ML20206M392
| ML20206M392 | |
| Person / Time | |
|---|---|
| Site: | North Carolina State University |
| Issue date: | 08/03/1988 |
| From: | Harris R North Carolina State University, RALEIGH, NC |
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| ML20206M389 | List: |
| References | |
| NUDOCS 8811300554 | |
| Download: ML20206M392 (18) | |
Text
{{#Wiki_filter:' 4 e 9 e RADIATION PROTECTION OFFICE NORTH CAROLINA STATE UNIVERSITY ENVIRONMENTAL RADIATION SURVEILLANCE REPORT FOR THE PERIOD 07/28/87 O&O3/88 b l i r l RALTON J. HARRlS ENVIRONMENTAL HEALTH PHYSICIST i ! i l 9911300554 001117 PDR ADOCK 05000297 4 l R PNV
- 1. NTRODUCTION During the months of May and August of 1987, an audit of the environmental monitoring capabl-lilies of the Radiation Protection Office (RPO) was performed by a committee appointed by the Radia-tion Protection Council. The conclusions of this audit have been summar! zed by the audit chairman, Dr. Lawrence H. Bowen, and are given in Appendix A of this report.
Since March 1988 the RPO environmentallaboratory has been operating a Nuclear Data 990 Gamma Spectroscopy System which was acquired following recommendations of the environmental audit committee. This equipment provides state-of the art computerized gamma spectral analysts capabilities using both Ge(U) and Nal(TI) detectors. Appreciation is expressed to Mr. Paul A. Shuping of the Radiation Protection Office staff for his assistance in providing the computer generated graphs in this report.
- 2. AIR MONITORING Table 2.1 shows the locations of the air monitoring stations. Tables 2.2 and 2.0 give the gross beta actMties and gamma actkities of selected nuclides in units of femtoCurtes per cubic meter.
Also, Figures 2.2a, b, c, d, e, and f gNe a graphical representation of the data of Table 2.2. Gross beta actNities are determined by counting Millipore air filters which are collected on a weekly basis. The lower limit of detection (LLD) for gross beta actMty is - 10 fCim 3. The gamma actMtles in Table 2.3 are determined by counting the fke (5) hi volume filters as a composite sample. These values are the LLDs for the given nudides with only an occasional data entry exceeding the LLD. TABLE 2.1 LOCATION OF AIR MONITORING STATIONS DISTANCE 2 ELEVATION 3 SHE DJEECTIONI (meters) (meters) 125 17 OROUGHTCN SOJIMYEST 500 18 DAVID CLARK LABS WfiST 192 + 11 UBRARY FX RTHWEST 99 14 RIDDICK SCUTHEAST 82 - 6 WITHERS NCRTHEAST 1 DIRECTION DIRECTION FROM REACTOR STACK 2 DISTANCE DISTANCE FlWA REACTOR STACK 3ELEVAT10N ELEVATION RELATIVE TO THE TOP OF THE REACTOR STACK
PAGE 2 TABLE 2.2 AIRBORNE GROSS BETA ACTIVITY (fCl m-3 11o) BFOU34 TON RIDDICK WITHERS LIBRARY DAVID CLARK D6IE 1987 07/28 08/04 4.3 1 2.8 33.2 14.1 29.014 0 19.0 A 2.4 21.113.1 08/04-08/11 21.213.5 16.313.3 18.713.6 20.012.7 19.713.4 12.313.8 6.411.5 14.3 1 4.2 GJ/1108/18 21.3 14.0 7.6 1 2.0 08/18 08/25 24.8 i 4.1 20.813 8 22.214 3 19.112.7 20.213.6 08/25-09/01 27.4 13.9 28.014 0 30.0141 29.013.1 24.613.8 09/01 09/09 25.013.6 26.014 0 23.9 i 3.4 22.812.6 29.9i3.6 09/09-09/14 28.213.8 24.913.4 15.4 13.0 18.212.6 19.213.6 09/14 09/22 24.515.3 20.5 A4.8 20.41 5.6 20.4 A 3.1 28.6 14.9 09/22 09/29 33.9 i 4.4 35.7 A4.4 28.9_t4.4 19.812.7 27.7 i 3.8 09/29 10/06 16.1 1.3.8 20.2 + 3.4 14.7 14.1 - - 12.012.1 10/06 10/13 11.513.6 21.9 A 3.8 11.6 A4.1 7.4 1 2.2 15.1 1 3.5 10/131(v20 20.912.3 31.813.7 27.513.5 .26.512.7 31.013.6 10/20 1078 21.913.9 17.8 14.0 16.613.6 17.4 1 2.6 18.61 3.6 10/28 11/03 40.114 7 38.114 4 30.214 5 26.9 i 3.2 0.6212.7 11/10-11. 17.513.5 21.513.6 18.313.5 16.712.3 21.513.7 11/17 11/24 21.913.8 19.113.6 22.213.8 22.112.8 43.4 1 8.8 11/24 12/01 18.213.5 18.413 5 13.513.3 11.512.3 - 12/01 12/08 16.314 2 11.713.2 12.613.3 6.9 1 2.2 12/08 12/15 17.513.6 16.813.5 15.013.2 9.5 1 2.0 11.713.2 12/15 12/29 18.712.4 15.2121 11.2 1.2.0 15.111.7 20.112.5 12/29 01/0548 16.713.7 18.513.5 22.013.8 16.112.4 - 1988 01/05 01/19 21.312.7 26.612.6 21.912.4 12.211.4 20.9 i 2.2 01/20-01/26 15.213.5 - 13.013.0 8.4 1 2.1 38.815.9 01/27 02/02 19.6141 5.413.9 12.9 i 3.6 3.4 1 2.0 02/03 02/09 14.6 14.1 13.8 A 3.5 16.613.5 3.212.0 - 02/10 02/23 27.512.7 23.112.5 22.9 A 2.5 11.011.4 29.4 13.3 02/24 03/02 29.41 3.6 22.7 i 3.3 24.01 3.4 7.9 A 1.9 37.7 A 3.9 03/CG 03/16 14.711.0 19.312.3 18.712.2 7.311.2 14.111.9 03/17 0372 - 20.213 9 10.613.6 10.912.5 14.8 i 4.1 03/23-03/29 - 21.013 9 17.6 10 4 15.112.6 23.5 i 3.8 03/30 04/05 - 23.314 0 17.113.5 14.512.4 22.913.7 04/06 04/19 - 15.012.0 10.711.8 9.3 1 1.3 11.111.8 04/19 04/26 18.213.7 18.713 8 18.813.8 11.212.4 14.513.5 04/26 05/03 18.613.6 18.313 7 - 8.7 1 2.3 2.3 1 3.0 05/03 05/10 16.513.5 11.913.3 10.513.2 8.3 1 2.2 16.41 3.4 05/10-05/17 21.313.4 22.1 13.4 20.613.4 - 25.4 13.6 05/17 0Y24 63.615.7 29.7 A4.2 23.313.8 23.4 12.9 15.213.4 05/24 05/31 42.5 14.7 22.513.8 21.813.7 10.41 2.2 18.313.5 05/31 06/08 23313.7 25.613.7 25.913.5 27.312.8 27.113.4 0006 06/14 30.8 i 4.3 23.6141 78.116 9 14.612.6 21.3 14.2 06/14-0&?2 22.813.5 25.7 16 3 31.313.8 25.212.7 30.9 i 3.7 06/22 0678 20.5 14.6 20.2 14.3 24.4 i .64 26.4 13.3 24.614 5 06/28 0hD5 18,613.4 21.1 13.5 15.4 12.4 17.212.5 33.115.7 07/05-07/12 29.4 1 4.0 27.213.9 22.4 1 .61 24.312.8 18.812.6 07/12 07/19 11,9 i 3.4 16.3 16 3 11.5 i 1.0 11.112.4 15.4 13.5 07/19 07/26 15.7 i 3.4 14.6 t 3.3 25.512.4 7.6 1 2.1 9.7 1 2.9 07/26 0803 30.913.8 33.9 i4.0 18.0 11.3 21.512.5 32.8 i 4.1
FIGURE 2.2a FACE 3 100 -
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FIGURE 2.2f Page 8 f 100: Airborne Gross Beta Activity 5 North Carolina State University 5 All 5 Monitoring Stations 90j July 28,1987-August 3,1988
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, .i i TABLE 2.3 AIRBOfW4EGAMRAA ACTMTY(fClnr3f1,} JPs12 9 -
SAMPLING FERIOD Co-57 Co-60 NUCLIDES 1987 Kb-95 Zn-95 Sr-85 Ru-lO3 Ru-106 Cs-137 Ce-141 Ce-144 Ba-140 08/04-08/13 < 1.3 < l.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 08/11-08/18 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4
< 3.3 < 2.7 < 11 < 4.7
< 1.3 < 12 < 3.3
- C8/18-08/25 < 1. 3 < 1.4 < 1.4 < 2.3 < 1.4
~
< 2.7 < 11 < 4.7
< 1.3
- 08/25-09/01 s 1.3 < 1.4 < 1.4 < 2.3 < 1.4 36.3 t 39.3 < 3.3 < 2.7 < 11 < 4.7
< 1.3 < 12 < 3.3 < 2.7 < 11
} 09/01-09/09 2.8 11.9 < 1.4 < l.4 < 2.3 14.3 z 13.1 < l.3
< 4.7 j 09/09-09/14 < 1.3 < l.4 < l.4 < 2.3
< 12 4.95 1 2.5 < 2.7 < 11 < 4.7
< 1.4 < l.3 52.3129 j 09/14-09/22 < 1.3 < 1.4 < l.4 < 2.3 < 1.4 < 1.3
< 3.3 < 2.7 < 11 < 4.7
< 12 < 3.3
- 09/22-09/29 < 1.3 < 1.4 < l.4 < 2.3 < 1.4 < 1.3
< 2.7 < 11 < 4.7
< 12 < 3.3
} 09/29-10/06 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3
< 2.7 < 11 < 4.7 1 10/06-10/13 < 1.3 < 12 < 3.3 < 2.7 < 11 < 4.7
' < 1.4 < l.4 < 2.3 < 1.4 < 1. 3 < 12 < 3.3 15.7 1 18.2 < 4.7 10/13-10/20 < 1.3 < l.4 < 1.4 < 2.3
< 2.7
< 1.4 < l.3 < 12 < 3.3 < 2.7 < 11 10/20-10/28 3.8512.3< 1.4 < l.4 < 2.3 < 1.4 < 1.3 < 12 < 3.3
< 4.7 10/28-11/03 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < l.3
< 2.7 < 11 < 4.7
< 12 < 3.3 < 11
, 11/03-11/10 < 1.3 < 1.4 < l.4 < 2.3 < l.4 < 1.3
< 2.7 < 4.7
< 12 < 3.3 i
11/10-11/17 < l.3 < 1.4 < l.4 < 2.3
< 2.7 < 11 < 4.7
} 11/17-11/24 < 1.3 < 1.4 < 1.3 < 12 < 3.3 < 2.7 < 11 < 4.7
< 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 < 3.3 < 2.7
+ 11/24-12/01 < 1.3 < 1.4 < 1.4 < 2.3 < l.4
< 11 < 4.7 I
12/01-12/08 < 1. 3 < 1.3 < 12 < 3.3 < 2.7 < 11 < 4.7
< l.4 < 1.4 < 2.3 12/08-12/15 < 1.3
< l.4 < 1.3 < 12 < 3.3 < 2.7 < 11 < 4.7
< 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 < 3.3 < 2.7 < 11
) 2/15-12/29 < 1.3 < l.4 < 1.4 < 2.3
< 4.7 12/29-01/05 < 1. 3 < 1.4 < l.4 < 2.3
< 1.4 < 1.3 12.3 1 5.7 .74 1 45 < 2.7 < 11 < 4.7
< 1.4 < 1.3 < 12 < 3.3 < 2.7 < 11
{ 1988 01/05-01/19 < 1. 3 < l.4 < l.4 < 2.3
< 4.7 1 01/20-01/26 < 1.3
< 1.4 < 1.3 < 12 < 3.3 < 2.7 < 11 < 4.7
< 1.4 < l.4 - 2.3 < 1.4 < 1.3 l
01/27-02/02 < 1.3 < l.4
< 12 < 3.3 < 2.7 < 11 < 4.7
< 1.4 < 2.3 < 1.4 < 1.3 < 12
) 02/03-02/09 < 1.3 < 3.3 < 2.7 < 11 < 4.7
< 1.4 < l.4 < 2.3 < 1.4 < 1.3 < 12 < 3.3 < 2.7 < 11
( 02/10-02/23 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12
< 4.7 i 02/24-03/02 < 1.3 < 3.3 < 2.7 < 11 < 4.7
< l.4 < l.4 < 2.3 < 1.4 < 1.3 < 12 < 3.3 < 2.7 < 11
] 03/03-03/16 < 1.3 < l.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12
< 4.7 1 03/17-03/22 < 1. 3 < 3.3 < 2.7 < 11 < 4.7
< 1.4 < 1.4 < 2.3 < 1.4 < 1.3
} 03/23-03/29 < 1.3 < 1.4
< 12 < 3.3 < 2.7 < 11 < 4.7 e 1.4 < 2.3 < 1.4 < 1.3 I 03/30-04/05 < 1.3 < 1.4
< 12 < 3.3 < 2.7 < 11 < 4.7
< 1.4 < 2.3 < l.4 < l.3 j 04/06-04/19 < 1.3 < 1.4
< 12 < 3.3 < 2.7 < 11 < 4.7
< 1.4 < 2.3 < 1.4 < 1.3 < 12 I 04/19-04/26 < 1. 3 < 1.4
< 3.3 < 2.7 < 11 < 4.7
< 1.4 < 2.3 < 1.4 < l.3 < 12 4 < 3.3 < 2.7 7.9 4.5 < 4.7 04/26-05/03 < 1. 3 < 1.4 < 1.4 < 2.3 < 1.4 05/03-05/10 < 1.3 < 1.4 < 1.4
< 1.3 < 12 3.6 1 1.4 < 2.7 < 11 < 4.7
< 2.3 < 1.4 < 1.3 < 12 < 3.3 < 2.7 < 11 < 4.7 i
t L---.--- - . - . - - - . _ - . - . . - _ - - - - - . - - - . - _ . - . . - - . - -. - -. .-_ . - _ .
P:g210 TASt.E13 AlfWOf30Eema ACTMTV(fCIvir3 1 1o), continued ; .,. SAMPLING NUCLILES ,
^
PERIOD Co-57 Co-60 Nb-95 Zn-95 Sr-85 Ru-103 Ru-106 Cs-137 Ca-141 Ce-144 Ba-140 , O',/10-05/17 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 3.5 1 1.1 1.6 1 1.4 < 11 < 4.7 , 05/17-05/24 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 1.2 i .43 < 2.7 < 11 < 4.7 05/24-05/31 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 3.3 i .65 < 2.7 < 11 < 4.7 l 05/31-06/08 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 2.1 i .53 < 2.7 < 11 < 4.7 96/08-06/14 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 3.7 1 64 < 2.7 < 11 < 4.7 G5/14-06/22 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 1.9 i .66 < 2.7 < 11 < 4.7 06/22-06/28 < 1.3 < 1.4 < 1.4 . < 2.3 < 1.4 < 1.3 < 12 1.3 i .57 < 2.7 < 11 < 4.7 06/73-07/05 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 1.6 i .63 < 2.7 < 11 < 4.7 07/05-07/12 < 1.3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 2.8 i .75 < 2.7 < 11 < 4.7 07/12-C7/19 .48 1 32 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 1.3 i .41 < 2.7 < 11 < - 4.7 ,
< 1.4 < 1.3 < 12 2.3 1 05 < 2.7 < 11 < 4.7
- 07/19-07/26 < 1.3 < 1.4 < 1.4 < 2.3 07/26-08/03 < 1. 3 < 1.4 < 1.4 < 2.3 < 1.4 < 1.3 < 12 < 3.3 < 2.7 < 11 < 4.7
] 1 l i a h O 1 l 1 i 0 . e .
l ' PAGE 11
- 3. MILX (TABLE 3.1)
Monthly anayses of cows' mik from the Campus Creamery have consistently shown concentra. tions of Sr.90 that are well below the FDA's Preventive Protective Action Guide value of 0.009 microcuries liter 1 for Infants. This laboratory's LLD for St 90 in milk is 4 picoeuries Eter 1 Pursuant to recommendations by the environmental audit committee, Sr.90 analysis will possibly be discontinned in the future in favor of l 131 anatysis. TABLE 3.1 SR 90 IN COWS' MILK (pCIliter 1 11 ) adg ACT1 Vin' t AUGUST 1987 <5.0 SEPTEMBER 1987 < 5.0 OCTOBER 1987 <5.0 NOVEMBER 1987 NO SAMPLE DECEMBER 1987 < 5.0 JANUARY 1988 <5.0 FEBRUARY 1988 < 5.0 MARCH 1988 < 5.0 APRIL 1988 NOSAMPLE MAY 1988 < 5.0 JUNE 1988 <5.0 JULY 1988 <5.0
- 4. SURFACE WATER (TABLE 4.1)
The data of Table 4.1 give gross alpha and beta actMties for water from Rocky Branch at points where it enters (CN) and axist (OFF) the campus. The values given are the respective LLD's for gross alpha Lnd beta actMtles. TABLE 4.1 SURFACE WATER (pClll'er-111 ) D6IE 1.DCATION GROSSALFHA CICSS BETA FOURTH OUARTER 1987 CN < 0.5 < 4.0 CFF < 0.5 < 4.0 FIRST QUARTER 1988 CN < 0.5 < 4.0 CFF .: 0.5 < 4.0 SECOND QUARTER 1988 CN < 0.5 < 4.0 CFF < 0.5 < 4.0 THIRD QUARTER 1988 CN < 0.5 < 4.0 CTF < 0.5 < 4.0
} . PAGE 12 ,
- 5. SOIL (TABLES 5.1,5.2, AND 5.3)
Soil samples were taken in the vicinity of Buriington Engineering Laboratories following dis. covery of primary water loss from the PULSTAR Reactor on 29 February 1988. These samples were taken near the vault and along the length of the sump transfer line on 01 March 1988. Addi-tional background samples were obtained frt.m the Gardner Arboretum (adjacent to Burlington Engineering Laboratories) and near David Clark Laboratories (500 meters west of the reactor). TABLELEGEND; S - SURFACE SAMPLE (0 TO 6 INCHES) D - DEEP SAMPLE (3 FEET) 2
'O - DEEP SAVPLE (5 FEET)
AS - ARBORETUM SURFACE SAMPLE (0 TO 6 INCHES) AD - ARBORETUM DEEP SAMPLE (3 FEET)
- DC'i- DAVID CLARK SURFACE SAMPLE (0 TO 6 INCHES) i DCD OAVID CLARK DEEP SAMPLE (3 FEET)
TABLE 5.1 GROSS BETA ACTIVITY IN PULSTAR SOIL (LLD = 11 pCl g 1) SAMPLE NO. oCl aram 1 S1 < 11 D1 16.1 S2 < 11 l 18.6 ! D2 l S3 11.5 D3 < 11 S4 < 11 l D4 < 11 l i S5 < 11 D5 < 11 S6 < 11 06 < 11 S7 < 11 l D7 < 11
*D7 < 11 l
l l f (. - - _ _. _ __
PAGE 13 TABLE 5.2 GAMMA ACTIVITYIN PULSTAR SOIL SAMPLE NO. NUCUDE oCl aram 1 S1 K 40 0.3010.04 D1 K 40 0.2010.03 S3 K-40 0.2810.03 D3 K-40 0.27 A 0.03
, SS K 40 0.2610.03 Co-57 0.017 i 0.013 l
D5 K-40 0.27 i 0.03 i Pb-212 0.046 1 0.017 DCS1 K 40 0.2610.04 DCD1 K 40 0.2710.03 t AS1 F 18 1.5810.41 ADI Co 144 0.065 1 0.084 i K-40 0.29 i 0.03 AS2 K 40 0.25 A 0.03 AD2 K 40 0.271 0.03 l
. PAGE 14
~ TABLE 5.3 GAMMA ACTIVITY IN FULSTAM SOIL SAMPLES D1 AND D7 SAMPLE NO. NUCUDE oCl aram 1 D1 K-40 2.23 A 0.22 Ra-224 0.525 1 0.215 Ra 226 0.117 i 0.019 , Ra-228 0.236 1 0.061 Th 228 0.018 1 0.014 ; Th-232 0.200 1 0.032 Co-58 0.013 1 0.005 l131 0.027 1 0.009 ( D7 K-46 2.2410.25 Ra 224 0.5310.33 Pa 226 0.137 i 0.016 Ra 228 0.349 A 0.073 Th-228 0.207 1 0.010 t i I Th 232 0.193 1 0.033 Cs 137 0.015 f.; 0.008 l l f y L i l t
PAGE 15
- 6. VEGETATION TABLE 6.1 GAMMA ACTIVITY IN PULSTAR GRASS t SAMPLE NO, NUCUDE oCl oram 1 1 K 40 2.1210.51 Be.7 0.071 A 0.113 Xe.133m 1.09 A 0.43 (DATE FOR TABL,E 6.1 WAS SUPPUED BY THE NORTH CAROUNA DIVISON OF FACluTY SERVICES)
- 7. CONCLUSCNS The data presented in this report support the conclusion that the PULSTAR Reactor has released no signifcant quantitles of radionuclides into the NCSU Campus environment or the surrounding com.
munh. Nearty all reported levels of radioactMty are at or below the detection limits of Ibis laboratory. All of the gross alpha and beta actMtles and gamma nuclides identified can be atirl. buted to natural background radiation or residual fallout from previous nuclear weapons testing. l t i 4 h i ll i i l
- . APPENDIX A 0
MEMORANDUM 31 August 1987 TO: John F. Roberts, Chairman Radiation Protection Council FROM: Lawrence H. Bowen, Chemistry Dept. vuw. N. J*N M ""
SUBJECT:
Audit of PULSTAR Environmental Honitoring In response to your memorandum of March 4, I have had two meetings with the concerned individuals: May 7 (with Carry Miller, Tom Bray, and Ralton Harris) and August 28 (with the above plus Ronald L. Shearin, Environmental Project Specialist of Shearon Harris Nuclear Plant of CP&L). In addition, the documentation on procedures provided by Mr. Harris has been reviewed and a tour of Shearon Harris was made with other members of the Council, including their environmental monitoring labs. Based on the above information, I can report to the Council that the NCSU program has been thoroughly reviewed. Enclosed are some general ccaciusions and some recommendations for changes in the current program. I am sorry I will not be available te discuss these recommendations with the Council, as I will be off-campus for the rest of September and October. However, Ralton Harris vill be able to elaborate on any of these and on our meetings. 1 trust the Council vill take appropriate action on these recommendations. I felt that it was most important to compare our program in detail with that , of Shearon .larris. They have 'a different magnitude of concern and their > program is much more closely regulated. However, their monitoring program provides a modern, well-reviewed model. Mr. Shearin has cooperated with us to an exceptional degree, and his expertise contributed much to this audit. The following general conclusions have been made
- 1) The present program monitors all pathways, but not as ef ficiently as it should. The major fault of the present program is the antiquated gamma-analysis procedure through no fault of the people involved, the reaults are not timely, and they are subject to equipment break-down and slow data processing. A new multichannel analyzer with data analysis capability should be top priority in the up-grading of this program. Additional shielding for the detector should also be obtained. .
- 2) Environmental monitoring has two parts: monitoring of the reactor effluents directly to insure that no release occurs or to place the reactor on condition of Unusual Event or Alert if something is detected, and perimeter monitoring to insure that the results of direct monitoring have not been in error. Both are performedt direct stack monitoring, daily air filter analysis in the reactor building, and perimeter air monitoring on a weekly basis, plus TLD environmental stations and milk, water, soil, and vegetation analysis. However, these menitoring programs are cur-rently carried out by several different groups. It appears that a more ,
effective program would provide more administrative coordination. In particular, the results of the daily and weekly air monitoring should be compared on a regular basis and the environmental TLD data should be included in any environmental monitoring reports. Comparison of results with the State labs is currently done, but perhaps should be on a more regular basiw to insure accuracy. Page 1 of 2
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- 3) Shearon H M = emphasizes modeling the effects of environmental release on the population. n is seems impractical considering the computer effort and unnecessary considering the lov levels involved in our present PULSTAR operation. However, the monitoring program should review the documentation on modeling to insure that it is unnecessary.
It seems that the current monitoring program could satisfy these require-ments by specifying detection limits (sensitivity) for each of its measure-ments and calculating that the measured values pose no hazard. It should be pointed out that the Council's review of all experiments proposed for the reactor, as well as any involving radioactivity, is a crucial safety precaution in the environmental program.
- 4) On the basis of this audit, a number of changes are recomended for the current environmental monitoring program to make it more efficient. Some of these vill require new equipment in addition to the multichannel analyzer.
Overall, they should reduce the work load of the present staff. The following changes in specific monitoring procedures are recomended: a) Environmental TLDs should be of the highest sensitivity available and should be counted no more than semi-annually to provide increased sensitivity. b) ne present air samples should be replaced with Positive Displacement Pumps capable of continuous operation over the PULSTAR operating period (Monday-Friday). A new air monitoring station in the normal plume path should be added,(e g Poe or 1911). One day for decay should be the operating procedure rather than the current ten days. c) The water samples should be analyzed by runniq through an ion exchange column rather than by boiling, which is time-consuming ' and produces loss of volatile fission products. De resin can be gamma-counted directly. 131 Sr analysis in milk is unnecessary, unless I usults mye d) ne i positive. It is subject to error and false positive results. A larger volume (1 t) should be used for the 131I analysis, e) Soil analysis is unnecessary. It provides no data which are pertinent to the program. f) Vegetation should be sampled more frequently during the growing season. Crass samples can be analyzed directly as pellets by gamma counting. cc: D. W. Morgan, Radiation Protection Officer R. J. Harris, Environmental Health Physicist G. D. Miller, Associate Director, Nuclear Reactor Program R. L. Shearin, Environmental Project Specialist, CP&L l l 1}}