ML19316A521

Forwards Data Re Radioactive Effluent Releases for Jul-Dec 1977

ML19316A521
Person / Time
Site:	Oconee
Issue date:	02/28/1978
From:	Parker W DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
NUDOCS 7912300060
Download: ML19316A521 (15)

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,, 5 l DUKE Powsn COMPANY Powra Bt. t.nixo 422 Socra Cat acu SrazzT. CnAnt.oriz. N. C. asa4a w.w a.....ca.., , February 28, 1978

%CE Pets 6CEnf TCLEP=ON E:ASCA 704 Srsam Pocouction 373-4083 Mr. J. P. O'Reilly, Director U. S. Nuclear Regulatory Co= mission Suite 1217 230 Peachtree Street, Northwest Atlanta, Georgia 30303 RE: Oconee Nuclear Station Docket Nos.50-269, -270, -287

Dear Mr. O'Reilly:

1 Pursuant to 10CFR 50.36a and Oconee Technical Specifications 6.6.1.2(c),  !

please find attached data concerning radioactive effluents released from Oconee Nuclear Station. This infonation is reported on a semi-annual ,

basis for the last six onths of 1977. l Very,truly yours,

'A u_. _ - d. ,

William O. Parker,Jr LIB:ge Attachment gec: Director of Inspection and Enforcement ~

s/j< , [pe' cA78

{,M' l 7912300C)60

.M RA$10 ACTIVE EFFLUENT REL._.aES LIQUlt AND AIRLORNE RELEASES Liquid and airborne releases are reported in attached tables.

SOLID 'JASTES Total volume of solid waste packated (cubic feet) 37,895.4 Total estimated activity involved (curies) 7,366.7

• Disposal of =a.tcrials shipped off-sitei" - - - -

I c DATE CU. FT. CURIES '

~

7-5 238 28.n 7-5 ' .

r' 599.2 -

~ 1.17 .

7-7 __

238 .561

'7-7 480 - .003

~

7-8 - - - ~

185 -

9.14 -

7-8 '

. 384.1 101.19 -

7-9 _

238 31.93 7-H 185 . 10.37 7-12 '

~

7.5 12.75 "

7-13 * ,

185 4.3 7-14 710.5 .82 '

7-15 7.4 -

1,70 7-18 185 n.27 7-18 185 .79 7-20 538.2 100.45 7 -20 '- '

~

238 24.26 7-21 238 8.83 .

~

7-22 238 7-22

_. . 2.59 _ ,

410.9 .65 7-23 .

100 2.30 , -- ._

7-25 100 1.47 7-26 100 1.83 7-26 -

238 .

25.48 __

7-27 - --

238 20.69

~

7-27 ' .

100 .20 7-27 238 n.24 7-28 402.3 .71 7-28 ' ,

238 .

24.38 7-29 238 2.30 7-28 ul.28 10.42 --

7-29 ,,

100 2.30 7-30 l

l n _. . y_ _ _ _ . .

DATE- -

~

Cth."E- CURIES

~

7-31 .-. 2- .238 - . 52.84 8-1 100 . 2 17

,8-1 - -

_-- 18'. -

. . -13.60 8-3 - -

'61,6.32 .73-8 _4, ,

100, 1 05-8-5 . 74 3.40 8-5 - -

100 1.45 8-7. ._.'100 _ ' . , 24 ..

8 .8 ,. .

. , , ,_., , 238.- ..- 23.47

~~ ' ' ~

'~

8-8 100..

__ . '...45 88 .

.85.6 15 58 .

8-8 . .2 - ~

316.7 --

46 8-9 738 *

-- . _- ".'*.54 --

8-10 .

-332.4 5.45 8-10 --

- 100 - - h- -

.- ... 1&- .

8-11 -

100

'~

' .65 8-12 -

238

~

87.62

~

8-12 '

100 .

.55 8-13 - 100 .

1.59 8-13 . .

1.-2 10.0. - - - - - .

8-14 . . - .- . 85 6 - 2441-4

- .100 8.-15 .. . . . _ . - - .1.95 8.15 185 2.24 8-16 238 820.76 '

0~17, ~- ,; _ , _ _ . ____ _3_g3 - ,2,33 .

8-17 7 8-18

.. 59. 2 . . .

. 54 .

185 - 5.82 8-19 40 408.8 8-20 .

- 110 3.58 g_gg . . . - - .

.g -

8-22 . . .

238

. 45.69

.. - .: ..a 8-22 - -

607 4- -

.46

.,-- -. ~ --

R ,

DATE-G. M. WRIES 2.62 8-23 100 8-24 ,

$5 ,2'.41 8-24 238 2.27 - -

8-25 .

no - 2.82 8-26 60' 280.5 8-26 .

.-316;7  ?'G4'

~

8-29 no . -

2.45 8-29 . 110 .. 1.1,6

~

8-31 110 ~~3.T ^ ,

~

- 376.6 8-31 -[ . 33- -

)

8-31 60 , 510. .

9-1 .

no .

2 I.30 9-1 - -

.. 7'. 5 100.

9-2 .

. no l' .2.3 #"

~

9-2 - -

238 - ' 1i'.65 ..

9-3 '185 4.76 9-5 no -

. ;. 9.3 .

9-5 238 -34.5 9-6 .

7.5 500_- . .' l 9-6 - 185 .

E n.99 9 -

. . . 479.36 ' I44 9-7

-~

no a .

~[.j9

. l 9-8 . -238 .-

42.09 I 9-9 . .

75. -

.43.07 9-9 * -

-77.04 __07 _

9-9 '. . .

.. 185

-1.89 9-10 ,

185 -J .1 71 9-11 ,

no, ~ 1.34.

9-11 -

185 -

. .1.21-

. = . . .- -

g - .

... e - , ,

DATE CU. FT. CURIES 9-13 185 1.18

.9-13 .. 1018.64 1.52 ,

9-13 77.04 14.96 9-15 110 3.30 9-15 50 425 9-18 135 3.37 -

9-18 185 '3.20 9-20 881.28 .53

.r 9-23 238 2.68 9-25 238 12.42 9-26 573.52 1.01 9-28 ~238 6.09 9-23 .

238 500

~

9-30 419.44 1.03

~

10-1 238 4.06 10-3 185 4.73 10-4 7.4 2.0 10-5 185 11.53

'10-5 - 308 .19 10-6 914.72 1.00 10-6 238 2.65

~10-7 -

185 .95 ..

10-9 238 8.65 10-9 - 185

~

1.4 10-10 185 1.5 10-11 l' 185 ,

2.32 l

'10-12 7.5 8.5 10-14 _ 684.8 2.50 1

10-14 . 110 5;;66

)

10-17 -

2. 110 1.98 e

l .-.- ._ _ - - _.

. _ 5_ ._

CU. FT. CURIES _ .

g no 1.71 ._

10-18 110 2.32 -

10-19 . ,

110 2.82 .

10-19

~

110 3.68 -

10-21 ,

659.12 1.33, _.

10-24 ~ "'

~

607.36 1.21 5-28 12.24

/ 238 10-31 -

256 , ,, , , ,

.12 -

11-2 .

a .

no 1.56 11-7 130 2.43 11-8

. 445.12 .37 .-

n-8 ~

205 4.52 11-9 ,

238 4.73 -

11-12 238 9.98 11-15 .

667.68 .94 11-16 '

7.5 1.00 11-18 238 2.33 11-19 205 1.3 11-25 .

~

975.84 .78 11-28 ...

' 238 10.41 11-30 ,.

320 .08 12-1 2.38 238 12-2 .-

.' 23.8 .80 .

12-4 7.5 .85 12-5 ..

'. ;i . 238 4.08 12-6 .

.' 185 18.44 12-10

~

804.64 .28 -

12-13 .

185 .163 12-15 . ..

205 2'.'29 12-20 - .

G a.

e

- ~ ~ '

_~g .

~

~

DATE

- O* U* _ CURIES 12-30 '

205 12-31 3.18 452.62 12-22 .

2.44 205 2.99 12-22 75" 12-27 24.45 102.72 15.84 -

12-27 205 -

3.26' 12-29 428 .69 12-30 '

205 3.87

• Dispositf au: All shipments to Chem-Nuclear Systems Waste Disposal Facility at Barnwell, South Carolina 0

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3 PDCENT OF TEcel! CAL 5pgcIptcA;!:N5

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• Washington, D. C. 20555 r y Re: Oconee Nuclear Station C h9 p Docket Nos. 50-269, -270, -287 fy g,qg,g#

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Dear Mr. Rusche:

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The Oconee Nuclear Station Technical Specification 3.9.3 concerning ra  :

active liquid effluent releases states that releases from the station shall l be controlled such that the instantaneous concentrations of radioactivity in liquid waste released from the Restricted Area do not exceed the values listed in 10CFR20, Appendix B, Table II, Column 2. Specification 3.9.7 further states that an effluent control monitor shall be set to alarm and automatically close the waste discharge valve such that the above requirements are met.

In our letter dated July 30, 1976, we informed you of the difficulty we were l experiencing with high background readings which prevented the setting of l the monitor as required by Specification 3.9.7. Prior to and since that time, considerable efforts have been expended in the solution of this problem. l An off-line radiation monitor has been temporarily installed in order to more l effectively decontaminate the monitor. Equipment and procedures have been provided which will allow flushing of the radiation monitors between releases to reduce the buildup of radioactivity on interior surfaces. Experimentation with various piping materials, coatings and surface finishes have also been conducted to obtain minimum background on the liquid effluent monitor. These actions have been successful in significantly reducing the average background seen by the detector and have resulted in the ability of the monitor to detect station releases.

However, efforts to correlate the liquid effluent monitor readings with a laboratory sample have been unsuccessful. The primary reason for this is considered to be the changing spectrum of radionuclides from release to release. Although it may be possible to calibrate the monitor to a specific predominate isotope, if one exists, it is believed impossible to calibrate a single monitor to the wide spectrum of radionuclides present in liquid waste effluents at the low levels of activity necessary to assure compliance with 10CFR20, Appendix B, Table II, Column 2 on an instantanenus basis as required by Technical Specification 3.9.7. The monitor is capable of detecting and alarming on gross changes in activity and can provide indication of an unex-pected condition.

11664-

.Mr. Benard C. Rusche Prg3 2 Novemb r 18, 1976 It is considered that our present Technical Specifications concerning liquid waste effluents are impractical to meet literally on a continuous basis. The provisions of 10CFR20, 520.106 permit the release of liquid radioactivity to an unrestricted area in concentrations which do not exceed 10CFR20, Appendix B, Table II, Column 2 amounts. These concentrations are permitted to be averaged over periods not exceeding one year. The provisions of 10CFR50, Appendix A, General Design Criterion 60, require that the design of the nuclear power unit shall include the means to control suitably the release of radio-active materials in liquid effluents ...... produced during normal reactor operation. The design and operation of the Oconee Nuclear Station provides for the control of liquid radioactive effluents primarily by releasing only in a batch manner from tanks which have been isolated and sampled to assure the acceptability of the release. This method of sampling prior to release assures that the limits of 10CFR20 are met. The liquid effluent monitor is provided as a tackup to detect gross changes which might occur from an unex-pected release. The regulations do not require a monitor capable of alarming and automatically closing a waste discharge valve as required by the Technical Specifications.

For the above reasons, pursuant to 10CFR50, 550.90, revisions to the Oconee Nuclear Station Technical Specification 3.9, " Release of Radioactive Waste,"

are requested as indicated on the attached replacement page. These changes revise the maximum concentration of radioactivity in liquid waste to 35 times the concentrations specified in 10CFR20, Appendix B, Table II, Column 2 when averaged over the period of a batch release. This value is acceptable in that it assures compliance with 10CFR20.105 for permissible levels of radiation in the unrestricted area. The requirements for calibration of the liquid )

effluent monitor have been revised to require annual calibration by means of a known solid source; monthly checks with a known solid source; and daily instrument checks. The provisions for comparison with liquid effluent releases have been deleted.

The liquid effluent monitor is required to be operable during liquid effluent releases. However, in order to assure that the provisions of 10CFR20 are met, redundant valve lineup checks of the effluent pathway and redundant sample analyses will be performed prior to each liquid effluent release. Additionally, effluent releases will be permitted only from isolated tanks.

Your prompt attention to this matter is requested.

Very ruly yours, l' l r

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William O. Parker. Jr' MST:ge "

Attachment cc: Mr. Norman C. Moseley

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Mr. Benard C. Rurche P2g2 3 November 18; 1976 WILLIAM 0. PARKER, JR., being duly sworn, states that he is Vice President of Duke Power Company; that he is authorized on the part of said Company to sign and file with the Nuclear Regulatory Commission this request for amendment of the Oconee Nuclear Station Technical Specifications, Appendix A to Facility Operating Licenses DPR-38, -47 and DPR-55; and that all statements and matters set forth therein are true and correct to the best of his knowledge.

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William O. Parker, Jr., W ee President ATTEST:

' M [. r / hv.

ohn C. Goodman, Jr.

Assistant Secretary (Seal)

Subscribed and sworn to before me this 18th day of November, 1976.

ff*ks l Notary Public Gvmot./

(Notarial Seal)

My Commission Expires:

u' d </, 1977

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