ML20235S192

Forwards Application for Mods to Facility NPDES Permit NC0024392.Mods Include re-permitting Collection Basin & Allowing low-level Radioactivity to Be Discharged Into Catawba River Below Cowans Ford Dam

ML20235S192
Person / Time
Site:	Mcguire, McGuire
Issue date:	09/29/1987
From:	Tucker H DUKE POWER CO.
To:	Everett G NORTH CAROLINA, STATE OF
Shared Package
ML20235S197	List: ML20235S192
References
NUDOCS 8710080362
Download: ML20235S192 (37)

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DUKE POWER COMPANY

- P.O. BOX 33189 CHARLOTTE. N.C. 28242 Teterwowe

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(704) 373-4331

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$estoweter, s Cooling water, and storm water runOf f. (2) The Sverage flow contributed by edch operat#On.f o r Add i t iona l De t a il s >

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_V. INTAKE AND EFPLUENT CHARACTERISTIC A, B, Si C: See instructions before proceeding - Complete one set of tables for each outf elt - Annotate the outf all number in the toece provi NOTE:

Tables V A, V4, and V C are included on separete sheets numbered V 1 througn V4.

D. Use the space below to list any of the polhitants hsted in Table 2c.3 of the instructions. which you i know eme<yticar detsor.n New you r rea discharged from any outf ati, For every pollutant you l.st, briefly devribe the reasons you bei eve it to be presen' and reoo

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VI. POTENTI AL DISCHARGES NOT COVE RE D BY AN AL YS f nalproduct or is any poliutant bsted initem V C e substance or a component of a substance wnich you currently use or menutecture as en intermed byproduct ?

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'CONTIAUE0 F ROM THE F RONT Do you have eny know6 edge or reason to behow that any biologiest test for ecute or chronse toxicity mes been receiving water en relation to your discherpe within the lest 3 years?

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QQ v so 16denents the trettsu and descenbe their purposes brinwt Fathead Minnow Flow-Through Acute Test Ceriodaphnia Survival and Reproduction Test Tests were for. informational purposes to determine whether the discharge showed any signs of toxicity. No acute toxicity to fathead minnows was demonstrated during the 96-hour test period. No effluent-related acute toxicity or chronic toxicity to Ceriodaphnia was demonstrated during the 7 day test period.

Were any of the analyses reported in item V performed by a Contract tabor 8 tory Or Consulting firm?

No Iso to Sectson IKI X v E % that the nomt. address. and telephone naam ber of. and pollu tan ts anah eed by, each sucts laboratory or farm beina s D NLWT A NAgyZEQ O E e A D O R E $b A NAME l i Item V; Part C I 1910 Cochran Road (412) 343-9200 '

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l NPDES Permit Modification #2 i Permission to Release Radioactivity to the Catawba River i

i

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q I'

Release of' Radioactivity to the Catawba River Normally the McGuire Nuclear Station turbine building sumps are discharged to the conventional wastewater treatment (WC) system for treatment ' with chemical addition and aeration.

The . treated wastes are discharged to the Catawba' River (discharge 002). Occasionally, the turbine building sumps L become contaminated with radioactivity by various. means including primary-to-secondary leaks and HVAC condensate drains. Sump. discharges may continue to be released to the WC system, may be routed to the normal Liquid Radwaste System discharge line for release to the condenser cooling water (CCW), or may be. routed to the Liquid Radwaste Collection- tanks for processing prior to release. The on of selected path of release depends the level radioactivity, volume of radioactive wastes, NRC Technical Specification's- processing requirements, potential for an oil spill, and the need to process chemical wastes.

permit -modification request includes adding the This Collection Basin (Wastewater Collection Basin, WWCB) as a permitted discharge point, one of the inputs to the WWCB is the unwatering of the CCW system for maintenance purposes.

During the unwatering process, a 54-inch isolation valve between the two units leaks. This leakage sometimes the allows unwatering processed' liquid radwaste to contaminate flow. The liquid radwaste has been processed to effluent limitations contained -in 10CFR Part 20 and diluted by the CCW flow; it is diluted farther by the unwatering flow and the WWCB.

All radioactive releases will be made in accordance with specifications. All effluent release technical released from the site will meet the radioactivity concentration and dose limitations specified in 10CFR Part 20, 10CFR Part 50, and McGuire Nuclear Station Operating License Technical Specifications. Attached is the NRC {

I approval for releasing radioactivity to the Catawba River. \

of this requested release path will not The addition increase the quantity of radioactivity released from the station. The dose due to radioactivity from this requested release path (combination of the discharge from the WC and WWCB) will be limited to 41% of the maximum permissible due concentration and will be added to the dose to radioactivity released from the present release path (discharge 004). As such there will be no change to the public. The  ;

health and safety of any memt>e r of the additional release path will provide more flexibility to the l 1

manner in which contaminated wastes can be treated and released. The requested release path will not result in an f increase in the discharge of any NPDES regulated pollutant.

_ _ _ - _ _ _- I

f p tAS #84 UNITED STATES

./. 9),

e NUCLEAR REGULATORY COMMISSION

! i W ASHINGTON. o. C. 20$55 E

June 5, 1987

'+,

...../

Docket Nos.: 50-369 and 50-370 Mr, H. B. Tucker, Vice President Nuclear Production Cepartment Duke Power Company 422 South Church Street .

Charlotte, Nortn Carolina 28242

Dear Mr. Tucker:

Subject:

!ssuance of Amendment No. 72 to Facility Operating License NPF-9 and hnendment No. 53 to Facility Operating License NPF McGuire Nuclear Station, Units 1 and 2 (TACS 61179/61180)

The Nuclear Regulatory Comission has issued the enclosed Amendment No. 72 Facility Operating License NPF-9 and A1nendment No. 53 These to Facility amend-Operating License NPF-17 for the McGuire Nuclear Station, Units 1 and 2.

ments censist of changes to the Technical Specifications in response toas sup your application dated March 19, 1986, 1

June 4, 1987 '

The amendments change Technical Specification Figure 5.1-4 to add another discharge point from the Conventional Wastewater Basin into the Catawba Riv The amendments are effective as of their date of issuance.

A copy of the related safety evaluation sucoorting Amendment No.72 to l Facility Operating License NPF-9 and Amendment No. 53 to Facility Operating License NPF-17 15 enclosed.

Notice of issuance of amendments will be included in the Comissi I Di-weekly Federal Register notice.

Sincerely, l 1

-- ,w

,N

s. -

j Carl Hood, Project Manager Project Directorate II-3 {

Division of Reactor Projects-I/I:

Enclosures:

1. Amendment No. 72 to NPF-9

2. Amendment No. 53 to NPF-17

3. Safety Evaluation See next oage cc w/ enclosures:

M Yhl) Gel 4J{. ,

[.

t Mr. H. B. Tucker McGuire Nuclear Station l

Duke Power Company 1

cc:

Mr. A.V. Carr, Esq. -Dr. John M. Barry Duke Power Company _ Department of Environmental Pealth P. 0. Box 33189 Fecklenburg County 422-South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 County Manager of Mecklenburg County 720 East Fourth Street Charlotte, North Carolina 28202 Chairman, North Carolina Utilities i Comission Mr. Robert Gill Dobbs Building Duke Power Company 430 North Salisbury Street Nuclear Production Department Raleigh, North Carolina 27602 P. O. Box 33189 Charlotte, North Carolina 28242 Mr. Dayne H. Brown, Chief Radiation Protection Branch J. Michael McGarry, III, Esq. Division of Facility Services Bishop, Libeman, Cook, Purcell Department of Human Resources and Reynolds 701 Barbour Drive 1200 Seventeenth Street, N.W. Raleigh, North Carolina 27603-2008 Washington, D. C. 20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Comission Poute 4, Box 529 Hunterville, North Carolina 28078 Regional Administrator, Region II U.S. Nuclear Regulatory Comission, 101 Marietta Street, N.W. , Suite 2900 Atlanta, Georgia 30323 L. L. Williams Area Manager, Mid-South Area ESSD Projects Westinghouse Electric Corporation MNC West Tower - Bay 239 P. O. Box 355 Pittsburgh, Pennsylvania 15230

e a

-I ff e

'o g

g, UNITED STATES NUCLEAR REGULATORY COMMISSION

• WASHINGTON. D. C. 20555 n, j s,,,. \

OUKE POWER COMPANY  ;

1 DOCKET NO. 50-369 McGUIRE NUCLEAR STATION, UNIT 1  ;

I AMEN 0 MENT TO FACILITY 0PERATING LICENSE Amendment No. 72 License No. NPF-9

1. The Nuclear Regulatory Comission (the Commission) has found that:

A. The application for amendment to the McGuire Nuclear Station, Unit 1 (the f acility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the licensee) dated March 19, 1986, as supplemented December 3, 1986 and June 4, 1987, complies with the l

standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Commission's rules and regulations as set forth in 10 CFR Chapter I; l B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations of the Commission; C.

There is reasonable assurance (i) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in ecmpliance with the Comission's regulations set forth in 10 CFR Chapter I;

0. The issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been satisfied, fQ4fL%~L% - 6y

2. Accordingly, the license is hereby amended by page changes to the Technical Specifications as indicated in the attachments to this license amendment, and Paragraph 2.C.(2) of Facility Operating License No. NPF-9 is hereby amended to read as follows:

(2) Technical' Specifications The Technical Specifications contained in Appendix A, as revised through Amendment No. 7a are hereby incorporated into the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMISSION C6 f/- ,

B. J. Youngbl od, Director Project Directorate II-3 Division of Reactor Projects-I/II

Attachment:

Technical Specification Changes

.Date of issuance: June 5, 1987 e

7._--__

p* *uouq UNITED STATES f jo,

- NUCLEAR REGULATORY COMMISSION

] ) w AsHINGTON, D. C. 20555 3 l

\ .... /

DUKE POWER COMPANY 00CXET NO. 50-370 McGUIRE NUCLEAR STATION, UNIT 2 AMEN 0 MENT TO FACILITY' OPERATING LICENSE _

Amendment No. 53 License No. NPF-17

1. The Nuclear Regulatory Comission (the Comission) has found that:

A. The application for amendment to the McGuire Nuclear Station, Unit 2 (the facility) Facility Operating License No. NPF-17 filed by the Duke Power Company (the licensee) dated March 19, 1986, as supplemented December 3,1986 and June 4,1987, complies with the standards amended (the Act and req)uirements of the Atomic Energy Act of 1954, as set forth in 10 CFR Chapter I; B. The facility will operate in conformity with the application, as amended, the provisions of the Act, and the rules and regulations  ;

of the Comission; C. There is reasonable assurance (1) that the activities authorized by this amendment can be conducted without endangering the health and safety of the public, and (ii) that such activities will be conducted in compliance with the Comission's regulations set forth in 10 CFR Chapter I; D. The issuance of this amendment will not be inimical to the common  !

defense and security or to the health and safety of the public; and E. The issuance of this amendment is in accordance with 10 CFR Part 51 of the Commission's regulations and all applicable requirements have been  ;

satisfied.

l I

i

)

l l

l

2. Accordingly, the license is hereby amended by page changes to the Technical ~

Specifications as indicated in the attachments to this license amendment, '

and Paragraph 2.C.(2) of Facility Operating License No. NPF-17 is hereby amended to read as follows:

(2) Technical Specifications _

The Technical Specifications contained in Appendix A, as revised through Amendment No. 53, are hereby. incorporated into the license.

The licensee shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

3. This license amendment is effective as of its date of issuance.

FOR THE NUCLEAR REGULATORY COMMISSION LM CC(

l / 4 oungbl d, Dire: tor E.he.

Pro c Directorate II-3 Division of Reactor Projects-I/II

Attachment:

Technical Specification Changes June 5, 1987 Date of Issuance:

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ATTACHMENT TO LICENSE AMENDMENT NO. 72 i

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FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND TO LICENSE AMENDMENT N0. 53 fi j

FACILITY OPERATING LICENSE NO. NPF-17_ .

DOCKET NO. 50-370 Feplace the following page of the Appendix "A" Technical Specifications with the enclosed page. The revised page is identified by Amendment number and contains vertical lines indicating the area of change.

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SITE BOUNCARY FOR L lQU t'D [FF LL'ENTS nu m McGt)lRE NUCLEAR STATION

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FIGURE 5.1-4 P.cGUIRE - UNITS 1 and 2 A=enhent No. 72 (Unit 1)

5-5 A=ensent so. 53 (Unic D l i l --_ _

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.[ g NUCLEAR REGULATORY COMMISSION

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 72 TO FACILITY OPERATING LICENSE NPF-9 AND AMENDMENT NO. 53 TO FACILITY OPERATING LICENSE NPF-17 DUKE POWER COMPANY C0CKET N05. 50-369 AND 50-370 McGUIRE NUCLEAR STATION, UNITS 1 AND 2

_ INTRODUCTION Existing Technical Specification (TS) 3.11.1.1 and its referenced Figure 5.1-4,

" Site Boundary for Liquid Effluents" define the authorized discharge point for radioactive material released in liquid effluents to unrestricted areas as being only to Lake Noman, an upstream impoundment of the Catawba River. By letter dated March 19, 1986, Duke Power Company (the licensee) requested a change to This proposed change would the TSs for McGuire Nuclear Station, Units 1 and 2.

modify Figure 5.1-4 to add a new release point for radioactive liquids and thereby permit the release of liquids containing trace quantities of radio-activity into the Catawba River, via the conventional waste water treatment system. The change would affect only the discharge location, and would i not t il increase existing TS limits regardin contained in the treatment pond, (2)g (1) the quantity of radioact ve to unrestricted areas, and would not decrease existing TS requirements regarding liquid discharge monitoring. The licensee provided additional information to support the request by letters dated December 3, 1986 and June 4, 1987.

The change would be accomplished by deleting from TS Figure 5.1-4 an existing, obsolete footnote which authorized a one-time discharge to the Catawba River on June 20, 1986, but retaining the existing arrow at the river and its label,

" Liquid Waste Discharge Point." (The existing arrow, label, and footnote were added in response to a separate application by the licensee submitted subsequent to the March 19, 1986 request.)

EVALUATION The McGuire plant is designed to release radioactive liquid effluents to Lake Norman and effluent controls are based on the concentrations of activity at The outflow from Lake Noman is into the the point of release to Lake Noman. Conventional ("non-radioactive") waste water is r Catawba River.

another discharge point directly to the Catawba River.

Water from the turbine building sump is normally released through the conven-tional wastewater treatment system. The quantity of radioactive material i contained in each treatment pond, and in each batch of slurry (used power l resins) to be transferred to the treatment ponds, is limited consistent with 10 CFR 20, Appendix B Table 11 by existing TS 3/4.11.1.5 and is not changed gg1MM$ 3 ff

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by these amendments. There are provisions for releasing turbine building sump water through the liquid radwaste system if the sump water is contaminated with radioactivity. The liquid radweste system is capable of processing 27,500 god, whereas the turbine building sumps can add up to 120,000 gpd during operation with primary to secondary leakage. Thus, the liquid radwaste system is not capable of handling the turbine sump discharge on a continuing j basis as would be required by the present technical specifications if there i were small steam generator tube leaks. Furthermore, when low levels of radioactivity are detected in a large pond (e.g., in one of the two 2.5 million gallon settling ponds of the conventional wastewater treatment system) {

release through the liquid radwaste system is impracticable. The licensee investigated several alternatives to the proposed additional release point and concluded that other possible solutions were unduly costly and were unwarranted I in view of the low levels of radioactivity and doses involved. Therefore the l

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licensee requested approval to release low level liquid radwaste through the conventional wastewater treatment system.

The TS change does not decrease the existing monitoring requirements (TS 3.3.3.8 and referenced TS Table 3.3-12) which assure that instantaneous radioactive I release rates remain within 10 CFR 20, Appendix 8 limits, and that radioactive l liquid effluent monitoring instrumentation remains operable or appropriate compensatory action taken. There are provisions for sampling and monitoring the water going into, and being released from, the conventional waste water system. The licensee has committed to make these measurements with the sensitivity necessary to assure that the concentrations are below the levels needed for compliance with the dose design objectives of 10 CFR 50 Appendix 1.

Specifically, the licensee committed to maintaining a lower limit of detection ,

of 0.1 pC1/L or less for Cs-137. These provisions satisfy General Design l Criterion 64 which require that a means be provided for monitoring effluent discharge paths. I The dose or dose commitment to a member of the public from radioactive ,l materials in liquid effluents released from each McGuire unit is limited j consistent with 10 CFR 50, Appendix I by existing TS 3/4.11.1.2 and is not changed by these amendments.

The licensee has comitted to ensuring that the use of this new release point does not increase the total permitted l

release from the station. To accomplish this, doses at both the new and i old release points will be added and the total will be maintained below the limits of Technical Specification 3.11.1.2. .

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The concentration of radioactive material released in liquid effluents l to unrestricted areas is limited consistent with 10 CFR 10, Appendix B, j Table II by existing TS 3/4.11.1.1 and is not changed by these amendments.

The change also, will not increase the concentration of radioactivity in the Catawba River. The radioactive material that is released to Lake l Norman reaches the Catawba River after some delay. Use of the new release point is a more direct release path for some of the material into the River. l j

This will lower concer.trations in Lake Norman without materially changing I the concentrations in the River. This is true because almost all of the )

activity released by the new pathway will be relatively long lived (i.e.

tritium and Cs-137) which cre not affected by the delay. Also in the low concentrations permitted by the technical specifications the short lived 1

materials are inconsequential.

1 The staff concludes that this proposed technical specification change is in accordance with release requirements of 10 CFR Part 50.36a, Part 50 Appendix I i and 10 CFR 20 Appendix B; and in accordance with 10 CFR Part 50 Appendix A, General Design Criterion 64 requirements for monitoring radioactivity releases. The change does not increase the liquid effluent release rates or the annual dose resulting from station liquid effluent releases. Thus, although the effluent release path is changed, neither the dose, quantity nor concentration of radioactive effluent in the River is changed. Therefore the proposed change is acceptable.

ENVIRONMENTAL CONSIDERATION These amendments involve changes to the installation or use of facility com-ponents located within the restricted area as defined in 10 CFR Part 20.

The staff has detemined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite and that there is no significant increase in individual or cumulative occupational exposure. The NRC staff has made a detennination that the amendments involve no significant hazards consideration, and there has been no public comment on such finding. Accordingly, the amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.

C0NCLUSION The Commission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Feoeral Register (51 FR 36088) on October 8, 1986. The licensee's subsequent submittals dated December 3, 1986, and June 4, 1987, do not alter the scope of the licensee's requested amendments as described in the October 8, 1986 Federal Register; nor do they affect the Comission's proposed no significant hazards considerationNo determination. The Commission consulted with the state of North Carolina.

public comments were received, and the state of North Carolina did not have any comments.

We have concluded, based on the considerations discussed above, that: (1) there is reasonable assurance that the health and safety of the public will not b endangered by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Comission's regulations, and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.

Principal Contributors: D. Hood, PO#II-3 C. Willis, PRPB Dated: June 5, 1987 l

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NPDES Permit Modification #3 Application for Clean Water Act Section 311 Exemption

Application for Clean Water Act Section 311 Exclusion In relation to oil and hazardous substance liability, the Clean Water Act Section 311 defines " discharge" as

" include (s) but is not limited to, any spilling, leaking, pumping, pouring, emitting, emptying or dumping but excludes

... (B) discharges resulting from circumstances identified and reviewed and made a part of the public record with respect to a permit issued or modified under section 402 of this Act, and subject to a condition in such permit ..."

[ 311 (a) ( 2) ] .

The implementing regulations promulgated by the Environmental Protection Agency specifies " (a ] discharge results 'from circumstances identified...and subject to a condition in such permit, ' whether or not the discharge is in compliance with the permit, where: (1) the permit application, the permit, or another portion of the public l record contains documents that specifically identify: (i)

The substance and the amount of the substance; and (ii) the origin and source of the substance; and (iii) The treatment which is to be provided for the discharge either by: . . . (B) A treatment system designed to treat the permittee's normai discharge and which is additionally capable of treating the identified amount of the identified substance. . .and (2) The permit contains a requirement that the substance and amounts of the substance...be treated...in the event of an on-site release; and (3) The treatment to be provided is in place."

(40CFR117.12 (c)].

Following is a description of the treatment provided by each of the McGuire Nuclear Station treatment systems and the substances on site that will be treated by that system in the event of an on-site release. Part of the substances are I

maintained and used at multiple locations and therefore may be released through more than one treatment system. The inventory data system lists the total quantity of the substance that is on site. Therefore, the total quantity of the substance on site is listed for each treatment system through which it can be discharged. In the event of a spill, the total quantity listed will probably not be released.

Discharge 001-Condenser Cooling Water (CCW, RC)

Condenser Cooling Water is drawn from Lake Norman. It is pumped through the condensers and component heataddition exchangers to and discharged back into Lake Norman. In removing heat, it provides natural neutralization- and dilution. Oil booms are placed across the discharge canal to prevent the discharge of oil. Maximum flow is 2.8 billion gallons per day. Attached are the chemical substances that can be discharged via the condenser cooling water.

MCGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH RC AMOUNT PRODUCT NAME (P/Ni A-184): 32.97 GAL ACETONE, ACS GRADE 12.00 GAL ARMSTRONG'S 520 ADHESIVE 45.00 GAL BRAHNi 87.69 GAL CLOVER LAPPING COMPOUND: 5.00 GAL CP-52 CHIL LAGi 2.00 GAL CP-82 CHIL-STIX F-R-Ni 4.25 GAL CRC 5-56 PENETRANT; (P/N 05004, CR8W P/N 556): 206000 GAL DIESEL FUEL OIL #2 7.79 GAL DYKEM STEEL BLUE; (P/N DX-100): 3.00 GAL FOSTER 85-20; SPARK-FAS ADHESIVE: 5.00 GAL GENERAL PURPOSE ADHESIVE "77"i 992.80 GAL l HYDRAZINE SOLUTION (54%): 220.00 GAL M & S STRIP-IT: (P/N 41500): 3.30 GAL f METAL POLISHING COMPOUND; 0.11 GAL MOLYKOTE G-RAPID SPRAY; (P/N 87504-24): 75.79 GAL MOLYKOTE PENE-LUBE SPRAY; (AEROSOL):

39.28 LBS MOLYKOTE 111: 5,63 GAL MS-450 PROTECTIVE VARNISH: 80.00 LBS NEVER-SEEZ PURE NICKEL SPECIAL NUCLEAR GRADE: 0.21 GAL PAINT, 1200 PRIME COAT, RED: 0.13 GAL PAINT, 1201 PRIMER: 2.00 GAL PLACCO RA-6602 (P/N 1368-001): 135,00 GAL RUGBEE SOIL RELEASE CONCENTRATE; 147.66 GAL TAP MAGIC CUTTING FLUID: 60069 GAL TERESSTIC 32: 995.75 GAL TERESSTIC 46: 21.00 GAL VARSOL C OIL SOLVENT VARSOL 1; (FISHER P/N S4574): 0.25 GAL 6500/6200 DRUM CLEANING SOLVENT; (P/N 43P63):

0.26 GAL 702 DIFFUSION PUMP FLUIDi 6.20 GAL 704 DIFFUSION PUMP FLUID (P/N 837-5):

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t Discharge 002.- Conventional Wastewater Treatment System (WC)

The Conventional Wastewater Treatment System treats waste L ' through a system. of basins - with chemical additions and

. aeration. Wastes' are initially directed to the initia'l holdup . pond where primary sedimentation occurs.

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200,000 gallon capacity basin has a retention' time of 12 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> and acts as a surge tank to prevent overloading and subsequent degradation of effluent quality throughout . the remainder of the system. This pond can be bypassed depending on influent quality. The initial holdup pond is

. followed by parallel settling ponds. These two 2.5 million gallon ponds provide 6-12 day retention. The ponds . are

- operated such that.one pond is in service while the other is on standby. Coagulent aids may be used for_ settling lighter solids along with pH adjustment to neutralize or precipitate various chemical compounds. The wastewater then flows to the final holdup pond where'it is aerated. This pond has_a volume of one million gallons and a retention time of 5  ;

days. The final holdup pond can be bypassed if the effluent l from the settling basins are within specifications. The final . ef fluent can flow by gravity or be pumped to the Catawba River with the pH - adjusted with an automatic CO addition system. An oil trap is prcvided to prevent oi$

spills to the receiving water. The holding capacity and recirculating capabilities. designed into the treatment facility assure a high quality effluent to the Catawba River. Attached are the chemical substances that can be discharged via the conventional wastewater treatment system.

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MCGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH WC' AMOUNT PRODUCT NAME (FISHER P/N A-38): 9.35 GAL ACETIC ACID, GLACIAL; 32.97' GAL:

ACETONE, ACS GRADES (P/N A-184): 10.00 BOX ALKALINE IODIDE-AZIDE REAGENT POWDER PILLOWSi 4.00 GAL ALL CLIMATE HIGH VACUUM PUMP OILi 16.11 LBS AMMONIUM CHLORIDE (P/N A-661): .

225.20 GAL AMMONIUM HYDROXIDES (FISHER P/N A-669): 12.00 GAL ARMSTRONG'S 520 ADHESIVE: 0.19 GAL BELZONA MOLECULAR RELEASE AGENT: 4.38 GAL BUFFER SOLUTION, PH 4.00; (P/N S0-B-99(CONC) & S0-B-101) 55.00 GAL CL-371. LOW TEMPERATURE RADWASTE ANTIFOAM: 87.69 GAL CLOVER LAPPING COMPOUND: 5.00 GAL CP-52 CHIL LAG: 2.00' GAL CP-82 CHIL-STIX F-R-Ni 4.25 GAL CRC 5-56 PENETRANT; (P/N 05004, CR&W P/N 556): 2250 LBS CS CORROSION INHIBITOR:- 206000 GAL DIESEL FUEL DIL 82: 0.32 GAL DIGESTION SOLUTION FOR COD, 0-150 PPB RANGE; (P/N 21258- 7.79 GAL

'DYKEM STEEL BLUE; (P/N DX-100): 487.00 LBS FEL-PRO N-5000 HUCLEAR GRADE: (PART NO. 51269) 110.00 GAL FENSO 71;. (P/N 390180 - 03746): 0.52 LBS FERRIC CHLORIDE; (FISHER P/N I-88): 217.00 GAL FIBRAX 370: 5.00 GAL FIRE-PREP 8256: 0.38 GAL FORMIC ACID; (P/N A-118): 3.00 GAL FOSTER 85-20; SPARK-FAS ADHESIVE 97.00 GAL GEAR DIL; GX 85W-140 5.00 GAL GENERAL PURPOSE ADHESIVE "77"i 9.38 GAL HERMES CEMENT; (P/N 999-125): 992.80 GAL HYDRAZINE SOLUTION (54%): 11.88 GAL HYDROCHLORIC ACID; (FISHER P/N A-144): 396.01 GAL KEROSENE; (P/N K10-1* FISHER): 345.00 GAL KUTWELL 40; CP/N 350040 - 03777): '

11780 LBS, LEAD / ACID STORAGE BATTERY, ANTIMONYi 0.68 GAL LOW LEVEL SODIUM REAGENT; (P/N 15111/181153)i 72.00 GAL LYSOL LIQUID DISINFECTANT 220.00 GAL M & S STRIP-IT: 24.80 GAL MARVEL MYSTERY OIL: 3.30 GAL METAL POLISHING COMPOUND; (P/N 41500): 5.98 GAL METHANOL; (FISHER P'N A-4124): 5.64 GAL METHYL ISOBUTYL KETONE; (P/N M-213): 5317.8 GAL MOBIL SHC 824: 48.63 GAL MOBIL 1 SW-30 OILi 0.73 GAL MOLECULAR N.F. CLEANER /DEGREASER: 0.11 GAL MOLYKOTE G-RAPID SPRAY; (P/N 87504-24): 75.79 GAL MOLYKOTE PENE-LUBE SPRAY; (AEROSOL): 39.28 LBS MOLYKOTE 111: 327.35 LBS MOLYKOTE 44 GREASE; (P/N'S 16390-23 a 16390-79): 332.00 GAL MOTOR OIL; 10W-40: 5.63 GAL MS-450 PROTECTIVE VARNISHi 110.00 GAL MULTI-PURPOSE CLEANER; (M & S P/N 4790): 302.10 GAL NE0 LUBE 82 DRY FILM CONDUCTIVE LUBRICANT: 80.00 LBS NEVER-SEEZ PURE NICKEL SPECIAL NUCLEAR GRADE: 100.00 PIL NITRAVER 6 NITRATE REAGENT; (P/N 14119): 11.05 GAL NITRIC ACID (BAKER P/N 4801); (FISHER P/N A200S, A200, A

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'MCGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH WC AMOUNT PRODUCT NAME NUTO H-32 LUBRICANT; (P/N 363010-01335) 70.00 GAL 627.00 GAL NUTG H-68s 0.21 GAL PAINT, 1200 PRIME COAT, P.E D : 0.13 GAL PAINT, 1201 PRIMER:

PHENYLARSINE OXIDE; (P/N 2205-16): 1.75 GAL 2.00 GAL PLACCO RA-6602 0.13 GAL PLATINUM COBALT COLOR STANDARD; (P/N S0-P-120):

POTASSIUM CHROMATE; (FISHER P/N P-220, P-220-3): 766.00 LES POTASSIUM HYDROXIDE; (P/N P-250): 19.14 LBS POTASSIUM PERMANGANATE; (P/N P-279): 16.60 LBS PROPIONIC ACID; (P/N A-258)s 0.13 GAL PRUSSIAN BLUE; (P/N 35): 39.60 LBS RANDG OIL HD 68; (P/N 01659): 15.00 GAL REAGENT SOLUTION W/ DIFFUSION; (P/N-15-17-11): 0.45 GAL RED GAGE OIL; (P/N A103): 0.53 44.00 GAL RIGID DARK CUTTING OIL: 135.00 GAL RUGBEE SOIL -RELEASE CONCENTRATE; (P/N 1368-001)i-855.00 LBS

.SANURIL 115 CHLORINE TABLETS: 9.00 GAL SAV0GRAN STRYPEE2E SEMI PASTE: 1.29 GAL SCOTCHKOTE ELECTRICAL COATING; (P/N 80-6100-3260-1):

SILVER NITRATE; . (P/N S-181): 2.10 GAL SODIUM BISULFATE; (P/N S-654/ FISHER): 15.20 LBS SODIUM ELECTRODE RINSE SOLUTION; (P/N 15-11-13x18-11-40) 0.13 GAL SODIUM FLUORIDE; (P/N S-299/ FISHER): 5.50 LBS SODIUM HYDROXIDE PELLETS; (P/N S-318): 14.80 LBS SODIUM HYDROXIDE 50% SOLUTION; (FISHER P/N S0-S-254): 6058.3 GAL SODIUM NITRITE; (P/N S-347/ FISHER): 2091.3 LBS SODIUM REFERENCE STANDARD SOLUTION; (P/N S0-S-139): 0.51 GAL SODIUM SULFHYDRATE; (P/N S-423): 2.53 LBS SPARTAN EP 460 OIL; CP/N 475375 - 05375): 401.85 GAL 785.00 GAL SPARTAN EP-150 OIL: 33.00 GAL SPARTAN EP-220 OIL: 74.00 GAL SPARTAN EP-680 OIL 40.00 GAL SPINESSTIC 22 LUBRICANT; (P/N 372038-01125): 10264 GAL SULFURIC ACID (93%); (FISHER P/N A-300): 237.00 LBS SURETT N-80K OIL; (P/N N-8K): 147.66 GAL TAP MAGIC CUTTING FLUID: 55.00 GAL TERESSTIC 100; (P/N 376045 - 01180): 1162.2 GAL TERESSTIC 150 275.25 GAL TERESSTIC 220: 60069 GAL TERESSTIC 32: 995.75 GAL TERESSTIC 46: 4038.3 GAL TERESSTIC 68: 5.60 GAL TOLUENE; (P/N T-324S/ FISHER): 1920 LBS TRISODIUM PHOSPHATE; (P/N S-377,S-376/ FISHER):

558.59 LBS UNIREX N2 LUBRICATING GREASE: 22.50 GAL VACUUM PUMP PRECISION OIL; (CAT t-69126): 21.00 GAL VARSOL C OIL SOLVENT VARSOL 1; (FISHER P/N S4574): 20.00 LBS W-INCONEL WELDING ROD 182: 5.00 LBS W-METCO 44 POWDER: 5.00 LBS W-METCO 447 POWDERi 5.00 LBS W-METCO 450 POWDER 5.00 LBS W-METCO 451 POWDER: 15.00 LBS W-1/8 SIL FLO WIRE:

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MCGUIRE NUCLEAR STATION l POSSIBLE DISCHARGES THROUGH WC AMOUNT PRODUCT NAME 15.00 LBS W-3/32 SIL FLO WIRE: 12.00 GAL XYLENE: 665.00 GAL ZERICE 46 OIL; (P/N 386040 - 02970): 0.25 GAL 6500/6200 DRUM CLEANING SOLVENT; (P/N 43P63):

0.26 GAL 702 DIFFUSION PUMP FLUID: 6.20 GAL 704 DIFFUSION PUMP FLUID; (P/N 837-5):

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- . Discharge.003 - Sanitary w?aste Treatment System (WT)

.The sanitary waste. treatment system is . a four (4)5. cell aerated lagoon system. It provides , ' approximate ly day

. retention and allows for variable level discharge. ~ Maximum volume (depth of 8 feet) is approximately- 321,300 gallons.

The first cell provides a two day retention and is kept in full' suspension by ' surface mechanical aerators. The second and third cells provide one day retention each and are kept partially suspended providing -for partial settling. The final cell is the settling cell and has a one day retention.

Flow from the final cell' is through a Sanuril chlorinator and a chlorine contact chamber. Discharge is into the Wastewater Collection Basin. Attached are- the ' chemical substances t h a t .' c a n' b e discharged' via the sanitary waste

. treatment system.

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'4 MCGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH WT AMOUNT PRODUCT NAME 45.00 GAL BRAWNi 2,00 GAL CLOROX LIQUID BLEACH: 4,25 GAL CRC 5-56 PENETRANT; (P/N 05004, CR8W P/N 556): 0,50 GAL KEPRO ETCHING SOLUTION; (KEPRO P/N E-1GT, E-lG, E-4G):

72.00 GAL LYSOL LIQUID DISINFECTANT: 327.35 LBS MOLYKOTE 44 GREASE; (P/N'S 16390-23 & 16390-79): 110.00 GAL MULTI-PURPOSE CLEANER; (M & S P/N 4790): 147.66 GAL TAP MAGIC CUTTING FLUID f

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Discharge 004 - Liquid Radwaste Treatment System (Radwaste, WL) 4 1

' The Liquid Radwaste Treatment system collects radioactively l 1

contaminated water from equipment drains, spills, or leaks auxiliary and reactor buildings. The system .

within the exchange l utilizes filters, evaporators, and ion '

demineralizers for the treatment process. Releases are made to assure compliance with 10CFR Part 20 and 10CFR Part 50.

Attached are substances that can be released via the Liquid Radwaste Treatment System.

4 MCGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH RADWASTE AMOUNT PRODUCT NAME ACETIC ACID, GLACIAL; (FISHER P/N A-38): 9.35 GAL ACETONE, ACS GRADES (P/Ni A-184): 32.97 GAL 10.00 BOX ALKALINE IODIDE-AZIDE REAGENT PONDER PILLOWSi 4.00 GAL '

ALL CLIMATE HIGH VACUUM PUMP OILi 1.10 LBS AMMONIUM ACETATE CRYSTALS; (P/N C-64):

AMMONIUM CHLORIDE; (P/N A-661): 16.11 LBS AMMONIUM HYDROXIDE; (FISHER P/N A-669): 225.20 GAL ARKALONE P; (LIQUID): 55.00 GAL BENZENE; (P/N B-414, B-245): 2.50 GAL BUFFER SOLUTION, PH 4.00; (P/N S0-B-99(CONC) & S0-B-101) 4.38 GAL 1.00 GAL CARBON TETRACHLORIDE: 211.75 LBS CAZAR 2 GREASE; 20000 LBS CEMENT C-320: 1.50 GAL CHROMERGE; (P/N C-577): 87.69 GAL CLOVER LAPPING COMPOUNDS 0.40 GAL COPPER REFERENCE STANDARD SOLUTION; (P/N 50-C-194):

COPPER SULFATE; (P/N C-493, C-495): 1.10 LBS CRC 5-56 PENETRANT; (P/N 05004, CR&W P/N 556): 4.25 GAL 1.00 GAL DAG; (P/N154): 8.00 LBS DESSICANT, INDICATING GEL; (P/N HDMI 103-6): 7.79 GAL DYKEM STEEL BLUE; (P/N DX-100): 487.00 LBS FEL-PRO N-5000 NUCLEAR GRADE; (PART NO. 51269): 0.52 LBS FERRIC CHLORIDE; (FISHER P/N I-88): 15.40 LBS FERRIC NITRATE; (P/N I-110): 1 10 LBS FERROUS AMMONIUM SULFATE; (P/N I-77): 2'.;.00 GAL FIBRAX 370: 14.00 GAL GEAR OIL: GX 85W-140i 9.38 GAL HERMES CEMENT; (P/N 999-125): 992.80 GAL HYDRAZINE SOLUTION (54%): 11.88 GAL HYDROCHLORIC ACID; (FISHER P/N A-144): 396.01 GAL KEROSENE; (P/N K10-luFISHER): 0.13 GAL LEAD REFERENCE STANDARD SOLUTION; (P/N S0-L-21): 11780 LBS LEAD / ACID STORAGE BATTERY, ANTIMONY: 72.00 GAL LYSOL LIQUID DISINFECTANT: 220.00 GAL M & S STRIP-ITi 24.80 GAL MARVEL MYSTERY OIL:

(P/N M-155): 0.25 LBS MERCURIC CHLORIDE; 19.20 LBS MERCURIC THIOCYANATE: (P/N M-197): 5.98 GAL METHANOL; (FISHER P/N A-4124): 5.64 GAL METHYL ISOBUTYL KETONE; (P/N M-213): 5317.8 GAL MOBIL SHC 824: 48.63 GAL MOBIL 1 5H-30 OILi (AEROSOL): 75.79 GAL

'MOLYKOTE PENE-LUBE SPRAY; 39.28 LBS MOLYKOTE 111 1.28 GAL MOLYKOTE 33 GREASE (P/N'S 14770-79 AND 14770-99): 327.35 LBS MOLYKOTE 44 GREASE; (P/N'S 16390-23 & 16390-79): 332.00 GAL MOTOR DIL; 10W-40: 302.10 GAL NEOLUBE 82 DRY FILM CONDUCTIVE LUBRICANT: 11.05 GAL NITRIC ACID (BAKER P/N 4801); (FISHER P/N A200S, A200, A 627.00 GAL NUTO H-68 8.10 GAL PETROLEUM ETHER; (P/N E139-4 E-139-5): 0.50 GAL PHOSPHORIC ACID; (P/N A-242): 0.18 GAL PLATINIZING SOLUTION: 19.14 LBS {

POTASSIUM HYDROXIDE; (P/N P-250): l

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MCGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH RADWASTE AMOUNT PRODUCT NAME POTASSIUM PERMANGANATE; -(P/N P-279): 16.60 LBS (P/N 35):

39.60 LBS PRUSSIAN BLUE: 44.00 GAL RIGID DARK CUTTING OIL: .

1.29 GAL SCOTCHKOTE ELECTRICAL COATING; (P/N 80-6100-3260-1): 2.10 GAL SILVER NITRATE; (P/N S-181): 0.50 LBS SILVER SULFATE; SODIUM BISULFATE; (P/N S-654/ FISHER): 15.20 LBS SODIUM FLUORIDE; (P/N S-299/ FISHER): 5.50 LBS SODIUM HYDROXIDE PELLETS; (P/N S-318): 14.80 LBS SODIUM HYDROXIDE 50% SOLUTION; (FISHER P/N S0-S-254): 6058.3 GAL ]

2091.3 LBS SODIUM NITRITE; (P/N S-347/ FISHER): .

0.51 GAL-SODIUM REFERENCE STANDARD SOLUTION; (P/N S0-S-139):

SPARTAN EP 460 OIL; (P/N 475375 - 05375): '401.85 GAL i 785.00 GAL SPARTAN EP-150 OIL: 33.00 GAL ,

SPARTAN EP-220 OIL: 74.00 GAL i' SPARTAN EP-680 OIL: 10264 GAL SULFURIC ACID (93%); (FISHER P/N A-300): 237.00 LBS SURETT N-80K OIL; (P/N N-8K): 322.00 GAL SYNESSTIC 32 OIL; (P/N 343101 - 03101): 147.64 GAL TAP MAGIC CUTTING FLUID: 55.00 GAL -

TERESSTIC 1003 (P/N 376045 - 01180): 1162.2 GAL TERESSTIC 150s 275.25 GAL

'TERESSTIC 220: 60069 GAL TERESSTIC 32: 995.75 GAL TERESSTIC 46: 4038.3 GAL  !

TERESSTIC 68: 5.60 GAL l TOLUEHE; (P/N T-324S/ FISHER): -558.59 LBS UNIREX NZ LUBRICATING. GREASE 0.25 LBS URANYL NITRATE; (P/N U-7): 22.50 GAL VACUUM PUMP PRECISION OIL; (CAT B-69126): 12.00 GAL XYLENE: .

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Discharge 005 - Wastewater Collection BasinBasin, (Collection WWCB)

The Wastewater Collection Basin is a 13.4 acre collection basin having a total capacity of approximately 40 million gallons; drawdown capacity is approximately 11 million The basin provides sedimentation, natural gallons.

neutralization and skimming. Flow from the basin ranges from 0 to 15,000 gpm. Holdup is minimal; if the Standby Nuclear Service Water Pond is being flushed, no holdup of the basin is possible. The overflow from the basin mixes with the discharge from the WC system in a concrete apron and is discharged to the Catawba River downstream of Cowans Ford Dam. Attached are the chemical substances that can be discharged via the Wastewater Collection Basin.

4 MCGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH WWCB AMOUNT PRODUCT NAME ACETIC ACID, GLACIAL; (FISHER P/N A-38): 9.35 GAL ACETONE, ACS GRADE; (P/Ni A-184): 32.97 GAL 10.00 BOX ALKALINE IODIDE-AZIDE REAGENT POWDER PILLOWS 4.00 GAL ALL CLIMATE HIGH VACUUM PUMP GILi 1.10 LBS AMMONIUM ACETATE CRYSTALS; (P/N C-64): 16.11 LBS AMMONIUM CHLORIDE; (P/N A-661): 225.20 GAL AMMONIUM HYDROXIDE; (FISHER P/N A-669): 2.50 GAL BENZENE; (P/N B-414, B-245)$

BUFFER SOLUTION, PH 4.00; (P/N S0-B-99(CONC) & S0-B-101) 4.38 GAL 1.00 GAL CARBON TETRACHLORIDE: 1.50 GAL CHROMERGE; (P/N C-577 ): 0.40 GAL COPPER REFERENCE STANDARD SOLUTION; (P/N S0-C-194):

COPPER SULFATE; (P/N C-493, C-495): 1.10 LBS 206000 GAL DIESEL FUEL OIL 82: 0.52 LBS FERRIC CHLORIDE; (FISHER P/N I-88): 15.40 LBS FERRIC NITRATE; (P/N I-110): 1.10 LBS FERROUS AMMONIUM SULFATE; (P/N I-77): 1100 GAL GASOLINE, UNLEADED: 992.80 GAL HYDRAZINE SOLUTION (54%): 11.88 GAL HYDROCHLORIC ACID; (FISHER P/N A-144): 396.01 GAL KEROSENE; (P/N K10-lNFISHER): 0.13 GAL LEAD REFERENCE STANDARD SOLUTION; (P/N S0-L-21): 0.25 LBS MERCURIC CHLORIDE; (P/N M-155): 19.20 LBS MERCURIC THIOCYANATE; (P/N M-197): 5.98 GAL METHANOL; (FISHER P/N A-4124): 5.64 GAL METHYL ISOBUTYL KETONE; (P/N M-213): 11.05 GAL NITRIC ACID (BAKER P/N 4801); (FISHER P/N A2005, A200. A 8.10 GAL PETROLEUM ETHER; (P/N E139-4, E-139-S): 0.50 GAL PHOSPHORIC ACIDS (P/N A-242): 0.18 GAL PLATINIZING SOLUTION: 19.14 LBS POTASSIUM HYDROXIDE; (P/N P-250): 16.60 LBS POTASSIUM PERMANGANATE; (P/N P-279): 2.10 GAL SILVER NITRATE; (P/M S-181): 0.50 LBS SILVER SULFATE; 15.20 LBS SODIUM BISULFATE; (P/N S-654/ FISHER): 5.50 LBS SODIUM FLUORIDE; (P/N S-299/ FISHER): 14.80 LBS SODIUM HYDROXIDE PELLETS; (P/N S-318): 6058.3 GAL SODIUM HYDROXIDE 50% SOLUTION: (FISHER P/N S0-S-254): 0.51 GAL SODIUM REFERENCE STANDARD SOLUTION; (P/N S0-S-139): 10264 GAL SJLFURIC ACID (93%); (FISHER P/N A-300): 1162.2 GAL TERESSTIC 150: 4038.3 GAL TERESSTIC 68: 5.60 GAL TOLUENE; (P/N T-324S/ FISHER): 0.25 LBS URANYL NITRATE; (P/N U-7): 22.50 GAL VACUUM PUMP PRECISION OIL; (CAT 8-69126): 12.00 GAL XYLENE:

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