ML20080J014

Responds to NRC Re Violations Noted in IE Insp Rept 50-272/82-28.Corrective Actions:Setpoint of Radiation Monitor 1R16 Will Be Lowered for Quantifying Abnormal Conditions

ML20080J014
Person / Time
Site:	Salem
Issue date:	08/24/1983
From:	Liden E Public Service Enterprise Group
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20080J013	List: ML20080J014
References
NUDOCS 8309260094
Download: ML20080J014 (31)

Text

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Public Service Electoc and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038 Nuclear Depadment August 24, 14R3 Dr. Thomas E. Murley, Regional Administrator Region I U. S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, Pennsylvania 19406

Dear Dr. Murley:

INSPECTION REPORT NO. 50-272/R2-2R NO. 1 UNIT SALEM GENERATING STATION SEPTEMBER 3, 1982 In Inspection Report No. 50-272/82-2R a violation on the report-ing of gaseous radioactive effluents was found. In our response to the Notice of Violation, dated February 4, 14R3, and in a subsequent letter dated March 4, 1983, we indicated that we would review all Radioactive Effluent Release Reports (RRRRs) from 1976 and revise them to reflect our best estimate of noble gas effluents based on recent reviews. The results of this review are provided in the attachment to this letter.

In your inspection report and in your Health Physics Appraisal conducted at Salem in 1980, it was indicated that a mechanism did not exist for quantifying anomalous releases which could have occurred between routine samplings of the plant vent. Tn our letter to you dated February 4, 1483, we indicated that since the 1R16 Unit 1 plant vent radiation monitor setpoint was 500,000 counts per minute in the past, our staff did not con-sider count rates above background, but below the alarm setpoint as indicating an anomalous condition. However, we agree that lowering the setpoint of radiation mon litor 1R16 to a lower value for quantifying abnormal conditions is appropriate. (Ry applying a new setpoint of 10,000 counts per minute, abnormal disch'arges can be assumed to have occurred in the interim between our nor-mal weekly and monthly grab sampling, which were not specifi-cally referenced in our Radiological Effluent Release Reports.

We have previously identified these possible discharges to you and have quantified them in our February 4, 19R3, letter.

We would like to emphasize that it is our position that our previously submitted RERRs were prepared in a manner consistent with Regulatory Guide 1.21. Th9 additional " abnormal releases,"

which could have occurred in the period between our normal arab 8309260094 830922 PDR ADOCK 05000272 G PDR The Energy People mn u n

Dr. Thomas E. Murley, Regional Administrator U.S. Nuclear Regulatory Commission R/24/R3 samples, seem to indicate in some cases higher cumulative curie quantities being discharged than previously reported. We main-tain, however, that the activity represented by these " abnormal releases" is an upper bound only. In re-estimating the cumula-tive totals, conservative relationships were used, and because the activity of the vent samples is below analytical detection limits, this upper bound is an uncertain measure of the actual release.

Should you have any questions in this regard, do not hesitate to contact us.

Very ruly yours,

. A. Liden Manager - Nuclear Licensing and Regulation Attachment CC: Mr. Donald C. Fischer Licensing Project Manager Mr. Leif Norrholm Senior Resident Inspector I

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l RE-ANALYSIS OF RADIOLOGICAL RELEASE REPORTS (SALEM NUCLEAR GENERATING STATION)

GASEOUS RELEASES In your Inspection Report No. 50-272/82-28 you requested that we comr.ent on the validity of prior Radiological Effluent Release Reports (RERRs).

It was and still is our position that the methods which we used in our preparation of the RERRs were consistent with Regulatory Guide 1.21. It is our position that these reports would be inaccurate only if during the reporting period abnormal releases occurred which were not concurrently re-

. ported to the USNRC as batch releases.

Since the 1R16 channel setpoint was set at 500,000 cpm, which in the past was the ETS limit, our staff did not consider count rates above " normal levels" but below this value as an abnormal condition. By applying our new setpoint of 10,000 cpm to past data, abnormal discharges can be said to have occurred in prior years which were not included in our RERRs.

We have previously identified those discharges and have quan-tified them for your review in our letter dated February 4, 1983. We acknowledge that our alarm setpoint value of 500,000 cpm, although below our Technical Specification limits, was set too high to provide for immediate identification and quan-tification of abnormal conditions.

Since actual sample data are not available for these releases, we have utilized conservative default relationships between the radiation monitor instrument responses and radioactivity concentrations to develop release' estimates.

Since perturbations in RMS readings are expected to occasion-ally occur during routine and non-routine maintenance, inspec-tion, and other plant activities, certain distinctions must be made concerning the treatment of 41evated plant vent RMS readings. For purposes of emergency planning efforts, we have defined UNPLANNED / UNCONTROLLED rel3ases as those releases of

radioactive gases from the plant which are not expected from i

routine and non-routine maintenance, inspection and other plant activities. The plant vent noble gas monitors (lR16, 2R16, 1R41C, 2R41C) will be used to quantify abnormalities in conjunction with reliable sample data if they are available.

For emergency planning notification purposes, an UNPLANNED OR UNCONTROLLED RELEASE will be defined as any release in excess of 25 percent of our Technical Specification limits. Before this instantaneous limit is reached, PSE&G investigates in-creases of the RMS vent monitors whenever levels exceed 500 uCi/sec. (less than one percent of our Technical Specification limits). We have defined this condition as an INVESTIGATION LEVEL.

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When this level is attained, investigation is required to determine the cause of the " upscale" meter response and quantification of release is required if there is any reason to believe that the meter response is actually based on the

-presence of increased radioactivity in the plant vent. The increased level of radioactivity may be related to routine activities or may be indicative of a developing problem. In any case, investigation includes obtaining a plant vent grab

. sample and noble gas grab samples within the plant if this is practical.

Utilization of this technique permits the quantification of any releases which may have occurred in between routine plant vent sampling periods for noble gases discharged to the environs.

We have described an overview of the quantification methods which we use in Figure 1. Quantification of radioactive gases from the Salem Station falls within one of the four categories listed below:

a.. Discharging of Waste Gas Decay Tanks

b. Containment Purges .

c. Continuous Releases from the Plant Vent (Grab Samples)

d. Elevated Plant Vent Radiation Monitoring System Readings-A review of each effluent release report is provided in the next section. S l

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Total Gaseous Activity Discharged

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Routine

- Batch Continuous Mode Mode Releases Quantification Method:

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. . Gas D'ecay Containment Periodic Analysis of Tank Releases Purge Grab Sample of Vent L

Quantification Method: .

Quant'ification Method:

Prior to Each~ Release Prior to Each Purge l

Analyze a Gr'ab Sample Analyze a Grab Sample l'

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a) Gas Decay or Purge.'in Pro'gress?

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.b) RMS Channel Faulty? '

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' d) line Voltage Spit.es Causing

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quantification Methed: FIG. 1

.,c Using Additional Grab , Sample

- ' date (if available) 'and RMS OVERVIEW OF HOW response are used. estimate RELEASE ESTIMATES ARE DEVELOPED f~' r,' total release activity l r,'

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TOTAL IODINE AND PARTICULATE ACTIVITY VENTED QUANTIFICATION METHOD:

WEEKLY SAMPLING OF PLANT VENT

! ROUTINE l MODE CONTINUOUS BATCH MODE j RELEASES ELEVATED GAS DECAY CONTAINMENT VENT RMS TANK RELEASES READINGS FIG.-1 (Cont'd) i OVERVIEW OF HOW RELEASE ESTIMATES ARE DEVELOPED NCA:' sal * '

6/20/83

ERROR ASSOCIATED WITH CUMULATIVE CURIE ESTIMATES FROM VENTILATION.. SYSTEMS EFFLUENT BASED UPON MONTHLY GRAB SAMPLING All samples of the plant vent are analyzed by PSE&G for compliance with the requirements of Table 2.3-2 of the Salem Environmental Technical Specifications. The Salem Environmental Technical Specifications require that all monthly gas samples be analyzed such that a concentration of 10-4 uCi/cc (or lower if readily achievable) be detectable.

All of the vent samples analyzed by PSE&G met this requirement. The minimum detection limit of 10-4 uCi/cc developed by the USNRC is based upon technical feasibility and upon the potential for significant environmental impact. In general, most of the routine monthly vent gas grab samples collected by PSE&G contained less then 1 x 10-b uCi/cc of noble gas activity.

In developing estimates of the routine activity being vented from the Salem Station, the results of the routine monthly vent grab samples were multiplied by the volume of effluent vented from the respective nuclear unit. If the assay of the plant vent grab samples indicated that the sample was less than the lower limit of detection (LLD) of the analytical technique, PSE&G did not assume that the activity in the vent was numerically equal to the LLD value. In the past, if noble gas activity was detected on either the weekly particulate or iodine continuous sampler devices, then PSE&G included this activity in our reports.

Using the detection threshold value, it can be shown that release estimates would be a small fraction of Technical Specification limits if it is assumed that the average vent flow is 70,000 cfm and the LLD for noble gas analysis is 1 x 10-6 uCi/cc.

In our response to the USNRC letter dated February 19, 1976 concerning compliance with 10CFR 50, App. I, PSE&G indicated that approximately 1200 curies /yr of noble gases would be discharged from our station through routine Reactor and Auxiliary Building Ventilation System operation.

It can be demonstrated that if 1200 curies /yr are discharged uniformly over a calendar year, it would correspond to a concentration of approximately 1 x 10-6 uCi/cc if the average ventilation system flow rate was 70,000 cfm. Grab sample l " snap shots" of the plant vent would not discern this activity l if the LLD was 1 x 10-6 uCi/cc.

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- .- 1976 (We revised RERR-l'-to reflect the elevated '

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• REV. 1 . , -

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1976)

RERR-1 ,;

GASEOUS EFFLUENTS-SUMMATION OF.ALL RELEASES .

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Unit Quar,ter Quarter Est. Total.

3' 4 Error %

A. Fission & activation gases .-

1. Total release ci

2. Average release rate for period 7.61E-01 10%

3.

44C1/sec. 9.57E-02 Percent of Technical specification limit SG '

(See sets Spec. 2.3.3.2) l.62E-04

,B. Iodines e' -

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Total iodine-131 '- ' '> -

Ci

2.

Average release rate for period (1) 3.

44 Ci/sec.

Percent of technical specification limit  %

• C. Particulates f., ,

1. Particulates with half-lives- 8 days Ci

2. Average release rate for period (2) '

3. 4Ci/sec.

Percent of technical specification limit $6

4. G ross alpha radioactivity t

• Ci D. Tritium

1. Total release i ci

2. Average release rate for period 1.46 E-5 10% .

3.

44Ci/sec. 2.56 E-4 ( 3)

Percent of technical specification  % (4)

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i (1) No detectable levels of iodine 131 were present in releases for the period from December 11, 1976 to December 31, 1976. The detectable level for I 131 was t

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approximately 2.54 E-14 uC1/ml during this period.

I (2) No detectable levels of particulate matter with half lives > 8 days were present in releases for the period of record (Dec. 11, 1976 to Dec. 31,'1976) The lower limit

• of detection for the principal gamma emmitting particulate was 2.25 E-9 uci/ml for CO-60.

(3) Calculated during Batch Release only. g (4) No Technical Specificetion Limits.

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TABLE 1B RERR-1 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1976)

GASEOUS EFFLUENTS-ELEVATED RELEASE

_ CONTINUOUS MODE BATCH MODE j 3rd 4th 3rd 4th Nuclides Released Unit Quarter j Quarter Quarter Quarter

1. Fission gases Krypton-85 Ci Krypton-85m Ci Krypton-87 ,

Ci Krypton-88 Ci -

Xenon-133 Ci 8.90 E-5 X'non-135 Ci Xenon-135M Ci Xcion-138 Ci Others (soecify) Ci -

Ci Ci Unidentified C1 -

E," 7 3,1r-o1 Total for period Ci _.l- -

l 7.61E-01

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l Iodine-133 Ci .

l Iodine-13 5- Ci ~1 -

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Strontium-89 Ci Strontium-90 Ci .

Camium-134 Ci Camium-137 Ci Barium-lanthanum-140 Ci Others (seecify) Ci

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. Tritium I

l Ci i l I l 1.46 E-5 l

1) Other than Xe 133 all fission gases were below detectable activity

l. (Approximat'eiy less than 6.67 E-7 uci/ml) .

2) Weekly sampling of the plant vent has indicated that there is no detectable Iodine activity (Approximately less than 2.5414 uCi/ml for I-131) .

- REV. 1

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E RADIOLOGICAL IMPACT ON MAN

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The calculated doses in this section pertain to tho se received in unrestricted areas. -

LIODID PATEWAYS Deses to individuals in the population resulting from liquid pathways will be provided at a later date, as sample analysis has not been fully completed. These dose {

will be relatively insignificant as the only liquid patbvay is the ingestion of seafood. The low-level liquid releases coupled with the small seafood harvest during the month of December will result in a minimal impact.

-- AIR PATEWAY The' individual and population doses resulting from the release of radioiodines and particulates will be f._ inconsequential as there was no iodine or particulates present .in any of the samples taken for this period of

record. . .

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There were only two-isotopes ' identified as a resB1t of -

gaseous. samples taken during this reporting period. ThesG isotopes, Xe-133 and E-3, were identified as a result of

. - . sample . analysis. . The .resulting . maximum, unr e s tr ic t ed -

f . . area; whole. body.and . skin doses were calculated to be 1.53E-05 mrem and 4.3'4Ew05 mrem respectfully. The highest dose to any organ dose from radioactive iodines and part'iculates was not calculated due to their absence in

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l s a=pl e analysis . - Th e calculated population whole body l

- - -- dose .was 2.57E-07 man-rem. The average total body dose

- <: to the popclation :within 50 miles of the - site was 5.30E--

. :- 08 mrem. .

.[- The doses were calculated using methods described in Regulatory Guide 1.109.

, - DIRECT RADIATION

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I The dir.ect radiation, resulting from station operation, 19 l considered to be.zero due to the shor t cperating period l and low-level operations for this period of record.

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1977 .

f (It was not necessary to change RERR-2.

We revised RERR-3 using the estimates previously supplied to you in our February 4, 1983 memo.)

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. REV. 1 RERR-3

. Part E. Radiological Imoact on Man .

The calculated individual doses in this section are based on actual locations of nearby residents'and farms. ,The population dose impact is based on the projected 1980 population and site specific data i.e., food production, milk production, feed for milch animals and seafood production, gathered during 1976.

The doses were calculated using methods described in Regulatory Guide 1.109 and I,epresent calculations for the six month reporting interval. - .

Liquid Pathways ,

Doses to individugJs in the population from liquid releases are

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primarily from the seafood ingestion pathway. The maximum ,

total body dose to an individual was calculated to be 3.65r-1 mrem. The calculated population total body dose was 5.58E-2 man-rem. The average total body dose to the population within fif ty miles of the site was 1.04E-2 mrem. The highest organ-dose from liquid releases was 2.62E-3 mrem to the -

gastrointestinal tract.

. .. Air Pathways The resulting maxim,um whole body and skin doses to an individual :

were calculated to be 1.67E-Olmrem and 1.67E-01 mrem respectively.

The calculated population total body dose was 1.72E-01 man-rem.

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. - The average total body dose to the population within fif ty miles

.of the site was 3.21E-05 mrem / person. ,

Di ect Radiation Direct radiation may be estimated by TLD measurements. One method for comparing TLD measurements ~ is by comparison with ~

preoperational data. Direct' radiation ~measuremeht's of on site

! locations averaged only 4.77 mrem / month. This value is not sta.tistically different f rom the preoperational value of 4.4 2 mrem / month.

Maximum Organ Doses The maximum organ doses from radioactive iodines and particulates was 5.39E-6 mrem to the thyroid. -

Part F. Meteorological Data Cumulative joint wind frequency distribution by atmospheric

, stability class are provided for the third and fourth quarters Tables 7 and 8 provide joint wind

. of 1977 as Table 5 and 6.

frequencies during batch releases.

P77 77 10 - ..

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EFFLUENT AND WASTE DISPOSA!. SEMIANNUAL REPORT (1977) REV. 1 GASEOUS EFFLUENTS-SUMMATION OF ALL BELEASES RERR-3 .-

Unit 3rd 4th Est. Total (2) ,

Guarter Quarter Error %

A. Fission & activation gases

1. Total release Ci 2.06E+00 4.35E+01 5.00E+01

2. Average release rate for period uCi/sec. 1.30E-01 5.'47E+00

3. Percent of technical specitication limit  %- 2.20E-06 9.24E-03 (See ETS Spec. 2.3.3.b)

(1)

D. Iodines ,

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1. Total iodine-131 Ci - -

2. Average release rate for period uC1/sec.-

3. Pe rcent of technical specification limit  %

t C. Particulates

1. Pa rticulates with half-lives 8 days di 3.91E-10 - 5.00E+01

2. Average release rate for period uC1/sec. 2. 4 62~-11 -

3. Percent of technical specification limit _% 1.89E-10 -

4 Gross alpha radioactivity Ci -

LLD' LLD D. Tritium

1. Total release Ci 9.07E-01 5.02E+01 5.~0 0 E + 01

2. Average release rate for period uCi/sec. 5.80E-02 2.16E+00

3. Percent of technical specification limit  % N/A N/A (1) No detectable levels of iodine 131 were present in releases for the period from July - December 1977.

(2) For batch releases the estimated overall error is within 10%.

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(We changed RERR-4 using the estimates previously supplied to you in our .

February 4, 1983 memo. It was not .

necessary to change RERR-5.)

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• RERR-4  !

Part E. Radiological Impact on Man

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The calculated individual doses in this section are based on actual locations of nearby residents and f arms. The population dose impact is based on the projected 1980 population and -

historical site specific data i.e., food production, milk production, f eed for milch animals and seafood production.

l The doses.were calculated using methods described in Regulatory Guide 1.109 and represent calculations for the six month reporting i interval. .

4 Licuid Pa thways i

. l Doses to individuals in the population from liquid releases are primarily'from the seafood ingestion pathway. The total body ,

. dose to an individual was calculated to be 7.95E-3 mren. The

. calculated population total body dose was 3.96E-2 man-rem.

The highest organ dose from liquid releases was 2.78E-2 mrem to the gastrointestinal tract.

Air Pa thways ,,

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~ 2 calculated to be 2.49E-2 mrem and 2.49E .2 mrem respectively.

iThe calculated population, total body dose was 2.59E-0 man-rem.

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[. Direct Radiation C _D rect radiation may be estimated by TLD measurements. One -

7 _ method for comparing TLD measurements-is by comparison with -

preoperational data. Direct radiation measurements of on site 2 -

1ocations averaged only 4.46 mrem /m6nEh. This value is not statistically different f rom the preoperational value of 4.42 mgem/ month.

Maximum Organ Doses -

T'he max'imum organ doses from radioactive iodines and particulates was 2.85E-2 mram to the GI-Tract.

.Part F. Meteorological Da ta Cumulative joint wind f requency distribution by atmospheric stability class are provided for the first and second quarters of 1977 as Table 5 and 6. Tables 7 and 8 provide joint wind -

frequencies during batch releases.

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, _-- _ - , e f.F1 1.Ul.flT AtlD WASTE Dl!!POS AL S EM I AtittuAl. It El'OltT l 19 'l lt ) REV. 1 GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES ,

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Unit 1st 2nd Est. To tal ( 2 )

Quarter Quarter Error 1 .

A. Fission & activation gases 1 To tal release C1 2.48EF00

2. Average release rate for period 3.42E+01 2.50E+01 i 3. Pe rcen t o f technical specification limit uCi/sec. ,3.19E-Ol 4.5SE+00 l (See ETC Spec. 2.3.3.b) 5.63E-04 1.64E-02_.

(1)

B. Iodines

1. To tal iodine-131 '

Ci -

6.11E-05

2. Average release rate for period 2.50E+01

3. uC1/sec. -

7.778-06 Pe rc en t o f technical speci fica tion limi t

' t 1.51E-03 C. Pa r ticula tes -

1. Pa r ticulates wi th hal f-lives > B days C1 3.12E-05 0

2. Average release rate for period

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3. uCi/sec. 4.01E-06 0 Pe rcent o f technical specification limit t

4. 7.82E-04 0 Gross alpha radioactivity Ci 4.98E-08 3.07E-06 2.50E+01 ,

D. Tritium

1. To ta l release 2.

Ci' 1.29E+02 0 2.50E+01 Average release rate for period uCi/sec.

3. Pe rcent of technical specification limit 1.66E+01 0

% N/A 0 (1) January No detectable

- Marchlevels 1978. of lodine 131 were present in releases for the period from (2) For batch releases the estimated overall error is w'ithin lo t.

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o o o o o m - i n e e e e c t t m m m h b

' R t

n n n n 3 n r e l n n n n l i n n u u lu t u s e 2 i t. t t a t o o i i O R s d 6 s s p p p p o o o o 3 o o d a i i i i r r r s s r o i e s y y y y n n n n 1 g u i t d d d d t t e e a r n 9 r r r r e e e e e r l n o o o o o o a t

, d i U T T P S S C C B G U 9 K K K K X X X X X A F I I l I i F l 8 c . . 7 u .

3 P 2

N 1

'  ;' ' , t i l '

. . . - . .- .. _= .- . - - - . . - . - . . - . - . - _ . . __ .__ - _- .

, 1 .

, r. s

? .

t

l 1

1 ll

, d i

i

• E l .

l

( .

1

! 3 1979 I -

(It was not neciessary to change RERR-6.

~~. We changed RERR-7 using the release

estimates previously supplied to you

~ ].., in our February 4, 1983 memo.)

m

, 9 O

W g

e 4 O E* .

m "4

W O e

4 0

g e 4 e

t.

l l

L

REV. 1 f' RERR-7 Part E. Radiological Impact on Man The calculated individual doses in this' section are based on actual locations of nearby residents and farms. The population' dose impact is based on the projected 1980 pop-ulation and historical site specific data i.e., food pro-duction, milk production, feed for milch animals and sea-food production. '

The doses were calculated using methods described in Reg-ulatory Guide 1.109 and represent calculations for the six month reporting interval. Doses from batch and continuous releases were calculated using the meteorological disper-sion coefficient X/O for the period July 1 - December 31, 1979.

Liould Pathways Doses to individuals in the population from liquid re-

leases are primarily from the seafood ingestion pathway.

The total body dose to an individual was calculated to be 4.50E-3 mrem. The calculated population total body dose was 1.10E-1 person-rem. The highest. organ dose from

- liguid releases was 2.95E-2 mrem to the gastrointes'tinal l . = tract.

p Air Pathways l(^

. The resulting whole body and skin doses to an individual were. calculated to be 2.32E+0 mrem and 2.63E+0 mrem re-G spectively. The calculated population total body dose was

'- 1.27E+2 person-rem. The average total body dose to the population within fifty miles of the site was 5.00E-3 mrem / person. .

C Direct Radiation

.i ._ . .--. - .-

Direct radiation may be estimated by TLD measurements.

! @, one method for comparing TLD measurements is by comparison with preoperational data. TLD measurements on site near the Se rvice Water pumps (location 11S1) and (location

f. 10S1) near the Circulating Water pumps averaged 21.6 and 9.2 mrads/ months, respectively,

7 .: apparently due to trace activity in the Refueling Water Storage Tank.

TLD's at onsite locations 2S1 and 5S1 which are 0.3 miles l and 0.9 miles from the reactor containment averaged 5.82 and 4.44 mrads/ month respectively. These values are within the statistical variation associated with the preoperation program results which were 4'.57 + 2.00 and 3.91 + 0.62 mrads/ month for stations 251 and 351, respe ct i,ve,1y.

,- l l

- j- , y - - - - - - - - - - - - - ----- -

, --- y--

TAlli.15 1 A REV. l' '

EFFl.UEtiT AtID WASTE DISPOSA!. SEMI ANNUAL IIEPORT (1979) -

GASEOUS EFFLUE!1TS-SUMMATIOti OF AI.I.' ilELEASES RERR-7 ..

3rd 4th Est. Total (l)'

Unit Guarter Quarter Error t A. Fisalon & activation gasco

1. Total release Ci 1.31E+03 2.46E+02 2. 50 E4 01

2. Average release rate for period uCL/sec. 1.65E+02 .U0VE+01'

3. Percent of technical. opecification limit 1 2.79E-01 5. 23E- 0 2 (See ETS Spec. 2.3.3.b) iB . Iodinen (2) '

i

1. Tota 1 lodine-131 - C1

2. Average release rate for period uCi/sec.

3. Percent of technical specification limit  %

C. Particulates , ,

l. Particulates with half-lives) 0 days - Ci T.57E-04 2.50E+01

2. Average release rate for period uC1/sec. 9.63E-05

3. Percent of technical specification limit  % 1.00E-02

4. Gross alpha radioactivity '

C1 D. Tritium'

l. Total release Ci 2.40E-03 2.50E+01

2. Average release rate for period '

uC1/sec. 3.05E-04

3. Percent of technical specification 1imit  ?, II/A (1) For batch relcanes the estimated overali error is within 10%

I (2) Iodine was below the minimal detection limit.

H P0014/19 1

_ 1 7

. R l l 4 4 V R O O 0 0 E E r - - - -

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E 4 7 E

7 E

E t r 0 0 5 5 Q 4 a ~ . .

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. ( o o u o

. i - i n i s d s r r a r a e e de e n 9 0 h e w s s m 0ep ) p e 0 9 t l f a P a a 557 l m m 1i 2 1 3 5 t - - 4 7 n l f h e e g 000 l

O35503 f r ( 31 3 ' r a m m 3 3 a. 0 - p l f r n l - - 333331 eio 1 l 1 o l u u L 1 I 6 m l 5 o i e n nnn n1 11 1 14 ntf s - - - f u i i - - - u A - F d t

o ooo - - i n e ee e c t t m m m t i t o I

i t tt o. n n n n- nnrel n nn n l i n n u u u l d s L l I

. s s t

ppppoooooooda i ii i a t o o i i i a l s a a e s yyyynnnnngnit d dd d t r r r s s r l i

l i

o b t )

d i rrrreeeeer1 no o oo o o a tt e e a o u r o o 2 i F KKKKXXXXXAFtiT I I l l T P S S C C l I C I t

G C T (

l c

b l

u .

2 3

w t ._ 1

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

, j

. e e s

• I i,

i I, .

t  !'

l I -

e I'

i I

is i

=

4 1

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. + ..

- ~ .

. :u.~ - . .

'f- --

1980 .

.i -

. .s ,

.5 .

. .- . (It was not necessary to amend RERR-9.

, . We amended RERR-4 using the release 4

estimates previously supplied to you.)  ;

, .m, .m. .

6%

M 4 g O e.,

em ee l

j .. #

5 t

e er e

i 1

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e e e f

d

)

I

,,-r,a-,.-,r-- ,y -,.-,,,,- nn e, ,--.n, ,-n- .-,---n--e ----,---.-.-~.,,,-n-,--,---,..--..,.-,_--.,w.w,an - ,--- n- - n.-enn.,----

- - _ REV. 1 RERR-8 Part E. Radiolocical Imbact on Man T'he calculated individual doses in th'is section are based on actual locations of nearby residents and farms. The

"- population dose impact is based on the projected 1980 pop-ulation and historical site specific data i.e., food pro-

- duction, milk production, feed for milch animals and sea-

! food production.

'., The doses were calculated using methods described in Reg-l-

ulatory Guide 1.109 and represent calculations for the six month reporting interval. Doses from batch and continuous releases were calculated using the meteorological disper-

sion coefficient X/Q for the six month reporting interval.

J  : .

Liouid Pathways a -

Doses to individuals in the population from liquid re-leases are primarily from the seafood ingestion pathway.

The total body dose to an individual was calculated to be 4

2.69E-3 mrem. The calculated population total body dose was 1.26E-2 person-rem. The highest organ dose from

'~

" g'. . .. ~

l'iquid releases was 7.79E-3 mrem to the gastrointestinal

~

m 1 tract.

r  : -

et Air Pathways Il _ The resulting whole body and skin doses to an individual "I . - were calculated

- spectively.

to be The 2.84E-2population calculated mrem 'andtotal 2.59E-2 bodymrem dosere-was ~

l lq _ g 3.13E-0 person-rem. The average total body dose to the -

pl 0 - population within fif ty miles of the site was 6.78E-4

mrem / person. .

[] Direct Radiation Direct radiation'may be' estimated by TLD measurements.

, One~ method for comparing TLD measurements is by ccaparison f3i - with preoperational data. TLD measurements on site near the Service Water pumps (location 1151) and near the Cir-n.

culating Water pumps (location 10S1) averaged 18.3 and 9.1 mrads/ months, respectively, apparently due to trace activ-ll*

• ity in the' Ref ueling Water Storage Tank.

TLD's at onsite locations 2S1 and 551 which are 0.3 miles

]

l and 0.9 miles from the reactor containment, averaged 5.73 and 4.75 mrads/ month respectively. The values for station 2S1 are within the statistical variation associated with the preoperation program results which' was 4.57 + 2.00.

,t -

[1 Values at onsite location 551 were slightly higher th'an preoperation value of 3.91 + 0.62.

,~

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l e

u' *--. a v

L%- > s- J wi L4 & & U l) L .) l.& $ .J *s..)]

>.I

~

TABLE.1A i REV. 1 .-

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1980)

• GASEOUS EFFLUENTS-SUMMATION OP'ALL RELEASES -

RERR-8 lat 2nd Unit Quarter Est. Total (l)

Quarter Error %

A. Pission & Activation-Gases .

o

1. Total release Ci 9.27E+00 2.. Average release rate for period uCi/sec.

3.96E+01 2.50E+01~~

3. Percent of technical specification.llmit ~1.18E+00 5.04E+00' 1 2.23E-03 (See ETS Spec. 2.3.3.b) .

9.51E-03 B. Iodines a

1. Total iodine-131 *

2. Average release rate for period Ci 4.50E-09 8.39E-05 2.50Et01

3. Percent of technical specification limit uCi/sec. 5.73E-10 1.078-05 -

% 1.00E-12 2.02E-08 C. Particulates '

~

l. Particulates with half-lives) 8 days Ci 1.65E-04 1.18E-03

2. Average release rate for period 2.50E+01

3. Percent of technical specification limit' uCi/sec. 2.10E-05 1.50E-04 ~~

4. Gross alpha radioactivity (2) e

% 4.09E-03 2.92E-02 Ci - -

D. Tritium' '

1. Total release *

2. Average release rate for period Ci 1.46E-05 7.01E-3 2.50E+01

3. Percent of technical specification limit uCi/sec. 1.86E-06 8.92E-04

% N/A N/A (1)

(2) For batch releases the estimated overall error is within 10%.

Analyses indicate no measurable alhha emitting transuranics.

M P8014/19 1 -

1 8

~-

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E

• dt nr E

0 0 E EE 66 3 E EE 97 f-9 E 2

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M Q 4 4 33 1 22 1 9 21 l

i C

T A 223 2012 1 00 4 4 D r 000 0000 0 00 0 0

) e - - +- - ++ - -

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( Q 149 4651 l 18 l 1 TS RE >

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- E r 00 0 00 0 00 LR ' e .

A E dt EE .

E EE E EE UD D 6 nr 17 2 60 6 44 NE O12a 31 3 54 5 66 NT M u . . . . . . .

AA Q 35 3 63 6 66 IV S ME U BEL O 1SE U 17 1 99 9

- N r 00 0 00 0 RT.S I e - - - - - .

LAT T  : tt , EE ,

. .E E 'E E ,

l l SN N sr 13 1 03 3 AOE O .la 43 4 54 9 TPU C u . . . . . .

SL . Q 51 5 41 5 IF * ,'

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SU t . ' '

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DA NG . il A

T N

E -

U L

F -

F E

)

1 d d d

( o -

o o i i i d s r r r

- e e de e s 90 4 e s s m O ep ) p e 89 5 8a P a a S57 6 m m li 2 135 t - - 46 - 0h e g U80 035583 f r ( 333 r a mm30 e0 - p8r l - - - 333331 eio 111 o l uu1 - s6 ml5 o me

- e n nnn n1 1 1114 ntf s - - - f u ii- uA F R o ooo o-nnnnnnrel - in e eee c tt munti t

- i ttt t n nnnl i nnuialdsll ppp a t ooirgaisaa s s yyy'poooooooda i i i i w

e s ynnnnnguit d dddt r rrst nbbobt d i rrrreeeeerl no o oooo a tt et aouroo

• i F KKKKXXXXXAFiT t I I I I T P SSCYMCRGCT l

c

u . . .

llll[lllll((l 1 h

' e 1

1981 (It was not necessary to change RERR-ll.

We admended RERR-lO using the release estimates previously supplied to you.)

4

REV. 1 RERR-10 s Part E. Radiological Impact on Man The calculated individual doses in this section are based

] on actual locations of nearby residents and farms. The population dose impact is based on historical site spe-cific data i.e., food production, milk production, feed 1

l for milch animals and seafood production.

The doses were calculated using methods described in hag-ulatory Guide 1.109 and represent calculations for ths six I month reporting interval. Doses from batch and continuous releases were calculated using the meteorological disper-sion coef ficient X/O for the six month reporting interval.

I Liquid' Pathways Doses to individuals in the population from liquid re-I leases are primarily from the' seafood ingestion pathway.

The total body dose to an individual was calculated to be 1.21E-02 mrem. The calculated population total body dose.

I was 4.64E-02 person-rem. The highest organ dose from lig-uid releases was 5.59E-02 mrem to the gastrointestinal tract.

Air' Pathways .

The resulting whole body and skin doses to an individual I were calculated to be 2.80E-02 mrem and -3.16E-02 mrem re-spectively. The calculated population total body dose was 1._4.5E+00 person-rem. The average total body dose to the population within fif ty miles of-the site was 2.71E-04 ll mrem / person.

Direct Radiation Direct radiation may be _ estimated by TLD m6L5urements.

One method for comparing TLD measurements is by comparison with preoperational data. As mentioned in previous Efflu-ent Release Reports, TLD measurements at location 10S1 and 11S1 have averaged higher than at other locations. This was due to trace activity in the Refueling Water Storage Tank. The average of all on site TLD locations, except 10S1 and 1151, was found to be 5.30 mrem / month. This val-ue is within the statistical variation of the preopera-tional mean which was 4.42 + 1.18 mrem / month.

M P80 17 14 ~

. - ---~

I-*

T- r CL;;i 1T ~G - ~LO ~ ,u Cl+'

TAnLE 1A-1

REV. 1 '

EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT (1981) 's GASEOUS EFFLUENTS-SUMMATION OF ALL RELEASES' - RERR-10 .

UNIT 1 j '

1st 2nd Est. Total (l) '.

Unit Quarter Quarter Error %

k. Fission & Activation Gases .

1. Total release

2. Ci 2.96E+02 Average release rate for period 2.64E+02 2.50E+01

3. Percent of technical specification limit uCi/sec. T.'Al~E+01 3.36E+01" '

,(See ETS Spec. 2.3.3.b)

% 2.52E-01 2.23E-01

5. Iodines

1. Total iodine-131

2. Average release rate for period Ci t 8.74E-04 7.49E-03 2.50E+01

3. Percent of technical specification limit uCi/sec._ l.12E-04 9.53E-04 2.18E-02 1.86E-01

. Particulates '

1. Particulates with half-lives) 8 days Ci 1.76E-04 3.26E-01

2. Average release rate for period  !

2.50E+01

3. Percent of technical specification limit uCi/sec. 2.26E-05 4.lSE-02

4. Gross alpha radioactivity (2) t 4.41E-03 8.09E+00 Ci 0.00E+00 0.00E+00

l. Tritium -

t

1. Total release

2. Average release rate for period Ci 1.07E+00 2.96E-01

3. Percent of technical specification limit

+

uCi/sec. 1.38E-01 3.76E-02 4 N/A N/A (1)

(2) For batch releases the estimated overall error is within 10%.

Analyses indicate no measurable alpha emitting transuranics.

I I P8014/23 1 9-A O

. S.

0 1 1 3 4 3 2 23 2 2 0 1 3 4 2 2 0 0 0

. R r 0 00 0 0 0 0 0 0 0 0 - - -

V R e - - - - + + - - - + + 8 E E E E dt E E E E E E E E E E E 9 1 1

• R R E nr 1 8 6 9 3 3 4 3 9 9 4 1 2 3 D 2a 5 3 3 5 0 5 1 4 0 5 6 . . .

O u . . . . . . . . . . . 3 1 3 M Q 0 2 6 2 1 1 6 2 3 1 2 l

- i C -

T A 1 3 1 1 1 2 2 0 D r 0 0 0 0 0 0 0 0

) e - - + - - + + +

1 tt E E E E E E E E 8 sr 0 7 2 5 5 2 6 0 9 1 a 3 8 2 8 2 2 9 0 1 u . . . . . . . .

( Q 2 5 7 8 9 2 2 0 TS RE OS PA EE RL 3 2 2 3 4 3 E r 0 0 , 0 0 0 0 LR e - - - - - -

A E dt E E E 8 E E

UD D nr 3 9 0 0 4 0 '

NE O 2a 1 7 1 3 0 6 .

NT M u . . . . . .

AA Q 3 1 2 4 3 4 t 1IV S

- ME1U 0EL O A 1SETU 3 2 2 4 4 3 -

IN r 0 0 0 0 0 0 0 ELSNI e - - - - - - 1 LATUT tt E E . E E E E BSN N sr 2 3 6 4 6 7 AOE O l a 3 8 6 7 9 3 TPU C u . . . . . .

SL Q 8 8 9 8 4 1 IF DF

• 8 E

E TS SU t

- AO i 1 i i i ii i i i 1 i i i i 1 i 1 WE n C C C C C C C C C C C C C C CC C

• S U .

DA NG A

T N

E U

L F

F E

d d o -

o i i d s r r e

e d e

- e s s m 0 e p p a a 5 5 7 8 m m 1 i 1 3 5 e g 8 8 0 8 3 5 5 8 3 - f r 3 3 3 r 1

. . l - - - - 3 3 3 3 3 1 e i o 1 1 1 o 0 e n n n n n 1 1 1 1 1 4 n t f s - - - f

- . R o o o o o - - - - - - i n e e e e 2 i t t t t n n n n n n r e l n n n n l /

s s p p p p o o o o o o o d a i i i i a 4 e s y y y y n n n n n g u i t d d d d t 1 d i r r r r e e e e e r l n o o o o o o

_ i F K K K K X X X X X A F U T I I l I T 0 l 8 c . P u . .

N 1 2 M

' '