/g. After that period releases from radwaste were relatively low during the period 2/17 through 4/11 when the reactor was run at fairly steady power. It wasn't until seven days after the April 15 shutdown when reactor water levels reached 0.65 pC1/g that the release rate from radwaste became the dominant source again. We were not able to measure routinely the release rate in the ventilation exhaust air from the concentrator room during the period 4/22 - 4/24 but the measure-ment made on 4/27 did account for the release from radwaste so that the concentrator could have been the source. On the other hand we know that other sources probably did contribute to the release from radwaste. For example, the high release rate on May 15 may have been due to sources other than the concentrator. Other sources are discussed below. The reason for the high release rates in mid June is unknown. They do not appear to be associated with a shutdown. They tiay have originated from other sources or the leak rate from the concentrator may have increased.

The apparent correlation of maximum iodine-131 release rates from radwaste with high iodine-131 levels in reactor water due to shutdowns I

(and startups) suggests that of the two concentrating mechan 1sms, that 23 l

i 1

I i

is, the Solidi Pack and the use of condensate demins for reactor water i I

cleanup during outages, the latter was the more important for lodine-131. l In fact, both mechanisms acting together probably caused the higher than l,

normal releases. Because of the longer half life of cesium-137 one would expect the Solidi Pack to concentrate it more than the iodine-131. Table l l

j A-8 in the Appendix shows the concentrations of cesium-137 in the feed to

! the evaporator. Ratios of concentrations in concentrator feed to current f

l reactor water were 3.5, 3.2 and 45 for sampling dates 2/5, 2/7 and 2/15.

. f For cesium-137 the ratios were 20, 20 and 1700. These results support ,

, the hypothesis that the Solidi Fack concentrated soluble fission products. '

With regard to other sources within the radwaste area it was suspected f that the exhaust from the flat bed filter rooms was a significant source a

j of iodine-131 because fairly high concentrations were measured from time

) to time. (see Figures 9, 10 and 11) The air in the exhaust duct was j

poorly mixed, that is laminar flow conditions prevailed. The degree of 6 l e

1 mixing .in a duct is determined down stream by releasing helium'into,a j duct and observing the concentration down stream. A well mixed duct j shows a fairly rapid increase to a constant concentration during the release. A poorly mixed duct shows a highly variable concentration

{ during the, release. The release rate, computed by multiplying the con-l centration by the duct flow rate is only valid if the air in the duct

)

i is well mixed, and the measured concentration is applicable to the total

< air flow. However, it seems reasonable to assume that if the concentration 4

in the exhaust duct from the flat bed filter rooms tracks the release rate 1

or the concentration in total radwaste exhaust then the flat bed filter 1

j room exhaust may have been a significant contributor to the total release.

5 During the period 1/31 through 2/6 samples were taken simultaneously in

.i j

the flat bed filter exhaust, the concentrator room exhaust, the combined

exhaust from the spent resin storage, sump and Solidi Pack areas and the f combined exhaust from the remaining areas of radwsste, including monitor I and collector tank rooms, turbine building sumps and access areas. The i

j exhaust from these areas was termed clean exhaust. Figure 11 shows the concentrations of iodine-131 measured in these areas along with the con-

, centration in the total radwaste exhaust. Except for the sample taken be-i 1

4 tween 0930 and 1930 on 2/3 the concentration in the total exhaust tract

the concentration in the concentrator room exhaust duct. Actually, Figure 9 4

1 i

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-11 l I I I I I l l I I l l 10 1/31 2/1 2/2 2/3 2/4 2/5 2/6 131 I CONCENTRATIONS IN RADWASTE VENTILATION EXHAUST AIR, PILGRIM PLANT, 1/31 through 2/6/75 FIGURE 11 I

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shows this correlation better. Note in Figure 9 that, except for the f j 2/3 sampling period the concentrator room accounts for nearly all the iodine-131 from the radwaste area. The flow rate in the cican exhaust j was measured to be 14,700 cfm and the air in the duct was mixed. During 4

the period in question the release rate unaccounted for in the concentrator

room exhaust was .014 pCi/sec. The concentration in the clean exhaust was i

-9 '

j 1.2 x 10 uC1/cc, which when multiplied by the flow rate of 14,700 accour:-

4 for 0.0083 pCi/sec. This leaves .0057 pC1/sec for the rest of the exhaust to account for the total. If the source were the flat bed filter exhaust the I

{ effective flow rate to account for the release rate would be 130cfm. There-

{ fore, although concentrations in the flat bed filter exhaust were high at j times the effective flow rate is very low and the concentration to the l

4 total release rate was small. It seems likely that the increase in iodine-131 in the clean exhaust may have signalled the appearance of a batch of liquid

!, with a relatively high concentration of iodine-131. It was not until 1930 j on 2/4 that this batch of water reached the concentrator. Increases in I iodine-131 concentrations in the exhaust from the spent resin storage and l

1 radwaste sump areas ( the air in which also was not mixed) may also reficct j rhe presence of the water with the higher concentration of iodine-131.

I During the period from late February until 4/10, samples were taken )

l of the air in the concentrator room and of the air in the corridor just

] outside the concentrator room. The reason for taking these samples was a

5 to verify that the concentrator was the source and to determine if the l fodine-131 in the concentrator room escaped to the access area. Figure 12 l shows the concentrations. Except for the two sampling periods from 3/18 j to 3/25 the concentration in the exhaust duct was virtually the same as i

that in the room. This shows that the lodine-131 from the leak in the

} concentrator was uniformly mixed throughout the room. The iodine-131 1

j concentration in the corridor outside the room showed the same general j

t trend as the iodine-131 concentration in the room indicating that there l was probably some air flow out of the room into the corridor.

]

4 A similar type of sampling was carried out across the corridor at the j flat bed filter room entrance. Samples were collected at two locations i

near the entrance, one about 12 feet above floor level and some 7 feet from t

the entrance to the room itself. The other sampler was located at 2 feet l above floor level and right at the entrance. Figure 13 shows the results.

1 26

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FIGURE 12 27

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- - -- UNTRANCE 12' ABOVE FLOOR j 10 -8

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, 16 20 24 28 4 8 12 16 20 24 28 4 8 12 16 20 24 FEBRUARY MARCH APRIL I CONCENTRATIONS IN FLATBED FILTER ROO*tEXHAUST DUCT AND AT ENTRANCE TO FILTER B.

FIGURE 13 28

The concentrations measured by the sampler at the entrance closely tracts the concentrations in the exhaust duct from the room (correlation coeff. ,

r = .94) but are a factor of 10 lower. In contrast the concentrations measured at the 12 foot elevation and 7 feet from the entrance were not as well correlated (r = 0.82) to concentrations in the exhaust. It is interesting to note that the unaccounted-for release rates from radwaste* l from 3/5 to 4/11 are better correlated to the concentrations measured at the 12' elevation outside the flat bed filter room (r = .68) than in the corridor outside the concentrator room (r = .018), or at the 2" eleva-tion in the flat bed filter exhaust (r = .52) or the exhaust itself from I the flat bed filter rooms (r = .67). This suggests there may have been j other sources than the flat bed filter. It should be remembered that I release rates during this period were low compared to previous periods, and one might expect other lesser sources to become apparent.

Figure 10 shows that on April 22, six days after the 4/15 shutdown during which reactor water concentrations reached 0.75 pCi/g, the total release from radwaste increased to 0.24 uCi/sec. During this period access to the radwaste area was difficult due to high airborne concentrations.

However, we were able to collect some samples in the radwaste area on 4/23 through 4/27. Two samples, one in the sump room and one in the sump room

-8 exhaust taken on 4/24 had an average concentration of 2.5x10 Ci/cc.

4 Camples taken in the exhaust from the two flat bed filter rooms on 4/23 also had relatively high iodine-131 concentrations (4.8x10~ pCi/cc).

However, also discussed above concentrations of this magnitude had been measured in the flat bed filter exhaust on previous occasions and because of poor mixing the flow rate applicable to the measured concentration was small, there was little effect on the total release. The exhaust from the spent resin storage area also had a relatively high concentration of iodine-131 on 4/24 (1.8x10~ pC1/cc). The area housing the radwaste distillate pump which is on the floor above the sump area also had a relatively high concentration (1.6x10~ pC1/cc). On 4/25 iodine concen-trations were still as high as on 4/23 and 4/24 in the sump and distillate pump areas (3.1x10~ and 2.0x10~ pri/cc respectively). Floor drains were sealed and hydrazine was used to decontaminate these areas. The I

  • The unaccounted-for' release rate is the difference between the total release rate and the release rate in the concentrator room exhaust.

I 29 l

l.

4 1

i release in total radwaste exhaust began decreasing on 4/24 and 4/25

so that on 4/28 the release was 0.01 pC1/sec or about 1/20 of that f on'4/22 and 4/23. On 4/27 a sample taken in the sump area had a con-centration of 5.6x10 pCi/cc. On 4/27 the concentrator again
appeared to be responsible for most of the release in radwaste although j
the release was only 1/10 that during the period 1/22 - 1/24.

j There doesn't seem to be much doubt that during the 4/22 - 4/26 1

{ period sources other than the concentrator were significant. We do )

now know what the source was. The relatively high release on 5/3, l

j 5/8 and 5/15 may also have originated from sources other than the con- 1 l centrator. Beginning on 5/18 the concentrator again was the dominant i

j source in radwaste.

Normalized release rates during the period of power operation from startup on 2/11 through 4/11 were in the same range as those experienced ,

j at other BWRs. The average normalized release rate was 0.49 g/sec. This l

J is the same as that experienced at Oyster Creek (NP-495 table 1-4).

j During the periods 1/25 to 1/30 the normalized release rates were well i

1 above 1 g/sec and on 1/27 reached 19 g/sec. From 5/1 to 5/18 normalized j release rates were above 1 for all measurements and reached 17 g/sec on 5/2

) and 20 g/sec on 5/14. By definition, the denominator of the normalized release rate is the reactor water concentration during the same period j the air sample is taken. Because there were time delays between the j appearance of high reactor water concentrations (e.g. during spiking) and j their appearance in the radwaste area, the higher release rates from rad-l waste appeared during time intervals when the reactor water concentrations j had decreased. Were individual normalized release rates averaged for these f periods, the resultant average would be artificially high because the j arithmetic average is biased toward higher values. For example, assume that release rates are 0.01, 0.1 and 0.01 pCi/sec for three consecutive j sampling periods and the average reactor water concentrations for the same three sampling periods are-0.01, .1 and 0.01 pC1/g. The normalized release rates are 1.0, 1.0 and 1.0 for the three periods and the average is 1.0 g/sec.

4 i

l

  • An average normalized release rate of 0.49 g/see was measured at Oyster i Creek. The average included a period of 2 months when powdex was used as
a filter medium in the reactor water clean up system.

i ,

l 30 j

-- - . . . . - - - - . _ . - - - - , . . = --

If the appearance of the release rate is delayed one sampling period and it is assumed that 0.01 pCi/sec was the release rate prior to the first j period considered above the normalized release rates for the three periods are 1, .1 and 10 g/sec with an average of 3.7 g/sec. l Other sources in the radwaste area were measured and found to be insignificant. Iodine-131 in the exhaust from turbine building equipment )

I and floor drain sumps was measured from 2/4 to 2/6. The average release rate was 0.00029 pCi/see which was 1.5% of the total release from rad-waste during the same period. ,

Vents from sludge tanks are combined to a header which takes suction I l

from the ventilation exhaust system upstream of the particulate filters.

For the period 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> on 1/28 to 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br /> on 1/29 the average concen-

~9 tration from 1620 on 1/29 to 1700 on 1/30 was 2.2x10 pCi/cc which is 1 a reduction of 140 times the average level measured before the filter was installed. The average release from total radwaste was 0.045 pCi/sec during the time when the vent had an average concentration of 3.1x10~ uCi/cc and 0.039 pCi/sec after the vent concentration had been reduced to 2.2x10~

pC1/cc. This shows the sludge tank vent header was not an appreciable source. l As pointed out above iodine-131 in the clean exhaust was measured from 1/30 to 2/5. Among other sources (including the turbine building sumps discussed above) the clean exhaust also included vents from receiver tanks.

Receiver tanks were shown to be a significant fraction of the total release of iodine-131 from radwaste areas at other BWRs (EPRI NP-495). The average release rate from 1/30 through 2/5 was 0.0026 pCi/sec. The average normalized release rate was 0.094 g/sec. Although this was a small contributor to the total release at Pilgrim, 0.094 g/sec is higher than normalized release rates from receiver tanks at other BWRs. Normalized release rates associated with receiver tanks were .0064, 0.055 and 0.017 g/sec at Monticello, Oyster Creek and Vermont Yankee respectively (NP-495).

A sample of the chemical form of iodine-131 was taken in the total i

radwaste building ventilation exhaust from 4/10 to 4/11. The results are as follows: l Particulate filter 2.4%  ;

1 39.3% j 2 '

l HOI 31.8%

Organic 26.6%

Total release 0.0068 pCi/sec 31

The fraction of elemental iodine-131 was higher than that measured in the radwaste exhaust from other BRRs. At Monticello, Oyster Creek and Vermont Yankee the average fraction of 1,2HOI and organic was 20%,14%

and 66% respectively. Chemical form samples were also taken in the exhaust from the flat bed filter (FBF) (2/8 - 2/9) and the concentrator room (2/5) . The results were as follows:

FBF Conc. Rm i'

Part i culate Filter 5.7% 2.7%

1 2

2.7% 24.7%

HOI 2.6% 12 % J Organic 89. % 60.6%

These measurements are more in line with those at the other BWRs (EPRI NP-495). l On 4/25, when radwaste building internal wall surfaces were con-taminated from the leak which occurred on 4/23 and 4/24, a chemical form sample was taken in the area. The results were as follows: 1 Particulate Filter 12.3%

1 45.9%

2 4

HOI 39.6%

Organic 2.2%

Total Concentra. ion 2.210.1(8) pCi/cc i

i 6

l l

32 l l

3.4 Reactor Building Exhaust air from the reactor building is divided into three parts contaminated exhaust, clean exhaust and refueling area exhaust. Tables A-12, A-13 and A-14 in the appendix su=marize the measurements from the three areas respectively. The release t ate f rom the refueling area was only measured for a snort time period. The average release rate was 0.00015 pCi/sec and was only 2.5% of the combined release from the contaminated and clean exhaust over the same time period. Sampling was discontinued so that the sampling equipment could be used elsewhere.

Release rates of iodine-131 in the contaminated exhaust were higher  ;

that those in the clean exhaust. Figure.14 and 15 show release rates measured in the contaminated exhaust. Only a limited number of samples were collected to find sources within the reactor building. On 4/23 when release rates were relatively high in the reactor building samples were taken in the exhaust from the cleanup pump room because there was a known leak in that area. Samples were also taken between 4/27 and 5/1 in the pump room exhaust. The exhaust rate from the pump room was measured to be 1400 cfm. Table A-16 shows the release rates measured 4

in the cleanup pump room exhaust. The average release rate was 0.009 pCi/sec.

4 For the same periods the iodine-131 release rate from the contaminated reactor building exhaust was 0.011 pC1/sec. Therefore, the cleanup pumps contributed about 80% of the iodine-131 being released from the reactor i

building. At Monticello, the cleanup pumps were also the dominate source of iodine-131 in the reactor building (EPRI NP-495).

Chemical form camples were taken in the cican and contaminated ventilation exhaust f rom the reactor building from 4/10 to 4/11. The results are as follows:

Contaminated Clean Particulate Filter 6.8% <l%

i 1 61.6% 49.1%

HOI 23.4% 16.5%

organic 8.3% 34.4%

Total Release 5.5 0.3(-3) 3.420.2(-4)pci/sec.

'The comparable chemical forms in reactor building ventilation exhaust air at Monticello was 35%, 32%, 24% and 8.9% for the Particulate filter, l y, HOI and organic respectively (EPRI NP-495). Note that the contaminated exhaust from the reactor building at Pilgrim was filtered through HEPA filters prior to being sampled. Therefore, the 6.8% collected on the 33

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JANUARY FEBRUARY I AND I RELEASES IN REACTOR BUILDING VENTILATION EXHAUST AIR, PILGRIM, JAN. - FEB., 1975 FIGURE 14 34

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particulate filter may have been elemental iodine (R. T. Hemphill, et.al. ,

i i " Surface Effects In the Transport of Airborne Radiciodine at Light Water ,

i Nuclear Power Plants". A final report to EPRI dated May, 1978, to be j published).

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4. COMPARISON OF PILGRIM RELEASES WITH OTHER BWRs.

4.1 Turbine Building 8

in addition to the release rates reported in EPRI NP-495, release rates of iodine-131 in total ventilation exhaust from the turbine building at Oyster Creek were measured for 158 days. These measurements were made from 6/76 to 11/76 as part of another EPRI sponsored program to measure the t persistence of radiolodine chemical forms in the environment. Continuous species measurements were made. These results will be appearing shortly '

in an EPRI report. For the purposes of this summary and comparison, these later Oyster Creek measurements are included with the 207 days of measure-ments reported in EPRI NP-495. i i

Table 2 shows the average normalized release rates of iodine-131 in total turbine building ventilation exhaust air at Monticello, Oyster ,

1 Creek, Vermont Yankee and Pilgrim. All normalized release rates have been j adjusted to a 1% carryover fraction. Only normalized release rates for l power operation from 2/11 to 4/10 are included for Pilgrim. Average j reactor water concentrations prior to shutdowns were used to normalize iodine-131 releases at the other BWR. Release rates measured before covered a relatively short time period, (6 days), and steady state reactor water concentrations were not available prior to startup. After April 26, release rates representative of the turbine building are uncertain because of the charcoal filter that was installed. Shutdown releases from Pilgrim are not included because of the short time periods involved. However, it should be noted that what little data are available (January 30 shutdown) release rates decreased no slower than the rate shown for the other plants. The ave rage rate. of decrease for the other plants when no turbine side main-tenance was carried out was 0.1 days ~ which is equivalent to a 7 day half

' life. After the 1/30 shutdown at Pilgrim, turbine building release rates decreased to approximately .0015pci/sec from pre-shutdown levels of i 0.0075pci/sec within three days.

Table 2 shows that normalized release rates f rom the turbine building at Pilgrim were higher than those at other plants. However, they were only marginally higher than those at Oyster Creek. For all plants except Vermont Yankee the variation f rom the average total release is less than a f actor 2. The very low normalized releases from Vermont Yankee are still a puzzle.

37

i l TABLE 2

) I NORMALIZED RELEASES (C1/Yr/uC1/g) IN TURBINE BUILDING VENTILATION EXHAUST AIR AT BOILING WATER REACTORS i

PLANT _

TOTAL PARTICULATE ELEMENTAL HOI ORGANIC POWER OPERATION j Monticello j (231 days) 31.0 4.0 20.0 3.6 3.3 Oyster Creek 3

(365 days) 60.0 10.0 26.0 18.0 5.0 Vermont Yankee 4 (448 days) 3.5 0.55 2.0 0.38 0.6 Pilgrim j (58 davn) 85.0 22.0 45.0 15.0 3.2 Average Ci/Yr/pCi/g 45.0 9.2 23.0 9.3 3.0

! Ci/Yr @ .005 uC1/g* 0.22 0.045 0.116 0.046 0.014

)

] OUTAGES (with Turbine Side Maintenance) 1 j Monticello j (28 days) 1.6 0.032 0.75 0.46 0.35

! Oyster Creek **

l (60 days) 3.5 0.30 0.53 1.6 1.0 i

j 0.C. Average

Vermont Yankee l (61 days) 0.6 0.055 0.096 0.26 0.18 st Average 1 23 days 1.9 remaining days

, 0.8[1 - exp( .lt)]

For 52 day outage 2.6 0.23 0.50 1.1 0.74 C1/Yr 0 .005 uC1/g 0 013 0.001 0.0025 0.0055 0.0037 DUTAGES (without Turbine Side Maintenance)

Monticello (63 days) 0.18 0.015 0.056 0.072 0.037

Use .2[1 - exp( .lt)]

for 4 80-hr. shutdowns 0.23 0.02 0.07 0.09 0.05 C1/Yr 3 .005 uC1/g . 0.0013 0.0001 0.0004 0.0005 0.0003 Total Annual Release Ci/Yr/pC1/g 47.8 9.5 23.6 10.5 3.9 Ci/Yr @ .005 uCi/g .24 0.048 0.12 0.053 0.020

  • ANS N-237, " SOURCE TERM SPECIFICATION", 1976
    • Docs not include releases from the reheater protection system exhaust.

38

i 4

i i

' I 4.2 Radwaste Area 131 I The concentrator was the major source of I in the radwaste area j during the period of measurement. On occassion, other sources appeared

+ to be dominant , but we were unable to identify them. Howeve r , t hey we re l not continuing sources and were dominant over a relatively short time interval. For the reasons given in the report we believe the releases i l

from radwaste at the Pilgrim Plant were not typical, and because the average j

{ normalized release rates given in this section may be used to project 30 l year average releases of iodine-131 from future plants, the very high a

' releases prior to the February 11 startup and af ter the startup on April 30 are not included in the comparison with other plants. Releases from

$ February 11 to April 14 are included for comparison with other BWRs. This I was a period of sustained power operaticn. Although the period includes the I associated with the spiking during the shutdown of 1/30 the peak concentration was not particularly high. The concentrator was the dominant source during the period, but releases did not reflect the higher concentrations in regenerant solutions due to condensate demineralizers being used for reactor water cleanup during outages. However, it probably

- includes the reconcentration effect of the solidi pack. Table 3 shows the results. Note the chemical forms for Pilgrim are taken from the single measurement in the total exhaust. This probably overestimates the elemental l fraction, because 1) the concentrator room exhaust was the main source of l release, 2) the concentrator room exhaust was mostly organic (61%) and 3)

I when the chemical form measurement was made in the total radwaste exhaust the concentrator room only accounted for only 30% of the total.

The average normalized release from radwaste at Pilgrim was higher than those at the other plants. However, the average release is only about twice as high as Oyster Creek. Releases at Pilgrim and Oyster Creek dominate the average with Monticello and Vermont Yankee having releases 1/5 and 1/7 the average.

4.3 Reactor Building The average normalized release rate from the reactor building during periods of power operation 1/24-1/30 and 2/11-4/14 was 0.53 g/sec. During the outages 2/1-2/10 and 4/18-4/30 the average normalized release rate was 0.36 g/sec. Table 4 compares normalized release rates from reactor building sources with those of other plants. The release rate during l

39

s i

outages at Pilgrim is not included because it is not representative of a l long refueling and maintenance outage. Note that except for Vermont Yankee l total normalized release rates during power optration are less than a factor t

2 from the average. The release rate at Vermont Yankee is 1/6 the average.

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40 . _ . - .

_ _ _ ~.. _ _ . . ._ _ _ - . _ . _ _ _ .. . _ . _ _ _ _ _

TABLE 3 131 1 NORMALIZED RELEASES (Ci/Yr./pCi/g) IN RADWASTE BUILDING VENTILATION EXHAUST AIR AT BOILING WATER REACTORS PLANT TOTAL PARTICULATE ELEMENTAL HOI ORGANIC POWER OPERATION Monticello 0.72 0.0072 0.14 0.10 0.47 (231 days)

Oyster Creek (365 days) 6.8 0.053 1.2 1.2 4.3 Vermont Yankee 1.0 0.01 0.20 0.14 0.66 (448 days) l Pilgrim (60 days) 12. 0.29 4.7 3.8 3.2 Average 5.1 0.09 1.6 1.3 2.2 Ci/Yr @.005pci/g 0.026 0.00045 0.008 0.0065 0.011 OUTAGES )

Monticello 0.021 0.00021 0.0013 0.0027 0.017 Oyster Creek 1.4 0.014 0.084 0.18 1.1 Vermont Yankee 0.4 0.004 0.024 0.052 0.32 Average 0.61 0.0061 0.036 0.078 0.48 C1/Yr @.005pci/g 0.0031 0.000031 0.00018 0.00039 0.0024 Total Annual Release C1/Yr/pci/g 5.7 0.0096 1.6 1.4 2.7 Ci/Yr/@.005pci/g 0.029 0.00005 0.008 0.007 0.014

1) After filtration through HEPA filter.
2) Assumes one long outage as for refueling and maintenance. Short duration outages are included under power operation.

i 41

a-t i

I i

4 TnBLE 4 I NORMALIZED RELEASE RATES (C1/yr/pC1/g) IN l REACTOR BUILDING VENTILATION EX11AUST AIR AT BOILING WATER REACTORS i

l f

j PLANT TOTAL PARTICULATE ELEMENTAL HOI ORGANIC 2

POWER OPERATION l

! Monticello 11.0 3.9 3.5 2.6 0.98 l

(231 days)

! Oyster Creek 5.9 2.0 1.3 0.57 2.0 (365 days)

Vermont Yankee 1.2 0.13 0.26 0.17 0.65 (448 days) s

' Pilgrim 13.0 0.88 8.0 3.0 1.1 (65 days)

Average 7.8 1.7 3.3 1.6 1.2

{ Ci/Yr @,005pci/g 0.039 0.0085 0.017 .0.008 0.006  ;

9 i

OUTAGES Honticello 0.47 0.024 0.14 0.19 0.12 l f Oyster Creek 1.3 ) 0.091 0.17 0.39 0.65 f Vermont Yankee 3.2 ) 0.064 0.58 1.9 0.65 l J .

i Average 1.7 0.060 0.30 0.83 0.47 i

f C1/Yr 0.005pci/g- 0.0085 0.0003 0.0015 0.0042 0.0024 1

3 Total Annual Release f Ci/Yr/pci/g 9.5 1.8 3.6 2.4 1.7 C1/Yr/e.005pC1/g 0.048 0.009 0.018 0.012 0.0085 l

I i

1) Assumes one extended outage as for refueling and maintenance.

4 Short duration outages are included under power operation.

j 2)-Includes containment purge.

i s

42 y,w- . ,

I TABLE A-1 RADIONUCLIDE CONCENTRATIONS IN PILGRIM REACTOR WATER 1/23 - 2/16/75 (LCi/g x 10 1 Std. Dev.)

MONTH / DAY TIME Mn-54 Co-60 I-131 I-133 I-135 Cs-134 Cs-137 Jan. 23 , 2118 0.17 .03 0.422.04 10.3 .4 779t112 -

0.691.02 1.322.06 23 2145 3.54 .13 8.53t.01 534t13 - -

95.0tl.3 194!1 .

23 2340 4.17 .13 7.08!.17 630116 - -

102 2 20911 24 0149- 1.71t.11 3.16!.58 673t17 - -

104!1 215t1 24 0402 1.08 .10 2.311.52 689t17 - -

102!1 209 1 24 0605 1.21!.10 2.08!.42 681t17 - -

100:1 207!1 24 0804 1.211.11 2.14t35 696t17 - -

10011 208!1 i

24 0950 1.31 .12 2.01 .23 843!21 - -

17012 251 1  ;

24 1205 6.17!.19 8.011.26 1385:35 - -

192!4 403t1  !

24 1410 7.06t.18 8.522.10 1266t32 - -

180 3 380!1 24 2032 2.36t.12 3.651.58 645116 - -

110 2 236 1 t.

25 0015 2.22 .10 3.01!.25 27917 81!32 -

76.2!.8 16411 .l 25 1520 0.55t.05 0.892.13 40.8tl.0 47 10 -

20.6 .2 42.4t.3 i

25 1940 0.34t.04 0.65!.10 19.0!.5 38t9 -

13.3 .1 28.5!.2 26 0115 0.251.04 0.53t.05 11.71.3 3627 -

7.7 .2 16.4 .2 26 1125 0.16t.03 0.42!.03 9.33 .23 44!4 -

3.51 .10 7.251.12 26 1620 0.11t.03 0.36!.05 9.291.25 4114 -

2.35t.07 5.14!.10 26 2107 0.161.03 0.43 .02 9.12 .23 40 3 -

1.94!.06 3.87t.09  !

27 0117 0.10t.03 0.35t.02 9.0S .35 37 3 -

1.65 .03 3.55t.08 j 27 0536 0.097!.028 0.30 .02 8.851.22 40.4 2.1 -

1.29t.03 2.63 .07 27 1013 0.099!.026 0.371.01 8.941.22 42.4tl.2 -

1.11!.03 2.38t.07 27 1447 0.1292.027 0.34t.01 8.361.27 43.7 1.7 -

1.00!.03 2.06t.06 ,

27 1818 0.13t.03 0.431.01 8.50t.26 40.321.6 - 0.822.05 1.742.06 28 0012 .11!.03 0.41 .02 7.131.24 30.11.8 -

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L 8 6 6 5 5 4 4 4 4 4 4 3 3 3 2 2 2 't '

B T

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. 100 075 38 1 2 0 2 3 6 7 8 4 1 2 2 1 1 3 0 0 0 0 0 0 0 0 0 0 4. 1 1 5 6 2 4

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- 1 t 1  ! t 1 2 2 ! t 1 t  !  ! 1  !  ! t 2 n

m_ M 0 6 9 3 4 5 7 5 0 0 0 4 3 8 1 1 7

9 8 9 0 6 8 1 7 7 4 0 2 4 3 3 4 7 9 3 7 0 8 0 0 7 1 1 9 5 3 6

. 0 0 0 0 2 5 2 0 0 2 0 0 0 0 0 0 0 1 0 1 4 4 4 m

E 1 1 5 0 0 5 5 5 5 3 5 0 2 5 4 8 4 5 0 8 8 5 0 5 8 _

M 0 0 0 0 3 0 4 4 4 4 4 0 1 1 1 0 3 4 3 3 1 3 0 4 5 I 6 7 8 0 1 2 0 1 2 3 3 6 1 3 7 8 9 0 4 9 3 6 8 2 3 T 1 1 1 2 2 2 0 0 0 0 0 0 1 1 1 1 1 0 0 0 1 1 1 2 2 m

Y 1 1 1 1 1 1 2 2 2 2 2 2 2 2 2 2 2 3 3 3 3 3 3 3 3 A 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 D

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m. _

I TABLE A-1, Cont'd.

MONTH / DAY TIME Mn-54 Co-60 I-131 I-133 I-135 Cs-134 Cs-137 Feb. 14 0670 0.34 .02 0.62t.02 16.6 .4 47.32.3 - 0.511.04 0.96t.03 14 0920 0.28 .02 0.71!.02 15.0 .4 46.72.3 - 0.42t.024 ~ 0.85 .03 14 1445 0.23 .02 0.46t.02 13.0t.3 61.7t.4 -

0.57!.05 1.081.03 15 0108 0.31t.02 0.50 .02 5.34t.13 44.0t.3 --

0.32t.02 0.72t.03 15 0500 0.24!.02 0.34t.03 4.41 .26 37.71.4 -

0.50!.10 0.531.02 t 15 1320 0.682.03 0.60t.01 4.841.30 42.8t.4 -

0.49i.09. 0.58t.03 16 0240 1.89t.05 0.55t.035 5.131.13 50.0 .2 -

0.71!.11 0.55t.04 16 0917 - -

4.07 .10 40.5!.1 -

0.62i.04 -

16 1403 3.56t.08 0.64t.09 8.62!.22 73.7 .3 -

1.12 .06 -

O i

4

I i 3 TABLE A-2 AVERAGE CONCENTRATIONS (pC1/g X 10 )

i 0F I-131 IN PILGRIM REACTOR WATER DURING SAMPLING PERIODS *

's

)

< Average l

Reactor Water Date & Time Date & Time Concentration i On Off (pC1/g x 103) i g_

X l 1-23 2117 1-24 0012 547193 l

! 1-24 0018 0313 664122

(

j 0319 0609 685!6 1 0615 0927 740 63 i

l 0932 1230 1114t383 1236 2107 1099!281

! 2115 2356 462 259 l l 1-25 0005 1-25 1412 160 168 1425 1907 30t15

{

j 1914 1-26 0034 15.415.2 i 1-26 0050 1049 10.5!1.7 l

j 1056 1537 9.31!.03 '

j 1540 2048 9.21t.12 l 2055 1-27 0100 9.10!.03 f, 1-27 0107 0518 8.97 .16 0524 0958 8.90 .06 1003 1431 8.65 .41

, 1434 1855 8.43 10

) 1900 2353 7.821.97

{ 2358 1-28 0424 6.76t.23

! 1-28 0430 0831 7.041.54 i

1 j 0837 1159 7.75!.23 l 1203 1627 7.46t.17 1

1 1631 1959 7.23!.16

2003 1-29 0229 6.94i.26 4
1-29 0234 0706 6.41!.49 {

0710 1105 5.84 .32 j 1109 1712 5.38!.33 j 1715 1-30 0107 5.17 .02 1

1-30 0113 0828 5.18 .31 l

0832 1647 14.8113.5 i 1652 1-31 0006 143 105 j *0N/0FF times are accurate for radwaste & approximate for other samples .

48

.. ~ -- . . - , . -- . - . - - - -

TABLE A-2, cont'd.

Average Reactor Water Date & Time Date 6 Time ON OFF Concentration (pci/g x 10 3) - f 3_

1-31 0010 1-31 0835 163 17 0842 1619 89 20 1641 2-1 0247 44t8 0253 1154 38!1 1200 1637 33.9!6.3 1647 2-2 0938 36.517.9 2-2 0942 2-3 0040 27.3!4.7 2-3 0043 1019 34.8 10.8 1023 1738 16.8!6.2 1748 2-4 0821 19.3 9.7 2-4 0823 1711 22.4 5.2 1714 2-5 0816 22.4!5.2 2-5 0823 1743 16.1 3.7 1743 2-6 0745 16.4!4.1 2-6 0748 1816 17.5 2.6 1816 2-7 0749 13.4 3.3 0800 1824 9.8!1.6 1828 2-8 1148 8.0!1.0 2-11 0215 2-11 1800 54.8!12.4 1805 2-12 0012 123 12 2-12 0015 0542 58.3 6.1 0548 1023 42.1!2.1 1028 1623 42.2 1.4 1631 2-13 0407 41.6 2.3 2-13 0414 0920 33.6 3.1 ,

0923 1344 29.4!2.8 1347 1657 26.2 1.7 1702 2336 22.8 1.8 .

2340 ~2-14 0543 18.1!2.1 2-14 0550 1111 15.8!1.1 1124 1510 14.0!1.4 1 1

49

1

TABLE A-2, cont'd.

i

?

Average 1 Reactor Water Date & Time Date & Time Concentration ON OFF (pC1/g X 103 ) s g_

2-14 1512 2-15 0819 7.6!3.3 2-15 0826 1618 4.6 .3 1627 2-16 0540 4.99121 2-16 0536 1544 6.313.2

! 1553 2348 6.4t3.2 2-17 0000 2-21 1132 5.141.66 j 2-21 1136 2-25 1535 13.1 5.9 l 2-25 1546 2-28 1340 15.3 2.2 2-28 1345 3-4 1303 14.1 1.0 i 3-4 1305 3-5 1950 12.8 .4 f 3-5 1955 3-11 1230 17.4 3.3

, 3-11 1132 3-14 1508 11.9 .7 4

3-14 1512 3-18 1047 1120 i

j 3-18 1055 3-21 1350 12.1!1.9

. 3-21 1403 3-25 1348 12.4!1.1 3-25 1350 3-28 1311 13.8 .5 1 3-28 1317 4-3 1318 13.4 .7 1

4-3 1320 4-10 0844 17.111.9 lj 4-10 0848 4-11 0845 15.5!2.1 i

j 4-11 0848 4-12 0820 17.2!4.5 l 4-17 0925 4-18 0907 485t233 4-18 0910 4-19 0915 235!120 3

4-19 0920 4-20 0905 107!61 i 4-20 0908 4-21 0855 172!138 l 4-21 0858 4-22 0921 84 28

' 4-22 0924 4-23 1003 135 163 i 4-23 1300 4-24 0845 1622124 4-24 1005 4-25 1000 84t14 l

4 4-25 1005 4-26 1005 75 28 4-26 1005 4-26 1417 55

. 4-26 1420 4-27 1020 108t74 4-27 1023 4-28 0918 130!42 f 4-28 092.3 4-29 0858 74137 4-29 0902 4-30 0920 52.5 7.8 50

1:

l' I

TABLE A-3 DAILY AVERAGE CONCENTRATIONS (UCi/g X 10 ! 1 St. Dev.)

0F I-131 IN PILGRIM REACTOR WATER DATE JANUARY FEBRUARY MARCH APRIL MAY 1 34!6 16 12.6 10.1 2

33!11 15 12.8 10.7 3 22!5 13 12.4 18 7 4 26 12.5 11.4 13.6 5 16 4 13 15.4 9.7 6 19 15.5 27.6 16.2 7 9.8!1.6 14.2 17.3 14.9 8 7. 3 11.5 19.9 14.5 l 9 4.4 19 15.8 14.2 10 --

35 17.0 10.9 11 63!12 13.5 14.0 13.3 12 52 4 12 20.4 14.1 13 28!3 11 13.6 18.4 14 15 2 11 13.4 17.3 15 4.9 .4 11 18 18.4 16 5.9!1.7 11 760 15.6

~17 4.1 11 650 12.2 18 4.4 11 320 19 5.1 10 150 -

20 7.4 17 64 21 4.7 10.5 195 55 f

22 33 9.9 20 l 23 391!234 6.9 12.4 250 24 8601112 5.9 14.5 74

[ 25 113 102 15 14.5 94 26 9.9!.7 10 14.5 55 i 27 8.7 .2 18 13 160 28 7.2 .2 18 13 100 1 29 5.9 .4 -- 13 47 30 108 64 --

17.3 58 31 97!22 --

12.5 --

51

TABLE A-4 1 AND I IN TURBINE BUILDING VENTILATION EXHAUST AIR, PILGRIM PLANT 1975 10 DINE-131 100lNE-133 NORMALIZED NORMALIZED (1)~

DATE & TIME DATE & TIME RELEASE RATE RELEASE RATE ON RELEASE RATE RELEASE RATE OFF (DC1/sec) (g./sec ) (UCi/see) (g/sec) 1/23 2108 1/24 0002 5. 61 !. 3 (- 3) 1.02 .18 (- 2 )

1/24 0010 0306 4.13 .02(-3) 6.24! .04(-3) 0312 0616 1.98!.12(-3) 2.882 .16(-3) 0619 0917 2.311.14(-3) 3.12! . 32 (- 3 )

0923 1222 7.59!.38(-3) 6.80t2.40(-3) 1226 2057 4.46!.22(-2) 4.06!1.06(-2) 2104 2345 6.27 .33(-2) 1.36!7.68(-2) 1/25 2354 1/25 1404 3.63 .20(-2) 2.27!2.40(-1) 4.13 .25(-3) 6.45!2.45(-2) 1410 1859 2. 81! .15 (-2 ) 9.36!4.72(-1) 9.28 . 96 (-3) 2.18! .39(-1) 1904 1/26 0034 2.14! .13 (-2 ) 1.39! . 48 (-1) 9.6 ! .72(-3) 2.58! .22(-1) 1/26 0039 1042 1.27 .06(-2) 1.212 .21 6.932 .46(-3) 1.741 .27(-1) 1047 1527 1. 4 7 t . 07 (-2 ) 1.58! .08 9.6 . 64 (-3) 2.26! .19 (-1) 1532 2041 1.19!.06(-2) 1.29 .07 1.02! .06(-2) 2.53! .15(-1) 2046 1/27 0053 1.14 t . 06 (-2 ) 1.25 .06 1.12! . 06 (-2 ) 2.91t . 23 (-1) 1/27 0058 0509 1.17! . 06 (-2 ) 1.30! 07 9.92t . 56 (-3 ) 2.56! .22(-1) 0514 0950 1. 09! . 06 (-2) 1.22 .06 1.101 .06(-2)  ?.67! .18 (-1) 0955 1422 1.14 .06(-2) 1.32t .09 1.19 . 06 (- 2 ) 2.76! .16(-1) 1426 1843 1.06!.06(-2) 1.26! .06 1.212 .06(-2) 2.87! .22(-1) 1851 2347 1.16! .16 9.04!.48(-3) 9.28 .48(-3) 2.62 . 55 (-1 )

2350 0413 9.44!.48(-3) 1.39! .09 8.08! .40(-3) 2.86 .18(-1) 1/28 0420 0823 7.10!.37(-3) 1.01! .10 5.61 .30(-3) 2.03! .11(-1) 0828 1204 6. 2 7! . 33 (-3) 8.08! .48(-1) 4.62 .22(-3) 1.76 .19(-1) 1221 1634 1.02 7.592.35(-3) .06 4.29 .26(-3) 1.751 .11(-1) 1638 .2007 7.42!.38(-3) 1.02 .06 3.14! .17(-3) 1.36 .14 (-1 )

2012 1/29 0219 5.94t.32(-3) 8.562 .56(-1) 2.81 1.30

.15 (- 3) .08(-1) 1/29 0224 0654 5.94!.32(-3) 9.28! .88(-1) 2.31! .14 (-3) 1.16! .15(-1) 0703 1113 6.10! . 33 (-3) 1.05! .08 2.14! .13 (-3) 1.22! .09(-1) 1117 1653 1.14 6.10!.33(-3) .10 1.822 .12 (- 3 ) 1.07! .07(-1) 1708 1/30 0058 5. 78! . 31 (-3) 1.12 .06 1.35 .08(-3) 7,96! .50(-2) 1/30 0103 0820 2.14 .13(-3) 4.14 . 35 (-1) .53! .05(-3) 3.06! .03(-2) 0825 1659 4. 7 8t . 23 (-3) 3.2322.95(-1) 1.352 09(-3) 7.65! .53(-2) 1705 2356 8.082.40(-3) 5.66 4.16(-2) 3.79! .02(-3) 9.60!3.36(-3) 52

I AND I IN TURBINE BUILDING VENTILATION EXHAUST AIR, PILGRIM PLANT 1975 (cont.)

IODINE-131 10 DINE-133 NORMALIZED NORMALIZED DATE & TIME DATL' 6 TIME RELEASE RATE RELEASE RATE RELEASE RATE RELEASE RATE ON OFF (p Ci/ sec) (g/sec) (u C1/sec) (g/sec) 1/30 2359 1/31 0825 1.65! .11(-3) 1.02 .01(-1) 4.46! .22(-3) 1.02 .15(-1) 0832 1649 2.81! .15(-3) 3.15 . 07 (-2) 2.30 .02(-4) 1.222 .44(-2) 1655 2/1 0240 1.12! 06(-3) 2.55! .48(-2) 2/1 0246 1209 1.06! 06(-3) 2.72! .17(-2) 1215 2/1 1654 1.072 08(-3) 3.16! . 63 (-2 )

2/3 1930 2/4 0825 1.40! 07(-3) 7.26!3.67(-2) 2/4 0828 1724 1.65 .01(-3) 7.37!1.78(-2) 1726 2/5 0759 1.78i .09(-3) 7.95!1.89(-2) 2/5 0805 1659 2.13 .11(-3) 1.32! .31(-1) 1704 2/6 0751 1.19 .06(-3) 7.25 1.84(-2) 2/6 0755 1758 .87! .05(-3) 5.00 .79(-2) 2/11 0218 2/11 1737 5.02! .30(-3) 9.12!2.08(-2) 1741 2350 1.49! .01(-2) 1.21! .14(-1) 2356 0513 1.30! . 06 (-2 ) 2.24 .26(-1) 2/12 0522 0945 1.56! .08(-2) 3.71 .26(-1) 2000 '

1609 1.43! .07(-2) 3.38! .20(-1) 1617 2/13 0330 1.07! . 06 (- 2 ) 2.58 .19(-1) 2/13 0340 0855 1.02 .05(-2) 3.04 .32(-1) 0906 1350 8.40! . 48 (- 3) 2.86! .31(-1) 1355 1713 1.10! .06(-2) 4.17! .35(-1) 8.3212.40(-3) 3.90!1.14(-1) 1724 2310 1.19! .06(-2) 5.221 .49(-1) 6.71! .49(-3) 1.86! .46(-1) 2318 2/14 0525 1.77! .09(-2) 9.76!1.20(-1) 2.19! .14(-2) 4.50! i34(-1) 2/14 0534 1515 2.09 .10(-2) 1.40! .14 3.98! .18(-2) 7.68! .96(-1) 1522 2/15 0753 1.65 .08(-2) 2.17 .09 4.42! .21(-2) 9.28!1.76(-1) 2/15 0802 1642 1.14! .06(-2) 2.48! .20 3.36! .16(-2) 8.32! .88(-1) 1649 2/16 0515 1.132 .06(-2) 2.26 .14 3.41! .16 (-2 ) 7.34 .88/-1) 2/16 0520 1557 7.932 . 35 (- 3) l'.26! .64 1.95 .10 (-2 ) 3.42!1.42(-1) 1602 2330 7.96! .39(-3) 1.24! .62 2.621 .14 (-2 )

2325 2/21 1100 8.72! .40(-3) 1.702 .23 2.78! .14(-2) 2/21 1108 2/25 1450 1.46! . 0 7 (-2) 1.11 .50 2.98! .14 (-2 )

2/25 1529 2/28 1330 3.22 .15(-2) 2.10 .32 1.22! .06(-1) 53

I i.

!. I AND I IN TURBINE BUILDING VENTILATION EXHAUST AIR, PILGRIM PLANT 1975 (cont.)

?

)

8 1 l 10 DINE-131 i 10 DINE-133 l

NORMALIZED NORMALIZED l DATE & TIME DATE & TIME RELEASE RATE RELEASE RATE RELEASE RATE RELEASE RATE j ON OFF (u Ci/sec) (g/sec) (uCi/sec) (g/sec) l I

i 2/28 1355 3/4 1045 3.87! .18(-2) 2.'77 .24 1.16! . 05 (-1)

~

3/4 1233 3/5 1910 3.66! .18(-2) 2.86! .16 1.00t .05(-1)

) 3/5 1925 3/11 1045 3.62 .17(-2) 2.08 .41 7.62! . 3 6 (-2 )

{ 3/11 1100 3/14 1435 3.55! .17 (-2) 2.98 .22 8.022 .42(-2) 1 3/14 1455 3/18 1128 3.662 .18(-2) 3.34! .16 7.18! . 3 0 (-2 )

}

3/18 1146 3/21 1437 3.222 .15(-2) 2.66! .44 4.74! .02(-2) f 3/25 1335 3/28 1345 3.30! .16 (- 2) 2.39! .14 7.65 .05(-2) l 3/28 1410 4/3 1235 4.50! .22(-2) 3.36! .24 1.25 .06(-1) j 4/3 1255 4/10 0900 6.14t . 30 (-2 ) 3.59 .44 1.78! .09(-1)

, 4/10 0914 4/11 0915 6.70 . 3 0 (-2 ) 4.33 .62 1.79! .08(-1) 4 1

/ 4/11 0925 4/12 0928 8.082 .40(-2) 4.70!1.25 1.94! . 09 (-1 )

l 4/18 0851 4/19 0837 7.38! .38(-3) 3.14 .16(-1) 9.90i2.70(-4) 4/19 0857 4/20 0850 4.10t .25(-3) 3.8222.19(-2)

{ 4/20 0853 4/21 0843 3.96! .22(-2) 2.30!1.86(-1) 9.70 1.80(-4) 4/21 ?.515 4/22 0858 5.45 . 29 (-2 ) 6.4922.19(-1) 2.93 .19(-2)

4/22 0930 4/23 0905 3.35 .19 (-2 ) 2.49 3.00(-1) 2.43 .14 (-2) 4/23 0940 4/24 1020 7.02! . 38 (-3 ) 4.34 3.33(-2) 8.32!1.36(-3)

, 4/24 1025 4/25 1015 4.83 . 29 (-3) 5.75!1.02(-2) j 4/25 1435 4/27 1029 1.70 .16 (-3) 1.58!1.09(-2) 1 4/27 1029 4/28 0939 1.00! .01(-2) 7.69 2.52(-2) i 4/28 0948 4/29 0840 1.90 .14(-3) 2.5611.30(-2) i 4/29 0845 4/30 0858 3.55 .18 (-2) 6.77!1.06(-1) 4.69! . 30 (-3 )

5/1 5/2 2.77 (-2) 2.772

5/2 5/3 4.12 (-2) 3.78 f 5/3 5/4 9.24 (-2) 4.956 l 5/4 5/5 5.46 (-2) 4.032 l 5/5 5/6 5.71 (-2) 5.88 5/6 5/7 3.36 (-2) 2.10
5/7 5/8 3.95 (-2) 2.604 l 5/8 5/9 6.30 (-2) 4.368
5/9 5/10 6.13 (-2) 4.368 i

i 54 i'

e i

i 1 AND I IN TURBINE BUILDING VENTILATION EXHAUST AIR, PILGRIM PLANT 1975 (cont.)

1 IODINE-131 IODINE-133 NORMALIZED NORMALIZED RELEASE RATE RELEASE RATE RELEASE LATE RELEASE RATE DATE & TIME DATE & TIME ON OFF (pCi/sec) (g/sec) (pCi/see) (g/sec) h 5/10 5/11 5.88 (-2) 5.40 5/11 5/12 5.63 (-2) 4.20 5/12 5/13 6.98 (-2) 4.96 t

5/13 5/14 6.55 (-2) 3.53 5/14 5/15 7.31 (-2) 4.20 5/15 5/16 7.22 (-2) 3.96

.5/16 5/17 5.71 (-2) 3.70 5/17 5/18 5.46 (-2) 4.45  :

5/18 5/19 6.3 (-2) l 5/19 5/20 5.88 .(-2) l 5/20 5/21 3.95 (-2) 5/21 5/22 2.18 (-2) .i 5/22 5/23 1.09 (-2) 5/23 5/24 2.44 (- 2) I 5/24 5/25 1.26 (-2) l 5/25 5/26 9.24 (-2) l 5/26 5/27 5.63 (-2) 5/27 5/28 4.20 (-2) l 5/28 5/29 4.45 (-2) f a 5/29 5/30 4.70 (-2) 4 5/30 5/31 7.896 (-2) l l

5/31 6/1 5.88 (-2) j

, 6/1 6/2 5.46 (-2) 6/2 6/3 5.796 (-2) 6/3 6/4 6.552 (-2) 6/4 6/5 5.46 (-2) 6/5 6/6 5.63 (-2) l l

1 6/6 6/7 5.292 (-2) 6/7 6/8 5.54 (-2) 6/8 6/9 5.96 (-2) 6/9 6/10 5.71 (-2) 55

1 I

i I AND I IN TURBINE BUILDING VENTILATION EXHAUST AIR, PILGRIM PLANT 1975 (cont.)

10 DINE-131 10 DINE-133 NORMALIZED NORMALIZED DATE & TIME DATE & TIME RELEASE RATE RELEASE RATE RELEASE RATE RELEASE RATE ON OFF (pCi/sec) (g/sec) (uC1/sec) (g/sec) 6/10 6/11 6.72 (-2 )

6/11 6/12 7.14 (-2)  !

6/12 6/13 5.46 (-2) 6/13 6/14 4.87 (-2) 6/14 6/15 5.04 (-2) 6/15 6/16 5.46 (-2) t 6/16 6/17 6.30 (-2) 6/17 6/18 5.29 (-2)

1) Normalized release rates are determined by dividing the release rate (pci/sec) '

4 by the reactor water concentration UCi/g in Table A-2.

i l

1 i

56

_.. _ _ = . _ _ . . _ _ . . _ . ._. .

i i

i l

11 RELEASES IN RECOMBINER ROOM EXHAUST, PILGRIM PLANT,1975 TABLE A-5 ON OFF pCi/cc pCi/cc 2/11 1026 2/11 1925 8.111.3 (-11) 1.3i0.2(-4) l 2/11 1936 2/11 2328 1.510.5 (-10) 2.4!0.8(-4) 2/11 2336 2/12 0640 1.410.3 (-10) 2.2 0.5(-4) 2/12 0650 2/12 1133 1.510.3 (-101 2.4!0.5(-4) 2/12 1139 2/12 1750 2.0 0.2 (-10) 3.2!0.3(-4) ,

2/12 1720 2/13 0210 1.3!0.7 (-11) 2.111.1(-5) l 2/13 0220 2/13 0822 8.711.2 (-11) 1.410.2(-4) 2/13 0830 2/13 2250 9.010.5 (-11) 1.4 0.1(-4) 2/13 2253 2/14 0725 1.11 .06(-10) 1.810.1(-4) l 2/14 0730 2/14 1512 1.2 0.3 (-10) 1.9i0.5(-4) 2/14 1615 2/15 0303 1.01 .05(-10) 1. 6 0.1(-4) 2/15 0305 2/16 2258 6.1 0.3 (-11) 9.8!0.6(-5) 2/16 2302 2/21 1420 2.710.3 (-12) 4.3 0.4(-6) 2/21 1430 2/25 1200 8.7!0.9 (-12) 1.4 0.1(-5) i 1

J l

57

j 1

J i

1 l TABLE A-6. 1 RELEASES IN VENTILATION EXHAUST AIR FROM j THE RETENTION BUILDING PILCRIM, 1975 1

4 131 7

i 8

# ON OFF pC1/cc pCi/sec 9108 2/11 2300 2/12 0405 9.3 7.4(-12) 4.413.5(-5) f 9110 2/12 1047 2/12 1245 1.110.9(-10) 5.224.2(-4) j 9111 2/12 1250 2/12 1818 2.3!1.1(-11) 1.lio.5(-4) l 9112 2/12 1823 2/13 0125 1.2 0.8(-11) 5.713.8(-5)

! 9113 2/13 0137 2/13 0745 1.8!1.1(-11) 8.5!5.2(-5) j 9114 2/13 0755 2/13 1650 1.6 1.1(-11) 7.5!5.2(-5) l 9151 2/13 1700 2/14 0638 < 1 (-11) <5(-5) 9161 2/14 0648 2/14 1520 1.611.3(-11) 7. 5!6.1 (-5 )

9172 2/14 1525 2/15 0330 < 7 (-12 ) <3(-5)

! 9235 2/15 0337 2/17 0217 4.2 2.1(-12) 2.011.0(-5) i l 9287 3/4 1905 3/5 2155 8.3!0.4(-10) 3.910.2(-3)

{,

9259 2/28 1258 3/4 1900 5. 9!1. 5 (-12 ) 2.810.7(-5)

! 9359 3/5 3/11 3. 9!2. 8 (-12 ) 1.8!1.3(-5) l 4

(

l 1

l 6

e 4

i i

j 58 1______ . _

TABLE A-7 I IN TOTAL VENTILATION EXHAUST AIR FROM PILCRIM RADWASTE BUILDING NORMALIZED DATE & TIME DATE & TIME RELEASE RATE RELEASE RATE ON 0FF (pCi/sec) (g/sec) 1/23 2117 1/24 0012 .0091 .0006 .02 .0030 1/24 0018 0313 .0250!.0015 .0371 .0024 0319 0609 .0118!.0008 .0172 .0011 0615 0927 .0077 .0005 .0104 .0011 0932 1230 .0214t.0014 .0191 .0067 1236 2107 .0259t.0017 .0235!.0062 2115 2356 .0440t.0029 .0950!.0537 1/25 0005 1/25 1412 .0293 .0018 .1822 .1918 1425 1907 .0350 .0024 1.1616!.5808 1914 1/26 0034 .0327!.0020 2.1120!.7216 1/26 0050 1049 .0248 .0016 2.3500!.4048 1056 1537 .0271 .0017 2.8952!.1584 1540 2048 .0552!.0935 5.9664 .3432 2055 1/27 0100 .1510 .0100 16.5440 .9680 1/27 0107 0518 .0700 .0046 7.7528 .4752 0524 0958 .09911.0060 11.0880 .6160 1003 1431 .0810!.0055 9.5040!.7040 1434 1855 .0293 .0018 3.45842.1936 1900 2353 .0237 .0015 3.0184 .4136 2358 1/28 0424 .0304 .0019 4.4792 .2904 1/28 0430 0831 .0293 .0018 4.1360 .3872 1 0837 1159 .0293!.0018 3.7576!.2288 I

i 1203 1627 .0327 .0020 4.3648 .2552 1631 1959 .0564 .0038 7.7528 .4928 2003 1/29 0229 .0483t.0031 6.9520 .4752 1/29 0234 0706 .03381.0024 5.2448!.5192 0710 1105 .0575 .0039 9.7680 .7920 1109 1712 .0417i.0028 7.7176!.6600 1715 1/30 0107 .0575 .0039 11.0880!.7040 1/30 0113 0828 .0293t.0018 5.62321.4576 0832 1647 .0293 .0018 1.971211.7952 59

.* - a .. -..a, 4 - - .m.. , m m m .... ---

i 1

e f

I j TABLE A-7 (cont.) l 4

i i NORMALIZED

} DATE & TIME DATE & TIME. RELEASE RATE RELEASE RATE

! ON OFF (pCi/sec) (g/sec)

. I l: 1/30 1652 1/31 0006 .01121.0007 .0781 .0576 j 0010 1/31 0835 .00582.0004 .0351! .0042 l 0842 1619 .0080!.0005 .08891 .0202 )

j 1641 2/1 0247 .0192 .0013 .43382 .0827 l l

0253 1154 .01691.0012 .4426! .0299 l 1200 1637 .0103 .0007 .30102 .0590 j 1647 2/2 0938 .0094!.0006 .2552! .0572 2/2 0942 2/3 0040 .00651.0004 .23851 .0431 2/3 0043 1019 .01051.0007 .3010! .0950 1023 1738 .0144!.0009 .8536! .3186 i

2/4 0821 1748 .03161.0020 1.6280 .8272 a

  • i 2/4 0823 1711 .02821.0018 1.2500! .2992 i

1714 2/5 0818 .0383!.0026 1.69801 4048 j 2/5 0823 1743 .0226!.0014 1.39041 .3256 1743 2/6 0745 .01581.0011 .9592 .2464 i 2/6 0748 1816 .00911.0006 .5183 .0827 i 1816 2/7 0749 .00551.0004 .4074 .1038 l 0800 1824 .00551.0003 .54741 .0933 j 1828 2/8 1148 .0120 .0008 1.48701 .2024 l 2/11 0215 2/11 1800 .0094!.0006 .16981 .0396 i 1805 2/12 0012 .0034i.0002 .0272 .0030 f 2/12 0015 0542 .0027 .0002 .0468 .0057 3

0548 1023 .0032!.0002 .0752! .0056

! 1028 1623 .0042!.0003 .0977 . 0070 i 1 ,

1631 2/13 0407 .0029!.0002 .0698 10057 i l 2/13 0414 0920 .00211.0001 .0628i .0063 l

} 0923 1344 .00321.0002 .10741 .0123 I 1347 1657 .0049 .0003 .1848 .0158 1702 2336 .00271.0002 .1197 . 0123 2340 2/14 0543 .00201.0001 .1118 . 0141 4

2/14 0550 1111 .0022 .0003 .13901 .0194 1124 1510 .0066!.0004 .47171 .0537 I

60 l . _ . .

TABLE A-7 (cont.)

NORMALIZED DATE & TIME DATE & TIME RELEASE RATE RELEASE RATE OFF (uCi/sec) (g/sec)

ON 2/14 1512 2/15 0819 .00651.0004 .8457! .3696 2/15 08?6 1618 .0105 .0007 2.27901 .2024 l 1627 2/16 0540 .01061.0007 2.1120! .1496 2/16 0536 1544 .0127!.0008 2.015221.0296 1553 2348 .00401.0004 .9328! .4664 2/17 0000 2/21 1132 .00541.0003 1.0384 .1408 2/21 1136 2/25 1535 .0064!.0004 .49721 .2253 2/25 1546 2/28 1340 .00352.0002 .2297! .0352 2/28 1345 3/4 1303 .00402.0003 .28072 .0273 3/4 1305 3/5 1950 .00212.0001 .16542 .0088 3/5 1955 3/11 1130 .00191.0001 .11091 .0220 3/11 1132 3/14 1508 .0029 .0002 .24381 .0202 3/14 1512 3/18 1047 .00251.0002 .22441 .0158 3/18 1055 3/21 1350 .00331.0002 .2693! .0449 3/21 1403 3/25 1348 .00831.0006 .06671 .0730 3/25 1350 3/28 1311 .00751.0005 .54211 .0378 3/28 1317 4/3 1318 .00421.0003 .30891 .0255 4/3 1320 4/10 0844 .00691.0004 .40131 .0493 4/10 0848 4/11 0845 .0061!.0013 .39161 .0906 4/18 0910 4/19 0915 .0147!.0011 .06211 .0320 4/19 0920 4/20 0905 .0088!.0006 .08141 .0466 4/20 0908 4/21 0855 .00671.0004 .03891 .0312 4/21 0858 4/22 0921 .0214 .0014 .02531 .0088 4/22 0924 4/23 1003 .2370 .0150 1.7512 2.1120 4/23 1300 4/24 0845 .2030 .0140 1.24081 .9592 4/24 1005 4/25 1000 .05801.0039 .68111 .1206 4/25 1005 4/26 1005 .03501.0028 .46381 .1760 4/26 1005 4/26 1417 .0250!.0016 .44791 .0343 4/26 1420 4/27 1020 .0271!.0017 .24901 .1716 4/27 1023 4/28 0918 .01581.0011 .12062 .0396 4/28 0923 4/29 0858 .01281.0009 .17251 .0871 4/29 0902 4/30 0920 .01061.0007 .20152 .0326 61

l TABLE A-7 (cont. )

NORMALIZED DATE & TIME DATE & TIME RELEASE RATE RELEASE RATE ON OFF (pCi/sec) (g/sec)

S/1 5/2 .064 6.4 5/2 5/3 .18 17.0 "

5/3 5/4 .085 4.7 j 5/4 5/5 .055 4.0 5/5 5/6 .043 4.5 5/6 5/7 .015 9.4 5/7 5/8 .030 2.0 5/8 5/9 .094 6.5 5/9 5/10 .061 4.3 I

5/10 5/11 .027 2.5 5/11 5/12 .024 1.8 5/12 5/13 .032 2.3 5/13 5/14 .029 1.6 5/14 5/15 .34 20.0 5/15 5/16 .17 9.2 5/16 5/17 .11 7.0 5/17 5/18 .087 7.3 5/18 5/19 .084 5/19 5/20 .080 5/20 5/21 .031 5/21 5/22 .039 5/22 5/23 .065 5/23 5/24 .11 5/24 5/25 .054 5/25 5/26 .057 5/26 5/27 .033 5/27 5/28 .041 5/28 5/29 .060 5/29 5/30 .049

^

5/30 5/31 .023 From 5/1 en samples were counted with BECO equipment and counting errors are not available.

62

' TABLE A-7 (cont.)

NORMALIZED DATE 6 TIME RELEASE RATE RELEASE RATE DATE & TIME (g/sec)

ON OFF (pCi/sec) 5/31 6/1 .014 6/1 6/2 .010 6/2 6/3 .013 6/3 6/4 .021 I 6/4 6/5 .027 6/5 6/6 .023 6/6 6/7 .023 6/7 6/8 .028 6/8 6/9 .016 6/9 6/10 .015 6/10 6/13 013 6/11 6/12 .011 6/12 6/13 .026 6/13 6/14 .089 6/14 6/15 .15 6/15 6/16 055 6/16 6/17 .61 6/17 6/18 .093 1

1 63

l

{

{

131 137 f TABLE A-8 1 AND Cs IN FEED TO CONCENTRATOR i I 1 i  !

{ TIME AND DATE I Cs

\

j 1800 ?/5 6.720.3(-2) 1.0

. 05 (-1)  !

2020 2/5 6.520.3(-2) 9.8to.5 (-2) l 1130 2/7 4 3.5!O.2(-2) 6.520.3 (-2)

I 0430 2/15 2.4 0.1(-1) 1.22 .06( 0) i

, l 4

i e

i 4

i 1

I i

1 l

1 3

i

.i e

a i

t i

1 J

i d

4 64

131 1 CONCENTRATIONS (pCi/cc) AND RELEASE RATES (pC1/sec)

TABLE A- 9 IN VENTILATION EXHAUST FFOM RADWASTE " CLEAN" AREAS ON OFF COFC. REL. RATE 2345 1/30 1010 1/31 3.720.2 (-10) 2.620.1 (-3) 1020 1/31 1806 1/31 3.310.2 (-10) 2. 3 0.1 (-3) 1817 1/31 0200 2/1 3.120.3 (-10) 2.120.2 (-3) 0210 2/1 0920 2/1 2.7 0.2 (-10) 1.910.1 (-3) I 0930 2/1 1725 2/1 4.220.2 (-10) 2.9!0.1 (-3) 1735 2/1 1025 2/2 2.510.1 (-10) 1.7! .09 (- 3) 1038 2/2 2342 2/2 1.li .07(-10) 7.610.5 (-4) 0000 2/3 1725 2/3 1.4! .07(-10) 9.710.5 (-4) 1725 2/3 0655 2/4 1.3! .07(- 9) 9.010.5 (-3) 0710 2/4 1750 2/4 2.0!0.1 (-10) 1.42 . 07 (-3) 1758 2/4 2210 2/5 4.920.2 (-10) 3.4!0.1 (-3) i l

65

i i'

i f

t i

131

{ TABLE A- 10 I RELEASE RATES IN EXilAUST I AIR FROM TURBINE BUILDING SUMPS l

i

! ON OFF s I 1257 2/4 1738 2/4 2. 3 0.1(-4)

1743 2/4 0730 2/5 1.410.1(-4) 0744 2/5 1630 2/5 3.3!0.7(-4) 1653 2/5 0707 2/6 2.320.2(-4) 0717 2/6 1840 2/6 5.320.3(-4) i J

4 8

I l

I t

i l

l I

i i -

s i

(

I f

i i

l I

l 1

i 66

. _ _ ._ _ ~ _. _ _ _ _ _ _. . _ _ . _ - . _ _ . . . -

l 131 TABLE A-ll I CONCENTRATIONS IN RADWASTE TANK VENT HEADER EXHAUST ON OFF I _

2003 1/28 0229 1/29 4.010.2 (-7) 0230 0540 4. 3!0.2 (-7) 0550 1620 9.8 0.5 (-8) 1624 2343 3.610.2 (-9) 2353 0725 1/30 1.810.1 (-9) 1 0738 1700 1.3 .07(-9) i l

1 l

)

l 2

d l

67

_ ._ _ _ __ . ~ . _ _ . . __ _ . _ - __

131 TABLE A-12 I AND I RELEASE RATES IN PILGRIM REACTOR' BUILDING CONTAMINATED EXHAUST i

10 DINE-131 10 DINE-133 NORMALIZED NORMALIZED DATE & TIME DATE & TIME RELEASE RATE RELEASE RATE ON RELEASE RATE RELEASE RATE OFF (pC1/secx103 ) (g/sec) (pCi/secx103) (g/sec) 1/23 2056 1/23 2354 4.36! .74 .008!.0021 1/24 0002 0258 7.3411.25 .0111.0019

\

l 0304 0558 5.351 92 .0081.0013 0605 0909 3.77 .64 .0051.0010 0915 1213 6.84!1.16 .0061.0027 1220 2045 14.9022.6 .0142.0047 2055 2330 14.9012.6 .032!.0222 2342 1/25 1352 12.90 2.3 .081 .1016 .277! .075

.004t.0023 1/25 1402 1847 20.8013.6 .697!.4300 1854 1/26 0020 14.9022.6 .966 .4200 .5062 .181 .014!.0049 1/26 0029 1030 12.90!2.3 1.226 .3200 .645! .144 .016 .0045 1040 1517 11.80:2.0 1.2681.2200 .535! .173 .0132.0041 1524 2027 14.90!2.6 1.6131.2600 .833 .187 .021!.0046 2038 1/27 0043 21.9013.7 2.394!.4100 1.0901 .255 .028 .0069 1/27 0050 0500 14.9022.6 1.6551.2900 .5951 .155 .0151.0042 l

0506 0940 14.90!2.6 1.6722.2900 .446! .125 .011 .0031 0945 1412 15.90!2.7 1.831!.3300 .655! .149 .015 .0035 i 1417 1827 11.0011.9 1.3021.2200 .9201 .170 .022!.0042 1 1840 2045 9.20 1.6 1.176 .2700 .684 .165 .0192.0067 2112 1/28 0404 12.90!2.2 1.9071.3400 j .940! .170 .0331.0060 1/28 0410 0814

{

t 12.1012.1 1.714.. 3300 .940! .170 .0341.0060 0814 1155 9.9011.7 1.277 .2200 .723! .127 .0271.0058 1158 1618 13.9012.4 1.856!.3300 .9731 .170 .0402.0070 1623 1953 14.90 2.6 2.058!.3600 1.0901 .190 .0471.0098 )

1957 1/29 0210 12.9012.2 1.856 .3300 .8401 .150 .0391.0069 1/29 0215 0642 12.9012.2 2.0081.4000 .734! .130 .0371.0085 0647 1057 15.9012.7 2.713!.5000 .704 .130 .040 .0074 1102 1640 12.90!2.2 2.394!.4500 .6351 .110 .037!.0067 1648 1/30 0048 27.7014.7 5.368!.9100 1.0901 .190 .0641.0115 1/30 0053 0813 7.9311.36 1.529!.2800 .3362 .061 .020 .0036 a

68

TABLE A-12 (cont.)

10 DINE-131 10 DINE-133 1

NORMALIZED NORMALIZED DATE 6 TIME DATE & TIME RELEASE RATE RELEASE RATE RELEASE RATE RELEASE RATE ON OFF (uCi/secx103 ) (g/sec) (pC1/secx103) (g/sec) 1/30 0817 1/30 1615 8.00 1.31 .5462.6000 .3801 .069 .022 .0040 1645 2348 5.161 .89 .0361.0320 .486 .087 .0121.0055 2353 1/31 0816 3.87 .66 .u24!.0050 .208 .036 .0051.00114 I 1/31 0820 1640 3.971 .68 .0451.0141 .099! .024 .005!.00248 1647 2/1 0230 3.67: .63 .083 .0230 0236 1201 4.66 .79 .0121.0210 .0962 .024 .025!.0063 1207 1648 3.772 .64 .1111.0310 1652 2/2 0640 3.47 .60 .095 .0290 .0271 .0094 .012!.0055 2/2 0645 2/3 0035 2.381 40 .087!.0230 2/3 0039 1025 2.981 .51 .0861.0350 1028 1733 7.54!1.29 .449!.2110 1737 2/4 0817 3.97 .68 .2062.1280 2/4 0818 1708 3.901 .66 .172 .0560 ,

1710 2/5 0749 5.161 .89 .230!.0750 2/5 0755 1735 3.471 .60 .2161.0700 1740 2/6 0735 3.081 .53 .1871.0640 2/6 0742 1818 2.181 .37 .124 .0310 1818 2/7 0749 3.572 .61 .266!.0910 2/11 1759 2/12 0005 7.6411.31 .062t.0128 2/12 0010 0532 5.9511.02 .102 .0220 0537 1012 7.3411.26 .1741.0320 1018 1618 8.8211.5 .209 .0370 I

1623 2/13 0357 7.24!1.24 .1741.0320 2/13 0403 0912 7.0411.21 .209!.0430 .724! .191 0351.0096 0917 1338 7.6411.31 .2601.0530 1.0901 .260 .0511.0121 1343 1704 7.2411.24 .2761.0520 .8331 .226 .039!.0107 1708 2326 6.3511.08 .2781.0540 1.590 .270 .044 .0147 2330 2/14 0539 5.9511.02 .328 .0720 2.480! .420 .0511.0090 2/14 0545 1503 6.9411.18 .4652.0930 4.7601 .820 .092!.0200 1506 2/15 0809 5.451 .93 .717 .3910 4.660! .790 .0971.0270 1629 5.061 .87 1.100!.2100 4.460! .770 .111!.0230 l 2/15 0846 69

4 i

t

)

TABLE A- 12 (cont.)

i 10 DINE-131 10 DINE-133 NORMALIZED NORMALIZED j DATE & TIME DATE & TIME RELEASE RATE RELEASE RATE RELEASE RATE RELEASE RATE j ON OFF (pci/secx103 ) (g/sec) (pci/secx10 3) (g/sec) j 2/15 1639 2/16 0530 4.36! .74 .874i.1600 3.7701 .640 . 0812.0175 i 2/16 0536 1544 5.45 .93 .8651.5400 4.660! .790 . 082!.0423 1546 2336 3.271 .56 .5111.3170 3.5701 .610 3 2350 2/21 1100 2.382 .40 .4631.1060 3.670! .630 {

! 2/21 1129 2/25 1545 3.08! .53 .2341.1320 3.570! .610 2/25 1550 2/28 1325 3.27 .56 .214!.0520 8.90011.500 j 2/28 1330 3/4 1245 3.97: .68 .281 .0540 9.160!1.600

! 1248 3/5 1935 6.74!1.15 .5272.0920 51.00018.900 3/5 1937 3/11 1115 3.08! .53 .176 .0500 6.350:1.080 i 3/11 1120 3/14 1527 3.08 .53 .2582.0480 3.270 .810 i 3/14 1532 3/18 1106 2.981 .51 .271 .0470 5.5602 .950 1

, 3/18 1111 3/21 1416 2.981 .51 .246!.0630 3.6701 .640

, 3/21 1421 3/25 1335 3.87! .66 .3121.0630 5.85011.000 1 3/25 1338 3/28 1330 4.071 .69 .295 .0520 6.450 1.160

j. 3/28 1334 4/3 1305 4.071 .69 .3032.0550 7.93021.360 I j 1310 4/10 0812 4.361 .74 .2552.0550 8.820!1.500 j 4/10 0815 4/11 0825 4.671 .81 .302!.0710 8.650!1.500 1

4/18 0900 4/19 0905 33.7015.80 .1441.0910 2.9801 .530 j 4/19 0907 4/20 0858 13.90!2.40 s

.1292.0910 .7732 .220 j 4/20 0900 4/21 0822 24.8024.20 .1451.1400 .5251 .098 j 4/21 0850 4/22 0915 '28.70!4.90 .3422.1480 2.5801 .440 f 4/22 0918 4/23 0950 38.7016.60 .286!.4150 7.440!1.270

$ 4/23 0950 4/24 0850 8.33!1.42 .051!.0476 j 4/24 1000 4/25 0955 6.15!1.05 .0732.0192 .1191 .031 l 4/25 0955 4/26 1010 14.9012.60 .1981.0950 .2582 .045 4/26 1015 4/26 1415 7.24!1.24 .132!.0240

- 4/26 1430 4/27 1023 10.3011.70 .095!.0790 .149! .039 1

4 4/27 1025 4/28 0925 8.4011.40 .0652.0273

4/28 0953 4/29 0850 6.1511.05 .083!.0514
4/29 0855 4/30 0908 21.9013.70 .4162.1020 .4361 .079 l-70

-- . -.y-. + - - .

" TABLE A-12, cont'd.

1 131 7

8 i

RELEASE RATE NORMALIZED RELEASE ON OFF (UCi/sec x 10 ) RATE (c/sec) 5/1 5/2 13. 1.3 5/2 5/3 14. 1.3 l

.5/3 5/4 21. 1.2 5/5 14. 1.0 5/4 5/6 10. 1.0 5/5 5/6 5/7 3.7 0.23 5/7 5/8 5.8 0.39 5/8 5/9 11. 0.76 5/9 5/10 9.0 0.63 5/10 5/11 29. 2.7 5/11 5/12 5.0 0.37 5/12 5/13 7.1 0.50 t

5/13 5/14 7.3 0.39 5/14 5/15 2.1 1.22 5/15 5/16 14. 0.76 l 5/16 5/17 12. 0.76 5/17 5/18 8.7 0.71 5/18 5/19 9.1 --

5/19 5/20 9.3 --

5/20 5/21 7.4 --

5/21 5/22 29. --

5/22 5/23 14. --

5/23 5/24 40. --

5/24 5/25 16. --

5/25 5/26 29. --

l 5/26 5/27 14. --

5/27 5/28 11. --

5/28 5/29 7.9 --

5/29 5/30 8.2 --

5/30 5/31 10. --

5/31 6/1 7.8 --

6/1 6/2 6.0 --

6/2 6/3 6.7 --

6/3 6/4 6.6 --

71

TABLE A12, (cont'd) 131 7

1 I

RELEASE RATE NORMALIZED RELEASE '

_ ON OFF 11C1/sec x 10 ) RATE (g/sec) 6/4 6/5 6.3 --

6/5 6/6' 5.7 --

6/6 6/7 5.5 --

6/7 6/8 5.2 --

- 6/8 6/9 5.2 --

6/9 6/10 5. 2 --

6/10 6/11 5.8 --

6/11 6/12 6.8 --

6/12 6/13 8.0 --

6/13 6/14 17. --

6/14 6/15 22. --

6/15 6/16 10. --

6/16 6/17 88. --

6/17 6/18 15. --

l l

I l

i s

i 1

1 l 72 l . _ _ .. .- . . . . _ . . ..

TABLE A-13 I AND 1 RELEASE RATES IN PILGRIM REACTOR BUILDING CLEAN EXHAUST 10 DINE-131 IODINE-133 NORMALIZED NORMALIZED DATE 6 TIME DATE & TIME RELEASE RATE RELEASE RATE RELEASE RATE RELEASE RATE ON OFF (uC1/secx103 ) (g/sec) (pC1/secx10 3) (g/sec) 2/4 1720 2/5 0809 2.4502 .12 .1100!.0260 2/5 0816 1727 3.740 .20 .2320 .0550 1733 2/6 0728 3.5001 .19 .21401.0550

, 2/6 0733 1807 3.5001 .19 .20001.0320 1812 2/7 0740 2.2201 .11 .1660 .0420 2/11 0213 2/11 1750 4.440 .22 .08101.0190 1754 2359 4.090! .21 .0332!.0037 2/12 0002 2/12 0550 3.6201 .19 .06212.0073 0555 1005 3.040! .14 .07211.0049 1010 1624 3.040 .14 .0720 .0041 1626 2/13 0347 2.570 .12 .0618!.0045 2/13 0352 0926 1.8701 .10 .05562.0059 0929 1324 2.5701 .12 .0874t 0093 1332 1650 2.100 .11 .0803 .0066 1653 2343 1.520 .09 .06662.0065 2348 2/14 0604 1.1901 .06 .0656!.0083 2/14 0607 1457 1.5101 .07 .1010 .0100 .1400!.0300 .002702.00065 I 1501 2/15 0829 1.210i .06 .16001.0700 .09111.0041 .001912.00036 2/15 0833 1634 1.300 .07 .2820 .0230 .19901.0360 .004931.00100 1637 2/16 0602 1.640! .09 .3280 .0230 2/16 0605 1537 1.3901 .07 .2210i.1130 1540 2354 1.230 .07 .19201.0960 .19901.0360 235b 2/21 1115 .724 .038 .1410!.0200 .1870t.0140 2/21 1119 2/25 1555 .6541 .033 .04991.0226 .3040!.0220 2/25 1605 2/28 1332 .3861 .020 .02522.0039 .24501.0160 2/28 1335 3/4 1255 .514 .025 .03651.0031 .7010 .0460 i

1358 3/5 1942 .4441 .051 .03471.0041 1945 3/11 1122 .526! .029 .0302!.0060 .5020!.0510 1125 3/14 1520 .6431 .033 .0540!.0042 3/14 1522 3/18 1041 1.870! .100 .1700!.0090 4.44001.2200 73

l TABLE A-13 (cont.)

10 DINE-131 10 DINE-133 NORMALIZED NORMALIZED DATE & TIME DATE & TIME RELEASE RATE RELEASE RATE RELEASE RATE RELEASE RATE '

ON OFF (pC1/secx103 ) (g/sec) (uci/secx103) (g/sec) 3/18 1059 3/21 1410 1.1101 .06 .09191.0152 .79401.1220 3/21 1412 3/25 1342 .7432 .036 .0599!.0061 1.88001.1000  ;

1345 3/28 1304 .7481 .037 .0542 .0033 3/28 1306 4/3 1313 .5962 .028 .0445 .0031 1.5500!.0900 1315 4/10 0830 .345! .016 .0202!.0024 .3970!.0210 4/10 0840 4/11 0830 .3331 .021 .02151.0032 i 4/11 0835 4/12 0900 .2571 .026 .01492.0042 .3270!.0490 l

4/18 0920 4/19 0928 52.000!2.500 .2210!.1140 4.4400!.2600 4/19 0928 4/20 0913 22.40011.500 .21002.1200 .98102.0630 4/20 0915 4/21 0902 10.300! .700 .05981.0481 .11001.0270 4/21 0905 4/22 0925 12.1002 .600 .14501.0490 1.40001.1300 4/22 0930 4/23 1007 8.9401 .430 .0660!.0800 .4730 .0470 4/23 1007 4/24 1000 10.400! .500 .06431.0493  !

4/25 0950 4/26 1000 8.4102 .420 .1120t.0420  ;

4/26 1000 4/26 1425 4.2101 .250 .0765 .0060 1425 4/27 1015 5.0201 .250 .0465!.0319 1020 4/28 0905 4.980! .220 .03831.0123 ,

4/28 0905 4/29 0907 1.020! .050 .0137!.0069 4/29 0910 4/30 0928 17.500 .800 .3340 .0520 2.61Cdt.1300 t

4 l

74 3

TABLE A-13, cont'd.

131 7

RELEASE RATE NORMALIZED RELEASE ON OFF (pCi/sec x 10 ) RATE (g/sec) )

5/1 5/2 2.6 0.26 5/2 5/3 2.9 0.27 5/3 5/4 30. 1.7 5/4 5/5 4.7 0.34 5/5 5/6 6.8 0.71 5/6 5/7 0.77 0.048 5/7 5/8 1.4 0.094-5/8 5/9 1.6 0.11 5/9 5/10 1.8 0.13 I 5/10 5/11 1.7 0.16 l 5/11 5/12 1.3 0.096 5/12 5/13 1.6 0.11 5/13 5/14 3.2 0.17 5/14 5/15 1.5 0.087 5/15 5/16 3.5 0.19 5/16 5/17 2.7 0.17 5/17 5/18 1.2 0.098 5/18 5/19 1.4 --

l 5/19 5/20 1.0 --

5/20 5/21 1.2 --

5/21 5/22 14.4 --

5/22 5/23 4.2 --

5/23 5/24 1.3 --

5/24 5/25 .99 --

5/25 5/26 5.7 --

5/26 5/27 1.2 --

5/27 5/28 0.69 --

5/28 5/29 0.59 --

5/29 5/30 0.76 --

5/30 5/31 0.77 --

5/31 6/1 0.67 --

6/1 6/2 0.47 --

6/2 6/3 0.96 --

l 6/3' 6/4 0.46 --

6/4 6/5 2.4 --

! 75

TABLE A-13* cont'd.

131 1 cont'd.

1 RELEASE RATE NORMALIZED RELEASE  !

ON OFF (UCi/sec x 10 ) RATE (g/sec) 6/5 6/6 0.78 --

6/6 6/7 0.50 --

6/7 6/8 0.40 --

6/8 6/9 3.8 --

6/9 6/10 0.63 --

6/10 6/11 0.43 --

6/11 6/12 0,38 --

6/12 6/13 1.1 --

6/13 6/14 0.45 --

6/14 6/15 0.45 --

6/15 6/16 0.46 --

6/16 6/17 0.54 --

6/17 6/18 0.26 --

k 6

76

131 TABLE A-14 1 IN REFUELING FLOOR EXIIAUST ON OFF RELEASE RATE (pCi/sec) 0830, 2/3 1720, 2/5 3.522.6(-5) 1726, 2/5 0722, 2/6 3.5tl.8(-4) 0726, 2/6 1803, 2/6 1.1 0.2(-4) 1808, 2/6 0733, 2/7 9.4!3.1(-5) l 1

77

131 TABLE A-15 I RELEASE RATE (pCi/sec)

IN VENTILATION EXRAUST AIR FROM CLEANUP PUMP ROOM i

CLEANUP PUMP ON OFF ROOM 1850 4/23 0833 4/24 4. 9!0.2 (-3) }

1445 4/27 1958 4/27 1.1 .06(-2) 2000 4/27 1121 4/28 6.510.3(-3) 1128 4/28 1950 4/28 1.1 .07(-3) 2030 4/28 1121 4/29 1.4 .07(-3) 1130 4/29 2145 4/30 2.1 0.1(-2) 2148 4/30 0810 5/1 1.31.07(-2)

I l

i l

l

1) Sample also taken in combined exhaust from cleanup pump room, l cleanup heat exchanger and sample hood. Release rate was i 5.610.3(-3)pC1/sec. I i

78 I

TABLE A 16 1311 CONCENTRATIONS (pCi/cc) IN THE REACTOR BUILDING BACKWASH RECEIVER TANK VENT OFF I ON 1/28 1923 1/29 0117 3. 0!0. 2 (-8 )

1/29 0145 1/29 0618 3.1!0.2(-8) 1/29 0630 1/29 1220 3.5!0.2(-8) 1/29 1230 1/20 1735 3.4!0.2(-8) 1/29 1740 1/30 0012 3. 3!0. 2 (-8) 1/30 0023 1/30 0752 2.7 0.1(-8) 1/30 0803 1/30 2252 2.7 0.1(-8) i 1/30 2304 1/31 0755 2.0 0.1(-8) 1/31 0807 2/1 0015 3.0 0.2(-8) 2/1 1805 2/2 0625 7. 8 0.4 (-8) 2/2 0635 2/3 0022 3. 0 0. 2 (-8) 2/3 0028 2/3 1040 1. 7! . 09 (-8) 2/26 3.6!0.5(-7) 2/26 5.5 0.3(-8) l l

l

1) upstream of charcoal filter
2) downstream of charcoal filter l l

l 79

TABLE A-17 I CONCENTRATIONS (DCi/cc) IN EXHAUST FROM FLAT BED FILTER ROOMS ON OFF I 2/1 0020 2/1 0825 4. 8 0. 2 (-9) 2/1 0840 2/1 1645 2.4!0.1(-9) 2/1 1650 2/2 1115 8. 0 0. 4 (-9) 2/2 1125 2/2 2305 5.8 0.3(-9) 2/2 2310 2/3 1725 6.6!0.3(-9) 2/3 1725 2/4 0725 9. 0!0. 5 (-8 )

2/4 0735 2/4 1819 5. 2!0. 3 (-8 )

2/4 1822 2/5 0705 l 5.9!0.3(-8) 2/5 0710 2/5 1620 1. 4 . 0 7 (-8) 2/5 1635 2/6 0700 1. 4 . 07 (-8) 2/6 0705 2/6 1832 7.8!0.4(-9) 2/6 1835 2/7 0730 2.9!0.2(-9) 2/7 0735 2/7 1852

1. 9!0.1 (-9 )

2/8 1110 2/9 1200 3. 2 0. 2 (-9) 2/9 1205 2/11 1640 2.1!0.1 (-9 )

2/11 1650 2/12 0735 1. 2 . 06 (-9) 2/12 0745 2/12 1907

3. 4 0. 2 (-9) 2/12 1915 2/13 0947
7. 2! 0. 4 (-9 )

2/13 0950 2/13 2244

9. 7!0. 5 (-9 )

2/13 2246 2/14 0747 4. 4 0. 2 (-9) 2/14 0800 2/14 1613

6. 6 0. 3 (-9) 2/14 1617 2/15 0220 2. 4!0.1 (-9) 2/15 0223 2/15 1813 3. 0 0. 2 (-9) 2/15 1823. 2/16 0430 4.1!0. 2 (- 9) 2/16 0443 2/16 1707 4.0t0.2(-9) 2/16 1727 2/16 2236 1. 6! . 08 (- 9) 2/16 2/21 9.6 0.5(-10) 2/21 1240 %40 hrs 3. 5!Q. 2 (-9 )

2/25 2/28 7. 9!0. 4 (-10) 2/28 3/4 2. 2! 0.1 (-9 )

3/4 1815 3/5 2050 1. 3!0. 2 (-9) 3/5 3/11

7. 6 t 0. 4 (-10) 3/11 3/14 1320 1.1 .06(-9) 3/14 3/18 1255 1.3 .07(-9) 80

i T ABLE A 17 I CONCENTRATIONS (UCi/cc) IN EXHAUST FROM FIAT BED FILTER ROOMS l ON OFF I 3/18 3/21 1240 3.5 0.2(-9) 3/21 3/25 1.21.06(-8) 3/25 3/28 2. 4 !0.1 (-9) 3/28 4/3 3.010.1(-9) 4/3 4/10 2.510.1(-9) 5/8 5/9 1.4(-8) 5/9 5/10 8. 8 (-9 )

.5/10 5/11 4. 4 (-9) 5/11 5/12 5. 0 (-9) 5/12 5/13 5 1(-9) 5/13 5/14 5. 3 (-9 )

5/14 5/15 3.3(-7) 5/15 5/16 1.0(-7) 5/16 5/17 6.6(-8) 5/17 5/18 5. 0 (-8 )

5/18 5/19 3. 7 (-8) 5/19 5/20 6.2(-8) 5/22 5/23 1. 9 (-8 )

5/23 5/24 5.6(-8) 5/24 5/25 3. 4 (-8) 5/25 5/26 1.1 (-8) 5/26 5/27 9. 5 (- 9) 5/27 5/28 1.3(-8) 5/30 5/31 5.3(-9) 5/31 6/1 4. 0 (-9 )

6/1 6/2 2. 6 (-9 )

6/3 6/4 1. 4 (-8) 6/5 6/6 5.6(-8) 6/6 6/7 3.3(-9) 6/7 6/8 4. 0 (-9) 6/8 6/9 2. 9 (-9 )

6/9 6/10 3.4(-9) l 6/10 6/11 2.2(-9) 6/11 6/12 2. 4 (-9) 6/12 6/13 8.1 (-9) 81

_ . _ . ~ _ - . . __ _ _ . _ . _ _ _ _ . . -_

1 TABLE A-17 I CONCENTRATIONS (pC1/cc) IN EXHAUST FROM FLAT BED FILTER ROOMS ON 131 OFF _,

7 6/13 6/14 2. 8 (-8) 6/14 6/15 2. 3 (-8) 6/15 6/16 1.6(-8) 6/16 6/17 7.3(-8) 6/17 6/18 6.9(-8) l 1

l l

1 i

t 82

?

TABLE A-18 1 AND I RELEASES (pC1/sec) IN ,

VENTILATION EXHAUST AIR FROM THE RADWASTE CONCENTRATOR ROOM (FLOW RATE = 6450 cfm)

OFF I ON 1/30 2359 1/31 1033 1.2!.05(-3) i 1/31 1038 1/31 1830 9.1!0.6(-3) 1/31 1850 2/1 0027 2. 2 1. 2 (-2) 2/1 0040 2/1 0900 1.7 .09(-2) 2/1 0905 2/1 1655 1.52.08(-2) 2/1 1703 2/2 1055 7.9!0.3(-3) i 2/2 1100 2/2 2320 6.4 0.3(-3) l 2/2 2325 2/3 1650 1. 4 . 06 (-2 ) j 2/3 1656 2/4

  • 0750 1.6 .09(-2) 2/4 0805 2/4 1809 2. 6!0. 2 (-2 )

i 2/4 1811 2/5 0650 3.8 0.2(-2) 2/5 0722 2/5 1617 2.1!0.1(-2)

2/5 1622 2/6 0648 1.4 .07(-2) 2/6 0652 2/6 1820 5.2 0.2(-3) 2/6 1827 2/7 0713 4.0!0.2(-3) 2/7 0720 2/7 1840 7. 0 0. 3 (-3)

=

2/7 1846 2/8 1130 1.9!0.1(-2) 2/11 0200 2/11 1.1 .06(-2) 2/11 1630 2/12 0710 2.9!0.2(-3) )

2/12 0715 2/12 1855 6.7!0.3(-3) 2/12 1900 2/13 1002 2. 3!0. 2 (-3 )

4 2/13 2241 2/14 0811 2.120.1(-3)

, 2/14 0815 2/14 1606 2. 6!0.1 (-3)

, 2/14 1609 2/15 0232 6. 4 0. 3 (-3) 2/15 0235 2/15 1805 9. 7 0. 6 (-3) 2/15 1807 2/16 0425 1. 6 . 09 (-2 )

2/16 0429 2/16 1715, 1.5 .08(-2) 2/16 1717 2/16 2228 5.810.3(-3) 2/16 2231 2/21 1210 7. 3 0. 4 (-3) 2/21 2/25 8.2!0.4(-3) ,

I 3.720.2(-3) 2/25 2/28 2/28 1143 3/4 1333 4. 0!0. 2 (-3) 3/5 3/11 1.6 .09(-3)

~3/11 3/14 2.3 0.1(-3) 83

i TABLE A 18 131 1 AND 133 I RELEASES (pC1/sec) IN VENTILATION EXHAUST AIR F. ROM THE RADWASTE CONCENTRATOR ROOM (FLOW RATE = 6450 cfm) l ON OFF I l 3/14 3/18 1420 1. 6 . 09 (- 3 )

3/18 3/21. 1210 1.71.09(-3) 3/21 3/25 2.4!0.1(-3) 3/25 3/28 2.1t o .1 (-3 ) I 3/28 4/3 2.510.1(-3) l i

4/3 4/10 2.1!0.1 (-3) 5/8 ,

5/9 1. 7 (-2 )

5/9 5/10 3.1 (-2 )

5/10 5/11 1. 2 (-2 )

5/11 5/12 9.9(-3) 5/12 5/13 1. 6 (-2 )

5/13 5/14 1. 4 (-2 )

5/14 5/15 4. 0 (-2 )

5/15 5/16 4. 4 (-2 )

5/16 5/17 2.1 (-2 )

5/17 5/18 2. 0 (-2 )

5/18 5/19 7. 5 (-2 ) .

5/19 5/20 7. 3 (-2 )

5/22 5/23 5.8(-2) 5/23 5/23 9.5(-2) 5/24 5/25 9.2(-2) 5/25 5/26 4. 5 (-2 )

5/26 5/27 2. 8 (-2 )

5/27 5/28 3.1(-2) 5/30 5/31 1.9(-2) 5/31 6/1 1. 2 (-2 )

6/1 6/2 *

9. 4 (-3 )

l 6/3 6/4 1. 5 (-2 )

j 6/4 6/5 2.9(-2) 6/5 6/6 2. 4 (-2 )

6/6 6/7 3.1(-2) 6/7 6/8 3.8(-2) 6/8 6/9 1. 4 (-2 )

6/9 6/10 1. 2 (-2 )

l 84

i I

f 131 1 RELEASES (UCi/sec) IN TABLE A-18 I AND VENTILATION EXHAUST AIR FROM THE RADWASTE CONCENTRATOR ROOM (FLOW RATE = 6450 cfm) l

-)

l OFF I ON  !

6/10 6/11 1. 4 (-2 )

6/11 6/12 1. 4 (-2 )

6/12 6/13 1. 7 (-2 )

6/13 6/14 8.1 (-2) i 6/14 6/15 1.5(-1) 6/15 6/16 3. 8 (-2 )

6/16 6/17 3. 6 (-1 )

i 6/17 6/18 2.0(-2) 85 L

1 i

i 131

{ TABLE A-19 I CONCENTRATIONS (pCi/cc) IN EXHAUST, ROOM AIR AND CORRIDOR AIR OUTSIDE RADWASTE CONCENTRATOR ROOM I CONCENTRATION

! ON OFF EXHAUST DUCT ROOM AIR CORRIDOR AIR I

?

2/21 2/25 2.7!0.1(-9) 3. 3!0. 2 (-9) NS l

2/25 2/28 1.2!.06(-9) 1.11.05(-9) NS I

j 2/28 3/4 1.3!.07(-9) 1.1!.06(-9) NS 3/4 3/5 NS 8.6 0.4(-10) i 2.120.1(-10) 3/5 3/11 5.220.3(-10) 5.5 0.3(-10) 7. 2!0. 4 (-11) 3/11 3/14 7.7 0.4(-10) 8. 0!0. 4 (-10) 3.610.2(-10) {

j 3/14 3/18 5.4 0.3(-10) 4.6 0.2(-10) 1.720.1(-10) 3/18 3/21 5.6!0.3(-10) 2.4 0.1(-10) 1.1 .06(-10) 3/21 3/25 7.6!0.4(-10) 5. 6!0. 3 (-10) 3. 3t 0. 2 (-10) 3/25 3/28 7.0 0.3(-10) 6.1 0.3(-10) 1.1!.06(-10) 3 3/28 4/3 8. 4!0. 4 (-10) 8.4 0.4(-10) j 1.4 .07(-10) 4/3 4/10 6.8 0.3(-10)

7. 0!0. 4 (-9 ) 1.3t.07(-10) l l

86 l

l TABLE A-20 1 CONCENTRATIONS (PCi/cc) NEAR ENTRANCE TO FLAT BED FILTER ROOM "B" I CONCENTRATION ON OFF AT ENTRANCE (2' ELEV.) 7' FROM ENTRANCE (12' ELEV. )

2/28 3/4 2.2!0.1(-9) 6.4 0.4(-10)

6. 5!0. 4 (-10) NS 3/4 3/5 3/5 3/11 1. 8!0.1 (-10) 3.5!0.2(-10) 3/11 3/14 3.1!0. 2 (-10) 5.0 0.3(-10) 3/14 3/18 5.1 0.3(-10) 2.0 0.1(-10) l 3/18 3/21 7.6 0.4(-10) 2. 8!0.1 (-10) 3/21 3/25 2.1 0.1(-9) 1.3!.06(-9) 3/25 3/28 4.2 0.2(-10) 3.920.2(-10) 3/28 4/3 1.6!.08(-10) 2.8 0.2(-10) l 4/3 4/10 1,4t.07(-10) 7. 8!0. 4 (-10) 4 l

l 87

- - _ - _ _ _ _ _ - _ - _ _ _ _ _ . - - .. - . . _ -. . . . . . _ . ~ . . .. = - - - - . . ,

TABLE A- 21 MISCELLANEOUS GRAB SAMPLES IN RADWASTE AREA LOCATION 1 1 Conc.

Flat Bed Filter 2005, 4/23 3.510.2(-8) i l

Exhaust Duct 2120, 4/23 5.7 0.3(-8) 0915, 4/24 5.210.3(-8) 4/25 4. 2!0. 2 (-8 )

R.W. Sump Room Area 4/24 1.6 .08(-8)

R.W. Sump Room Exhaust 4/24 3.3!O.5(-8) 1 R.W. Sump Room Area 4/25 3.lt0.2(-8)

R.W. Sump Room Area 1525, 4/27 5.6!0.3(-9)

Area near Distillate and -

4/25 2. 0!0.1 (-8 ) ,

sludge pumps 4/25 2.2!0.1(-8) l I

\

i l

l l

1 i

i 88 L. /

U.S. NUCLE AR REGUL AT ORY COMMISSION 17-7 7)

BIBLIOGRAPHIC DATA SHEET NUREG/CR-0395 4 TITLE AND SUBTITLE (Add Volume No,if aapiconate1 2 (Leave Diank)

Evaluation of Radioiodine Measurements at Pilgrim RE eiENn ACCESSION Nc.

Nuclear Power Plant 5 D ATE HEPORT COMPLE TED

7. AU THOR (S)

C. Pelletier, J. Cline, P. Voilleque, R. Hemphill *{eptember k978

9. PE RF OHMING OHGAN12ATION NAME AND MAILING ADDRESS (Include lip Codel DATE REPORT ISSUED MONTH jYEAR October 1978 Science Applications, Inc.

o ae.ve o<<n*>

NES Division Rockville, Maryland 20850 8 Ileave blanki

12. SPONSOHING ORGANIZATION N AME AND M AILING ADDHESS (Inctuae lep Codel p Effluent Treatment Systems Branch M. CONT R ACT NO Division of Site Safety & Environmental Analysis United States Nuclear Regulatory Commission A6075 Washington, DC 20555 PE A!OO COV C RE D (Inclus,ve defes) 13 TYPE OF REPORT 14 (Leave e/ank)
15. SUPPLEMENTAHY NOTES
16. ABSTR ACT (200 words or less)

An evaluation of radiciodine measurements made for The Boston Edison  ;

Company at their Pilgrim Nuciear power plant is presented. Measurements include the nuclides 1-131, 1-133 and I-135, ventilation exhaust air and reactor water. Concentrations of the nuclides Cs-134, Cs-137, Mn-54 and Co-60 in reactor water are included because they were readily 1 j

detectable. The evaluaticn is made in the same manner as evaluations of '

radiciodine measurements made for the Electric Power Research Institute at three other BWRs. Measurement results for the four BWRs are summarized and compared.

)

17 KE Y WORDS AND DCVUMENT AN ALYSIS 17a. DESCRIPTORS l

17b. IDENTIFIERS /OPF N ENDED TE RMS 19 SECURITY CLASS (This report) 21 NO OF P AGES 18 AV AILABILITY STATEMENT 70 SECURITY CLASS (This page) 22. P RICE Unlimited s NRC FORM 335 (7-77)

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UNITED STATES .

NUCL EA A MEG ULATORY COMMIS$10N WAStfiNGTON, D. C 20555 f ~l POST AGE AND F E E5 P AID 4 OFFICI AL DUSINESS u.S. HUC LE A R RE GU LA TOM Y PC N ALTY FOR PRIV ATE USE, $300 COMM'5580N

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u U S. MAJt J 1 120555003927 1 R R AN

US NRC SFC Y PUBL IC DOC U ME NT ROOM BR ANCH CHIEF HST LOBRY WASHINGTON DC 20555 e

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