ML20087D972

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Addendum to Semiannual Radioactive Effluent Release Rept 1991:Quarters 1 & 2
ML20087D972
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 06/30/1991
From: Kensicki S
CLEVELAND ELECTRIC ILLUMINATING CO.
To:
Shared Package
ML20087D964 List:
References
NUDOCS 9201170225
Download: ML20087D972 (9)
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Tile CLEVELAND ELECTRIC ILLUMINATING COMPANY PERRY NUCLEAR POWER PLANT UNIT 1 ADDENDUM TO TIIE SEMI ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT 1991: QUARTERS 1& 2 Approved By:

r /

.b t?LO --/. 12AnDc W Director,Pefry Nuclear Engineering Department

)

Gederal Manager, Perry Nuclear Y iikcy .

Power Plant i% PDR 01170225 920113 7

  • I' ADOCK 05000440 PDR

._ -m- _ ._ _- > _ _ _ . . . _ _ . _ _ _ _ _ _ _ _ . . _ . - _ _ . _ _ . _ _

i 1991 QUARTER 1 & 2 SRERR ADDENDUM

SUMMARY

The_ analysis results for strontium 89/90 and iron 55, for the second quarter of 1991, were not included in the Semi-annual Radioactive Effluent Release Report for the first and second quarters of 1991.

These results were omitted because the analysis had not been completed by the contracted vendor laboratory.

The changes incorporating the strontium 89/90 and iron 55 results on the attached data sheets are'in bold and indicated with a revision bar in the right hand margin. A summary of these changes is provided as follows:

i

( 1.- ONSITE DOSE FOR LIQUID EFFLUENTS, page 5 t

1s. The Total Body dose, for the second quarter of 1991, increased from the reported value of 5.7E-03 mrem to 5.8E-03 mrem.

2._ RADIOLOGICAL IMPACT ON MAN (DOSE l SUMMARIES) Attachment 1, page 20

a. The Individual Liquid Total' Body dose, for the second quarter.

of 1991, increased from the report value of 7.86E-04 mrem to 8.02E-04 mrem.

b. The Individual Liquid Organ (Liver) dose, for the second quarter of 1991, increased from the reported value of 1.49E-03 mrem to 1.52E-03 mrem.
c. The Population Liquid Total Body dose, for the second_ quarter-of 1991 increased frcm the reported value of 5.4E-02 rem to 5.5E-02 rem.

l

~ - . - --. - . - . . -

i

3. LIQUID ErrLUENTS Att6chment 4, pages 27,28
a. The.rlssion and Activation Products Total Release (excluding tritium, gases and alpha), for the second quarter of 1991, ,

increased from the reported value of-1.96E-02 curies to 3.21E-07, curies.

I

b. The rission and Activation Products Average Diluted Concentration, for the second quarter of 1991, increased from the reported value of 7.76E-10 uci/ml tc. 1.27E-09 uci/ml.
c. The total curie release of re55, for the second quarter of 1991, increased from the reported value of 0.00E+00 curies to 1.05E-02 curies,
d. The total curie release of Sr89, for the second quarter of 1991, went from an unreported value to 2.04E-03 curies.  ;
e. The total curie release (minus xel33 and Xel35), for the second quarter of 1991, increased frcm the reported value of'3.09E+00 curies to 3.11E+00 curies.
4. GASEOUS ErrLUENTS Attachment 5, pages.30,31 ,
a. The total curie release, for Particulates with half-lives greater than 8 days, for the second quarter of 1991, increased from the reported value of 2.76E-07 curies to 9.56E-05 curies. t
b. The Particulate Average Release Rate, for the second quarter of 1991, increased from the_repotted value of 3.51E-08 uci/sec to 1.22E-05 uci/sec.
c. The total curie release of Sr89, for the second quarter of 1991, increased from the reported value of 2.70E-07 curies to 9.550-05 curies.
d. The total curie release of Sr90 for the second quarter of 1991, increased from the reported-value of 6.00E-09 curies to 2.47E-03 curies.

~

e. The total curie release of Sr89 and Sr90, for the second quarter of 1991, increased from the reported value of 2.76E-07 curies to 9.56E-05 curies.

RADIOLOGICAL IMPACT ON MAN

-Sampling and analysis of liquid and gaseoun effluents were performed in accordance with the frequencies, types of analysis, and Lower Limit of Detection (LLD) outlined in the PNPP Unit 1 Technical Specifications.

Radioactive material was detected in some of the liquid and gaseous effluent samples analyzed. Dose calculations, using measured effluent flow and meteorological data, resulted in dose to individuals at levels below 10CTR20 and 10CFR50, Appendix I limits. Direct radiation resulting from plant operation, as measured by environmental thermoluminescent dosimeters located around the plant, did not contribute any measurable dose to members of the public for the reporting period and, as there are no other nearby fuel cycle sources, 40CFR190 limits were not exceeded.

Summaries of maximum individual and population doses resulting from liquid and gaseous radioactive effluent releases are given, in Regulatory Guide 1.21 format, in Attachment 1.

Technical Specification 6.9.1.7 requires assessment of radiation doses from radioactive liquid and gaseous effluent to members of the public while onsite. These onsite doses are assessed relative to offsite dose values, and are adjusted for appropriate dilution, dispersion, and occupancy factors.

ONSITE DOSE FOR LIQUID EFFLUENTS The onsite liquid effluent pathway of concern for members of the public is shore exposure while fishang along the Lako Erie coast. Occupancy is assumed to be 60 hours6.944444e-4 days <br />0.0167 hours <br />9.920635e-5 weeks <br />2.283e-5 months <br /> per year and the dilutien factor for the-point of exposure is 10.

Ratioing this exposure _ pathway to doses calculated for offsite locations yields the following onsite dose values.

Total Body Organ Quarters 1 & 2 3.9 E-01 mrem 1.5 E-03 mrem (skin)

Quarter 1 3.8 E-01 mrem 1.4 E-03 mrem (skin)

Quarter 2 5.8 E-03 mtem 1.3 E-04' mrem (skin)

Attachment 1 (Continued - Page 3 of 3)

Radiological Impact on Man (Dose Summaries) 1991: Quarter 2 -

SUMMARY

OF MAXIMUM INDIVIDUAL DOSES LAST ACCUMULATIONS FOR PERIODSt

. LIQUID 91 4 1 1-91 63024 GASEQUS 91 4 1 1-91 63024 AIR 91 4 1 1-91 63024 APPLICABLE ESTIMATED AGE LOCA110N  % OF LIMIT EFFLUENT ORGAN DOSE GROUP DIST DIR APPLICABLE

- (MREM) (M) (TOWARD) LIMIT (MREM)

LIQUID TOTAL BODY 8.02E-04 ADULT RECEPTOR 1 2 7E-02 3.0Ef00 LIQUID LIVER 1.52E-03 TEEN RECEPTOR 1 1.5E-02 1.0E401 NOBLE GAS AIR DOSE 3.96E-02 283. WNW 4.0E-01 1.0Ef01 (GAMMA-MRAD)

- NOBLE GAS AIR DOSE 5.38E-02 '283. WNW 2 7E-01 2.0Ef01 (BETA-nRAD)

NOBLE GAS T.DDDY 2.56E-02 ALL 283. WNW 5.1E-01 5.0Et00 NOBLE GAS SKIN 6.77E-02 ALL 283. WNW 4.5E-01 1.5Et01

-IODINE 1 T4YROID 4.58E-01 INFANT 283. WNW 3.1Et00 1.5Et01 PARTICULATES

SUMMARY

OF POPULATION DOSES LAST ACCUMULATIONS FOR PERIODS!

LIQUID 91 4 1 1-91 63024 GASEOUS 91 4 1 1-91 63024 EFFLUENT APPLICABLE ESTIMATED ORGAN POPULATION DOSE (PERSON-REM)

LIQUID TOTAL BODY 5.5E 02 LIQUID THYROID 7.7E-03 GASEOUS TOTAL BODY 2.1E-03 GASE0US THYROID 1.6E-01 Attachment 4 (Page 1 of 2)

Liquid Effluents QUARTER 1 1 START DATE 91010101 END DATE'91033124 QUARTER 2 i START DATE 91040101 END DATE 91063024 EFFLUENT AND UASTE DISPOSAL REPORT LIQUID EFFLUENTS -- SUMMATION OF ALL RELEASES t UNITS 1 QUARTER 1 QUARTER 1 1 1 1 1 2 I A. FISSION AND ACTIVATION PRODUCTS i 1. TOTAL RELEASE (EXCL.: CI 3.92E-02 1 3.21E-02 i TRIT GASES: ALPHA)!

i..........................................__._  !  ! 1 I 2. AVERAGE DILUTED 1UCI/ML t 3 24E-09 . 1.27E-09 1 i CONC. DURING PERIOD 8 8 0.00Ef00 1 0.00Ef00 t t

I 3. PERCENT OF 1  % 1 hPPLICABLE LIMIT 1 1 1 B. TRITIUM CI i 1.01Et00 1 3.07Ef00 t I 1. TOTAL RELEASE t

't 2. AVERAGE DILUTED IUCI/ML 1 0.37E-08 1 1.22E-07 1 1- CONC. DURING PERIOD 1 1 1  !

! 3. PERCENT-OF 1  % i 2.79E-03 1 4.06E-03 1 1 APPLICABLE LIMIT  ! t i 1 C. DISSOLVED AND ENTRAINED GASES I 1. TOTAL. RELEASE-  ! CI t 1.17E 03 1 1.33E-03 1

! 2. AVERAGE DILUTED tuCI/ML 9.64E-11 1 5.26E-11 1 1 CONC. DUR1HO PERIOD !  !  !  !

! 3. PERCENT OF t  %  ! 4.82E- 05 1 2 63E-05 8 AP

. . . . . . . .P.L _I _C.A B .L.E. L.I .M.I .T. . . . . . . . . . . .1 . . . . . . . . . .1 . . . . . _ _ _ . .1 D. GROSS ALPHA RADI0 ACTIVITY I 1. TOTAL RELEASE  : CI 9.29E 05 1 0.00Ef00 t E. VOLUME UASTE RELEASED ILITERS 1 1.90Ef09 8 4.19Ef09 1 8 (PRIOR TO DILUTION)  !  ! 1 t 1 USED DURING PERIOD  !  !  !  !

, . ~. .- .,- -.

Attachment 4 (Continued - Page 2 of 2)

Liquid Effluents QUARTER 1 1 START DATE 91010101 END DATE 91033124 QUARTER'tSlARTDATE{1040101 E"? DATE 91063024 DATE Of kEPORT! DEC. 1.e 1991 PREPARED BY!-

CONTINU0JS MODI BATCH MODE QUARTER I t NUCLID?.S t UNITS 1 QUARTEF. t DUARTER t OUARTER I RELEASED 1 1 1 2 1 1 1 2 i H3 1 CI 1 0.00E400 1 0.00EiOO t 1.01Ef00 t 3 07Ef00 .

. 1 CR51 1 CI i 0.00E100 1 0 00Ef00 t 8.47E-04 1 1.31E-02 I

I HN54 CI I 0.00EiOO ! 0.00Ef00 1 2.36E-03 t- 1.16E-04 1

! FESS t CI i 0.00EiOO t 0 00E400

  • 2.79E-03 ! 1.0SE-021 1 C058  : CI I 0.00Ef00 1 0.00Ef00 t 0.00E400 1 1.66E-04 1 1 C060 1 CI 1 0.00EiOO I 0.00Ef00 1 1.37E-02 ! 2.79E-03 1 I IN65  : CI 1 0.00Ei(0 1 0.00EiOO t 4.96E-03 1 2.5BE-03 1 I CRB9 1 CI 1 0.00Ef00 t 0 00E100 1 0.00Ef00 1 2.04E .

...........................__........_............................-03..%

2 TC99h  ! CI t 0.0]Ef00 1 0.00Ef00 t B.42E-06 1 0.00Ef00 t 1 A0110M 1 CI 1 0.00Ef00 1 0.00EiC0 t 2.10E-05 1 7.45E-04 8 t  : CI 1 0.00Ef00 1 0.00EiOO ! 5 94E-03 1 1.55E-05 t

...' CS13 4 t CS137 1 CI 1 0.00E400 1 0 00Ef00 t 8.37E-03 1 1.02E-04 1

!* SB125  : CI 0.00Ef00 t 0.00E400 1 2.42E-04 1 0.00E400 t E . PERICD- 1 CI t 0.00Ef00 1 0.00Ef00 1 1.05EiOO 8 3.11E+00 8 1 (ABOVE) i t i i  !  !

t* XE133:  ! CI 1 0.00Ef00 1 0.00Ef00 1 1.06E-03 1 1.20E-03 8

!* XE135 t CI 0.00Ef00 1 0.00Ef00 1 1.01E-04 1 1.31E-04 !

I Attachment 5 (Page 1 of 2)-

Gaseous Effluents QUARTER 1 1 START DATE 91010101 END DATE'91033124 OVARTER 2 1 STAkT DATE 91040101 END DATE 91063024 EFFLUENT AND UASTE DISPOSAL REPORT _

GASEOUS EFFLUENTS -- SUMMATION OF ALL RELEASES

! UNITS ! CUARTER t QUARTER t I i 1  ! 2 1 A. FISSION AND ACTIVATION GASES I 1. TOTAL RELEASE i CI t 3.00Ef00 1 1.33Ef01 1 i i 30iiiii EEEiisi---- iUEi7sici- l  !

i iii:51! i- i lifiB5 !i 1 RATE FOR PERIOD l 3. PERCE

. SPECITICATI DE EC N "ICAL!

IMIT !

1

! 0.00E100 { 0 00E100 tt B. 10 DINES 1 1. TOTAL 10 DINE-131 1 CI I 6.74E-04 ! 3.35E-03 1 j 2. RATE AVERA ORE PRERIODE(SE !UCI/ SECT 8.66E-05 ! 4.26E-04 1

. 1 8 t t t 3. PERCENT OF TECHNICAll  %  ! 0.00Ef00 1 0.00E100 1

...._-SPEC.IFICATI.ON LIMIT .!

C. PARTICULATES .

' t 1._PARTICULATES WITH  ! CI t 4.87E-05 ! 9.56E-05 t i HALF-LIVES >8 DAYS !  !  ! 1 I 2. AVERAGE RELEASE !UCI/SEC1 6.27E-06 1 1.22E-05 1 1 RATE FOR PERIOD  !  !  !  !

I 3. PERCENT OF TECHNICAll  %  ! 0.00Et00 1 0.00Ef00 t i SPECIFICATION LIMIT 1 1 1 1 1 4. GROSS ALPHA t ~ CI 1 8.96E-05 2.62E-05 I I RADIDACTIVITY t I t t D. TRITIUM I

..1 .. T.O.T.AL.R.E.L

.. . . E.A.S E. .. .....! ..C..I ..... .....

0 0 0 E.t 0 0 1. . 0 ..0 ..0.E.f 0 0..t 1 2. AVERAGE RELEASE !UCI/SECl 0.00Ef00 1 0.00Ef00 t j ,8 RATE FOR-PERIOD , t 1 i  ! 3. PERCENT OF TECHNICAL!  %  ! 0.00Et00 8 0.00Ef00 t I i SPECIFICATION LIMIT !  !  !  !

.=

Attachment 5 (continued - Page 2 of 2)

Gaseous Effluents GUARTER 1 1 START DATE 91010101 END DATE 91033124 OUARTER 2 ! START DATE 91040101 END DATE 91063024 DATE OF REPORTt DEC. 12e 1991 PREPARED BY!

CONTINUOUS MODE BATCH MODE f Cffff fUNkkbf bbkkkkk f bbkkkk f hbkkkkk f bhkkEk f

1. FISSION AND ACTIVATION OASES  ;

1 CI  ! 0.00Et00 1 1 3/E-03 1 -------- 1 -------- !

...-KR85h 2.14E-02 1 6.97E-02 1 -------- 1 -------- t

...............'...I

~

t KR87 t C I t KR88 i CI i 7.08E-03 ! 3.17E-02 1 -------- 1 -------- t .

_t . ....X E 13 3. . . _ _ .8 . . C.I...__..i. 3. 83.E.-01.1..1 .. . 22E100.. ..-........1.....-

1 ...- ....t 8.31E-01 1 5.3 i+00 t ----1 -------- t t XE135M t CI 1

.!. . X. .E 13 5. . .. . .t ._.....I

.. _ C I . ..__ .2.06Et00

.... 1 .......Et005.y3 ..... 1..- - .....__'_..---

_ ... ..-. .- ..t

! XE137 1 CI

......................... ...... ........_-01 1 -------- 1 -------- t I 2.59E-01 ! 2.59E . . ........................

t XE138 i CI 2.41E-01 1 4.37E-01 1 -------- 1 -------- t

! TOTAL FOR t i 1 1 1 1 PERIOD t CI 1 3.80EiOO 1 1.33E101 1 -------- 1 -------- 1

! (ABOVE) I  !  !  !  ! 1

2. 10 DINES t 1131  ! CI 1 6.74E-04 1 3.35E-03 1 -------- 1 -------- !

I 1133 8 CI i 1.82E-03 1 6.85E-03 1 -------- 1 -------- t 1 TOTAL FOR  !  ! 1 1 1 1 PERIOD  ! CI 1 2.49E-03 1 1.02E-02 1 -------- 1 --------  !

! (ABOVE) i i  !  !  !  !

3. PARTICULATES

! 4.77E-05 t 9.55E-05 l-

--- t t SR89  : CI

........__....................................__------ _- 1....... .. ...._---- __ ..__

i 1.06E-06 1 2.47E 08 ! -------- 1 -------- l 1 SR90 1 CI I

! 4.87E-05 i 9.56E-05 ! ----- -- tI ------- i.t 1 TOTAL FOR !  !  !  !

! PERIOD t CI 1 (ABOVE)  !  ! 1 l -- .. -- . - - . .- . - - - -- -

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