ML20235N812
| ML20235N812 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 02/21/1989 |
| From: | Tucker H DUKE POWER CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NUDOCS 8903010418 | |
| Download: ML20235N812 (71) | |
Text
_ _ _ _ _. _ _ _ _ _ _ _ _ _ _ _ _ _ _,
4 Duxu POWER GOMPANY c
I P.O. Box 33180 CHARLOTTE, N.O. 28242 IIALILTUCKER Tztxeniown vms reensnaar (704) 373-4531 MUOLKAE PRODUCTION February-21, 1989 i
.U.S. Nuclear. Regulatory Commission 1
Document Control Desk Washington, D.C.
20555
Subject:
McGuire Nuclear Station Docket Nos. 50-369, -370 Clarification of Liquid Waste Effluent Monitoring Requirement Submittal Of Additional Information Gentlemen:
By letter dated June 5,1987, the NRC issued Amendments No. 72 and No. 53 to the i
McGuire Facility Operating Licenses.
The amendments consisted of changes to i
Tech Specs requested by our letters dated March 19, 1986 as supplemented December.3, 1986 and June 4, 1987.
The change added another discharge point from the Conventional Wastewater Basin into the Catawba River.
The Tech Spec change did not decrease the existing monitoring requirements (TS 3.3.3.8 and referenced TS Table 3.3-12) which assures instantaneous radioactive release rates remain within 10CFR 20, Appendix B Limits, and ' that radioactive effluent monitoring-I instrumentation remains operable or appropriate compensatory action be taken.
At that time Duke also committed to maintaining a lower limit of detection (LLD) of 0.1 pCi/L or less for Cs-137.
By letter dated May 10, 1988 we submitted a description of the methods of imple-menting the dose design objectives of 10CFR Part 50, Appendix I as provided by Duke.
It was also concluded that the LLD value at the discharge point should be determined based on the annual continuous release bases, and that we could take credit for dilution factors made available prior to the release point outfall.
On February 17, 1989, during a tele-conference between members of our Radiation i
i Protection and Regulatory Compliance staff, with Mr. Stan Kirslis of your staff, questions concerning the handling of contaminated water in our Turbine Building Sump resulting from a Steam Generator tube leak was discussed.
At that time we stated that we would provide Mr. Kirslis with additional information concerning i
our use of portable demineralized equipment as a supplement to our radwaste f
processing systems.
Also included is information concerning other restrictions and requirements affecting our control of conventional waste water based on federal and state environmental regulatory requirements.
Should you have any questions concerning this matter, please contact S.E. LeRoy of at (704) 373-6233.
Very truly yours,
$K.
86f Hal B. Tucker SEL/395/sel 8903010418 890221 P
/ /
PDR ADOCK 05000369 lr P
PNu
.5 Attachment w
Document Control Desk February 21, 1989 Page 2 xc: W/ Attachment Mr. M.L. Ernst Acting Regional Administrator, Region II l
U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, GA 30323 Mr. Darl Hood, Project Manager U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. -20555 Mr. P.K. Van Doorn NRC Senior Resident Inspector McGuire Nuclear Station Mr. Stan Kirslis, Project Manager U.S. Nuclear Regulatory Commission l
C/0 Mr. Jim Crolley Region II, U.S. Nuclear Regulatory Commission 101 Marietta St., NW, Suite 2900 Atlanta, GA 30323 l
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L.____.______
February 21, 1989 v
ATTACHMENT Document Control Desk WC Release Point Additional Info.
Duke Power' Company Duxe Powsa COMPANY McGuire Nuclear Station P.O. BOX 33189 WILLIAM A. HALLER
/
MANAcen a
NUCLEAM TECHNICAL SERYlCES
(
3
<70m a n asoo j
)
September 19, 1988 V
k Mr. Charles Wakild, Chief h(
Water Quality Section Division of Environmental Management Department of Natural Resources and
{
j Comunity Development f
r P.O. Box 27687 Raleigh, N.C.
27611
['
(Y ATTENTION:
Mr. Dale Overcash
SUBJECT:
McGuire Nuclear Station
{
NPDES Permit Modification 3 @VI) y(g 3
Uw
\\
File: MC-702.13 INFORMATION
Dear Sir:
l On September 27, 1987 we' requested that the McGuire, Nuclear Station NPDES
. permit (NC0024392) be modified.
The requested modifications included (1) re-permitting the Collection
- Basin, (2) allowing very low-level radioactivity to be discharged into the Catawba River below Cowans Ford Dam, and-(3) appl.ying for a Clean Water Act Section 311 exemption.
On April 1, 1988 we amended the modification request by (1) withdrawing part 2 of the request and (2) requesting that our instream administrative limit for hydrazine be incorporated into Part III of the NPDES permit.
After recent discussions with your staff, we request to postpone the Section 311 exemption. We will discuss the Section 311 exemption with your staff later.
However, we would appreciate action on the request to re-permit the Collection Basin and to incorporate the instream administrative limit into the permit.
Once developed, we would appreciate the opportunity to discuss the draft permit with _ you prior to it going to public notice.
Should you have any questions or desire additional information, please contact R.T.
Simril,-
(f704) 373-2310) or M.C. Griggs [(704) 373-7080).
Sincerely,
(
I W.A. Haller, Manager Nuclear Environmental Compliance MTG/57/rhm xc: Document Control Desk I
i b
E.
201 YOJ R T' F0RYAT ON DUKE POWER GOMPm NUGLEAR PRODUGTION DEPARTMENT P.O. Box 33189. 499 SOUTH CNURCH STREET CHARLOrrTE. N.C. 98949 (704) 373-4011 April 1, 1988
~
Mr. Charles Wakild, Chief Water Quality Section Division of Environmental Management Department of Natural Resources and Comunity Development-P. O. Box 27687 Raleigh, N. C.
27611 Attention:
Mr. Dale Overcash
Subject:
McGuire Nuclear. Station NPDES Permit Modification File: MC-702.13 l
Dear Sir:
On September 29, 1987 we. requested that the McGuire Nuclear Station NPDES permit
-(NC0024392) be modified. The requested modifications included (1) re permitting the Collection Basin, (2) allowing very low-level radioactivity to be discharged into the Catawba River below Cowans Ford Dam, and (3) applying for a Clean Water Act Section 311 exemption. On November 17, 1987 we met with your personnel to discuss our request. As a result of our discussion we desire to amend our modification request.
With this letter, we withdraw part 2 of our modification request. Another in-depth review of the regulations and additional discussions with our legal staff indicated that radioactive waste releases regulated by the Nuclear Regulatory Commission are not subject to state regulation under the water program, Northern State Power Co. V. Minnesota, 447 F. 2d 1143 (1971), aff'd. 405 U.S. 1035, 92 S.
Ct. 1307, 31 L. Ed. 2d 576 (1972).
In view of this regulatory interpretation and the distinction between NRC and EPA / state authority, we withdraw the request for your approval to allow very low-level radioactivity to be discharged into the Catawba River below Cowans Ford Dam.
Additionally, in 1983 an instream administrative limitation was approved by the Department of Natural Resources and Community Development for.hydrazine. The limitation was 0.06 mg/1. We desire to incorporate this currently approved administrative limit into the NPDES permit. The limitation applies instream to Lake Norman and the Catawba River below Cowans Ford Dam, depending on the release pathway.
Since 1983, the regulatory climate has changed and there are overlapping regulatory requirements.
It is for this reason that we request the hydrazine administrative limitation be formally incorporated into Part III of the NPDES permit.
Procedures are in place to assure compliance with the above mentioned limit. We will subnit the procedures to you for your review should you desire.
s Mr. Charles Wakild, Chief April 1, 1988 Page Two Once conpleted, we would appreciate the opportunity to discuss the draft permit with you prior to it going to public notice.
Should you have any questions or desire additional information, please contact R. T. Simril [(704)373-2310] or M.
C. Griggs ((704)373-7080).
Sincerely, g.1 W.,A. Haller, Manager Nuclear Technical Services WTG/1518/sbn xc:
D. H. Brown, Department of Human Resources Document Control Desk U. S. Nuclear Regulatory Commission Washington, D. C.
20555 l
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20R YOUR 1:0RMrl0N DmCE POWER COMPA.NY P.O. BOX 30189 CHAALOTTE. N.C. 28242 MAL B. T1*CKER te La rnoirie
,l,'"l",
l504: J73 4Sai September 29, 1987 Dr. George T.
Everett, Chief Water Quality Section Division of Environmental Management Department of Natural Resources and Community Development P.O. Box 27687 Raleigh, N.C.
27611
SUBJECT:
McGuire Nuclear Station NPDES Permit Modifica tion File:
MC-702.13
Dear Sir:
On several occasions we have discussed various discharges i
from our McGuire Nuclear Station with your staff.
As a result, we have decided to request that the McGuire NPDES permit (NC0024392) be modified.
I The modifications include (1) re-permitting the Collection Basin and (2) allowing very low-level radioactivity to be discharged into the Catawba River below Cowans Ford Dam, and (3) applying for a Clean Water Act Section 311 exemption.
Attached is the information substantiating the request.
Re-periaitting the Collection Basin will alleviate th e necescity of case-by-case approvals for condenser cooling o
water system unwatering.
Permitting very low-level l
radioactive'cy to be discharged into the Catawba River will i
result in no increase in the quantity or dose of radioactivity released from the station; therefore the health and safety of the public will not be impacted.
Enclosed please find a check (No. 311792) for $100.00 for the permit processing.
Also enclosed is a sketch of the statien showing all discharge locations.
We would appreciate the opportunity to discuss the specifies of our request with you while you are developing the modification.
Should you have any questions or desire 1
[.
-._______________________9
l NPDES Permit Modification $1 Application for Re-Permitting Collection Basin I
i l
I i
d I
a
4 Supplemental Information
System Description
Collection Basin (Wa stewater Collection Basin, WWCB)
I f
The Collection Basin (Wastewater Collection Basin, WWCB) is a 13.4 acre collection basin having a total capacity of R
a pproxirtately 40 million gallons; drawdown capacity is approximately 11 million gallons.
Flow from the basin ranges from 0 to 15,000 gpm.
If the Standby Nuclear Service Water Pond is being flushed, no holdup of the WWCB is i
possibles otherwise, holdup is minima 1.
j i
Inputs into the basin include overflow from the Standby l
Nuclear Service Water Pond. (SNSWP), treated sanitary waste
- effluent, yard
- drains, a
lab sink and floor
- drains, miscellaneous Administrative Building drains, and condenser cooling water system unwatering.'
)
The SNSWP is a 34.9 acre pond designed to provide water for the safe shutdown of the station in the unlikely event that Cowans Ford Dam is lost.
The level in the pond is maintained, per requirements of the McGuire Nuclear Station Operating License Technical Specifications, by pumping water from Lake Norman into the pond.
The pond will receive runoff from a drainage area of 171 acres.
The sanitary waste treatment system is a four (4) cell aerated lagoon system.
It provides approximate ly 5 days retention and allowc for variable level discharge.
The effluent flows through chlorinators, a
chlorine contact chamber, and a Parshall fiume before discharging into the WWCB.
The sanitary waste treatment system is regulated as discharge 003.
The lab sink and floor drains discharge approximately three liters of chemical waste per month.
Flow from these drains go to a groundwater sump then to the SNSWP then to the WWCB.
The Administrative Building drains incittde an HVAC sump, i
ficor drains, hot water boiler and chilled water system discharge.
Flow is to a yard drain which flows to the WWCB.
Ths Condenser Cooling Water (CCW) System for each of the two (2) units has a volume of approximately 2 tntllion gallons er.ch.
Whenever a unit is scheduled down for refueling, and for condenser tube periodically during other shutdowns,
- leaks, the system must be unwatered for purposes of maintenance.
Unwatering must continue while maintenance is performed because of leakage by the valves in the approximately ll-foot diameter CCW piping.
Che maximum
unwatering rate is approximately 2000 gpm; the water is essentially lake water.
Treated liquid radioactive waste effluent (discharge 004) discharges into a crossover line
(
between the CCW system of the two units.
During unwatering, l
trace amounts of radioactivity can potentially be released into the water from the unwatering process because of leakage by a 54-inch isolation valve.
All yard drains discharge to the WWCB. The WWCB provides sedimentation, natural neutralization, and skimming.
The overflow from the WWCB mixes with the discharge from the Conventional Wastewater Treatment (WC) system (discharge 002) in a concrete apron and is discharged to the Catawba River downstream of Cowans Ford Dam.
9 l
4 NPDES Permit Modification #2 Permission to Release Radioactivity to the Catawba River i
l 1
I l
O l
l Release of Radioactivity to the catawba River Normally the McGuire Nuclear Station turbine building sumps L
are discharged to the conventional wastewater treatment (WC) system for treatment with chemical addition and aeration, i
The treated wastes are discharged to the Catawba River (discharge 002).
Occasionally, the turbine building sumps 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 selected path of release depends on the level of radioactivity, volume of radioactive wastes, NRC Technical Specification's processing requirements, potential for an oil spill, and the need to process chemical wastes.
This permit modification request includes adding the 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 allows processed liquid radwaste to contaminate the unwatering 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 effluent release technical specifications.
All radioactivity released from the site will meet the concentration and dose limitations specified in 10CFR Part 20, 10CFR Part 50, and McGuire Nuclear Station Operating License Technical Specifications.
Attached is the NRC approval for releasing radioactivity to the Catawba River.
The addition of this requested release path will not 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 concentration and will be added to the dose due to radioactivity released from the present release path (discharge 004).
As such there will be no change to the and safety of any member of the public.
The health additional release path will provide more flexibility to the manner in which contaminated wastet can be treated and released.
The requested release path will not result in an increase in the discharge of any NPDES regulated pollutant.
j
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NPDES Permit Modification #3 Application for Clean Water Act Section 311 Exemption l
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___________-__________a
A 2
1 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 l 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 record contains documents that specifically identify:
(1)
The substance and the amount of the substance; and (ii) the origin and source of the substance; and (iii) The treatment l
which is to be provided for the discharge either by:... (B) A treatment system designed to treat the permittee's normal 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."
(40CFRil7.12 (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 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 heat exchangers and discharged back into Lake Norman.
In addition to 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 l
billion gallons per day.
Attached are the chemical l
substances that can be discharged via the condenser cooling I
water.
McGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH RC AMOUNT PRODUCT NAME 32.97 GAL ACETONE, ACS GRADE; (P/N: A-184):
12.00 GAL ARMSTRONG'S 520 ADHESIVE:
45.00 GAL BRAWNi 87.69 GAL CLOVER LAPPING COMPOUND:
5.00 GAL CP-52 CHIL LAGi 2.00 GAL CP-82 CHIL-STIX F-R-N CRC 5-56 PENETRANT; (P/N 05004, CR8H P/N 556):
4.25 GAL 206000 GAL DIESEL FUEL OIL 82:
7.79 GAL DYKEM STEEL BLUE; (P/N DX-100):
FOSTER 85-20; SPARK-FAS ADHESIVE:
3.00 GAL 5.00 GAL GENERAL PURPOSE ADHESIVE "77" 992.80 GAL HYORAZINE SOLUTION (54%):
220.00 GAL M & S STRIP-IT*
3.30 GAL METAL POLISHING COMPOUND; (P/N 41500):
MOLYKOTE G-RAPID SPRAY; (P/N 87504-24):
0.11 GAL MOLYKOTE PENE-LUBE SPRAY; (AEROSOL):
75.79 GAL 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, REDi 0.13 GAL PAINT, 1201 PRIMER:
2.00 GAL PLACCO RA-6602:
RUGBEE SOIL RELEASE CONCENTRATE; (P/N 1368-001):
135.00 GAL 147.66 GAL TAP MAGIC CUTTING FLUID:
60069 GAL TERESSTIC 32:
995.75 GAL TERESSTIC 46:
VARSOL C OIL SOLVENT VARSOL 1; (FISHER P/N S4574):
21.00 GAL 6500/6200 DRUM CLEANING SOLVENT; (P/N 43P63):
0.25 GAL 0.26 GAL 702 DIFFUSION PUMP FLUIDi 6.20 GAL 704 DIFFUSION PUMP FLUID; (P/N 837-5):
l
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Discharge 002 - Conventional wastewater Treatment System (WC)-
l 1
The Conventional Wastewater Treatment System treats waste through a system of basins with chemical additions and aeration.
Wastes are initially directed to the initia l holdup pond where primary sedimentation occurs.
This 4
200,000 gallon capacity basin has a retention time of 12 to i
1 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 l
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 from the settling basins are within specifications.
The final effluent can flow by gravity or be pumped to the Catawba River with the pH adjusted with an automatic CO oi$
addition system.
An oil trap is previded to prevent spills to the receiving water.
The holding capacity and i
recirculating capabilities designed into the treatment l
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.
1
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MCGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH WC AMOUNT PRODUCT NAME 9.35 GAL ACETIC ACID GLACIAL; (FISHER P/N A-38):
32.97 GAL ACETONE, ACS GRADE; (P/N A-184):
10.00 BOX I
ALKALINE IODIDE-AZIDE REAGENT POWDER PILLOW $i 4.00 GAL ALL CLIMATE HIGH VACUUM PUMP OIL:
16.11 LBS AMMONIUM CHLORIDE; (P/N A-661):
AMMONIUM HYDROXIDE; (FISHER P/N A-669):
225.20 GAL 12.00 GAL ARMSTRONG'S 520 ADMESIVE 0 19 GAL BELZONA MOLECULAR RELEASE AGENT:
BUFFER SOLUTION, PH 4.00; (P/N S0-B-99(CONC) & S0-B-101) 4.38 GAL 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 OIL 822 DIGESTION SOLUTION FOR COD. 0-150 PPB RANGE; (P/N 21258 0.32 GAL
'.79 GAL DYKEM STEEL BLUE; (P/N DX-100):
487.00 LBS FEL-PRO H-5000 NUCLEAR GRADE; (PART NO. 51269):
FENSO 71; (P/N 390180 - 03746):
110.00 GAL 0.52 LBS FERRIC CHLORIDES (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 FOST ER 85-20; SPARK-FAS ADHESIVE:
97.00 GAL GEAR OIL; GX 85W-140:
5.00 GAL GENERAL PURPOSE ADHESIVE "77":
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):
345.00 GAL KUTWELL 40; (P/N 350040 - 03777):
11780 LBS LEAD / ACID STORAGE BATTERY, ANTIMONY:
LCW LEVEL SODIUM REAGENT; (P/N 15111/181153):
0.68 GAL 72,00 GAL LYSOL LIQUID DISINFECTANT:
220.00 GAL M & S STRIP-ITr 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):
0.73 GAL MOLECULAR N.F. CLEANER /DEGREASER:
0.11 GAL MOLYKOTE G-RAPID SPRAY; (P/N 87504-24):
7 5.79 GAL MOLYKOTE PENE-LUBE SPRAY; (AEROSOL):
39.28 LBS MOLYKOTE 111:
327.35 LBS MOLYKOTE 44 GREASE; (P/N'S 16390-23 & 16390-79):
5.63 GAL MS-450 PROTECTIVE VARNISHi 110.00 GAL MULTI-PURPOSE CLEANER; (M & S P/N 4790):
302.10 GAL NEOLUBE 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):
NITRIC ACID (BAKER P/N 4801); (FISHER P/N A2005, A200, A 11.05 GAL
4 l
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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 NUTO H-68:
RED:
0.21 GAL PAINT, 1200 PRIME CDAT, 0.13'OAL PAINT, 1201 PRIMER:
1.75 GAL PHENYLARSINE OXIDES (P/N 2205-16):
2.00 GAL-PLACCO RA-66028 PLATINUM COBALT COLOR STANDARD; (P/N S0-P-120):
0.13 GAL POTASSIUM CHROMATE: (FISHER P/N P-220, P-220-3):
766.00 LBS POTASSIUM HYDROXIDE; (P/N P-250):
19.14 LBS POTASSIUM PERMANGANATE; (P/N P-279):
16,60 LBS 0.13 GAL PROPIONIC ACID; (P/N A-258):
39.60 LBS PRUSSIAN BLUE; (P/N 35):
15.00 GAL RANDO OIL HD 68; (P/N 01659):
0.45 GAL REAGENT SOLUTION W/ DIFFUSION; (P/N 15-17-11):
0.53 RED GAGE OIL; (P/N A103):
44.00 GAL RIGID DARK CUTTING OIL RUGBEE SOIL RELEASE CONCENTRATE:
(P/N 1368-001):
135.00 GAL 855.00 LBS SANURIL 115 CHLORINE TABLETS:
9.00 GAL SAV0GRAN STRYPEEZE SEMI PASTE:
SCOTCHKOTE ELECTRICAL COATING; (P/N 80-6100-3260-1):
1.29 GAL 2.10 GAL SILVER NITRATE; (P/N S-181):
15.20 LBS SODIUM BISULFATE; (P/N S-654/ FISHER):
SODIUM ELECTRODE RINSE SOLUTION: (P/N 15-11-13M18-11-40) 0.13 GAL 5.50 LBS SODIUM FLUORIDE; (P/N S-299/ FISHER):
14.80 LDS SODIUM HYDROXIDE PELLETS; (P/N S-318):
SODIUM HYDROXIDE 50% SOLUTION: (FISHER P/N S0-5-254):
6058.3 GAL 2091.3 LBS SODIUM NITRITE; (P/N 3-347/ FISHER):
SODIUM REFERENCE STANDARD SOLUTION; (P/N S0-S-139):
0.51 GAL 2.53 LBS SODIUM SULFHYDRATE; -(P/N 5-423):
401.85 GAL SPARTAN EP 460 OIL; (P/N 475375 - 05375):
785.00 GAL SPARTAN EP-150 OIL:
40.00 GAL SPINESSTIC 22 LUBRICANT 4 (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 150i 275.25 GAL TERESSTIC 220:
60069 GAL TERESSTIC 32:
995.7 5 GAL TERESSTIC 46:
4038.3 GAL TERESSTIC 68:
5.60 GAL TOLUENE; (P/M T-3245/ FISHER):
TRISODIUM PHOSPHATE (P/N S-377,5-376/ FISHER):
1920 LBS 558.59 LBS UNIREX N2 LUBRICATING GREASEi 22.50 GAL VACUUM PUMP PRECISION OIL: (CAT 8-69126),
VARSOL C OIL SOLVENT VARSOL 1; (FISHER P/N S4574):
21.00 GAL 20.00 LBS W-INCONEL WELDING ROD 182:
5.00 LBS W-METCO 44. PONDER:
5.00 LBS W-METCO 447 POWDER:
5.00 LBS W-METCO 450 POWDER 5.00 LBS i
W-METCO 451 POWDER:
15.00 LBS W-1/8 SIL FLO WIRE:
MCGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH WC AMOUNT-PRODUCT NAMg 15.00 LBS W-3/32 SIL FLO WIRE:
. 665.00 GAL 12.00 GAL XYLENE:
ZERICE 46 OILJ (P/N 386040 - 02970):
6500/6200 DRUM CLEANING SOLVENT; (P/N 43P63):
0.25 GAL 0.26 GAL 702 DIFFUSION PUMP FLUID:
6.20 GAL 7 04 DIFFUSION PUMP ' FLUID; (P/N 837-5):
l 1
Cischarge 003 - Sanitary waste Treatment System (WT)
The sanitary waste treatment system is a inur (4) cell aerated lagoon system.
It provides approximately 5 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 i
substances that can be discharged via the sanitary waste treatment system.
I l
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1 i
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MCGUIRE NUCLEAR STATION POSSIBLE DISCHARGES THROUGH WT AMOUNT PRODUCT NAME 45.00 GAL BRAWN 2.00 GAL CLOROX LIQUID BLEACH:
CRC 5-56 PENETRANTJ (P/N 05004, Craw P/N 556):
4.25 GAL KEPRO ETCHING SOLUTIONS (KEPRO P/N E-1GT, E-1G, E-4G):
0.50 GAL 72.00 GAL LYSQL LIQUID DISINFECTANT:
MOLYKOTE 44 GREASE; (P/N'S 16390-23 & 16390-79):
327.35 LSS MULTI-PURPOSE CLEANER; (M & S P/N 4790):
110.00 GAL 147.66 GAL TAP MAGIC CUTTING FLUID:
i I
i
l -.
Discharge 004 - Liquid Radwaste Treatment System (Radwaste, WL)
The Liquid Radwaste Treatment system collects radioactively contaminated water from equipment drains, spills, or leaks within the auxiliary and reactor ' buildings.
The system utilizes
. filters, evaporators, and ion exchange domineralizers 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 32,97 GAL (P/Ni A-184):
ACETONE, ACS GRADE; ALKALINE IODIDE-AZIDE REAGENT POWDER PILLOW 52 10.00 BOX 4.00 QAL ALL CLIMATE NIGN VACUUM PUMP OILi 1.10 LBS AMMONIUM ACETATE CRYSTALS; (P/N C-64):
16.11 L55 AMMONIUM CHLORIDE; (P/M A-661):
AMMONIUM HYDRQXIDE; (FISHER P/N A-669):
225.20 GAL 55.00 GAL ARKALONE P; (LIQUID >t 2.50 GAL 82NZENE; (P/N 3-414, 8-245):
BUFFER SOLUTION, PH 4.00; (P/N S0-8 44(CONC) $ 50-8-101) 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 COMPOUND' COPPER REFERENCE STANDARD $0lVTION; (P/N 50-C-194):
0.40 GAL 1.10 L85 COPPER SULFATE; (P/M C-493, C-495):
4.25 GAL CRC 5-56 PENETRANT; (P/N 05004, CR&W P/N 556):
1.00 GAL DAG; (P/N154):
8.00 LES 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 1-88):
15.40 L53 FERRIC NITRATE; (P/N I-110):
1.10 LBS FERROUS AMMONIUM SULFATE; (P/N I-77):
217.00 GAL FIBRAX 370 97.00 GAL GEAR OIL; GX 85W-140:
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 K10-1NFISHER):
LEAD REFERENCE STANDARD SOLUTION; (P/N 50-L-21):
0.13 GAL 11780 LBS LEAD / ACID STORAGE B ATTERY, ANTIMONY:
72.00 GAL LYSQL LIQUID DISINFECTANT 220.00 GAL M & 5 STRIP-IT 24.80 GAL MARVEL MYSTERY DIL:
0.25 L55 MERCURIC CHLORIDE; (P/N M-155):
19.20 LBS MERCURIC TH10 CYANATE:
(P/N M-197):
5.98 GAL METHANOL; (FISHER P/M A-4124):
5.64 GAL METHYL ISOBUTYL KETONE; (P/N M-213):
68.63 GAL MOSIL 1 $W-30 OIL:
75.79 GAL MOLYKOTE PENE-LUBE SPRAY; (AEROSOL):
39.28 LBS M01YKOTE 111:
1.28 GAL MOLYKOTE 33 GREASE (P/N'S 14770-79 AND 14770-99):
327.35 LBS MOLYKOTE 44 GREASE; (P/N'S 16390-23 & 16390-79):
332.00 GAL MOTOR GIL; 10W-40s 302.10 GAL NEO..'.E 92 DRY FILM CONDUCTIVE LUBRICANT :(FISHER P/N A2005, A200, A 11.05 GAL NI kic ACID (8AKER P/N 4801);
627.00 GAL NUT: H-64:
8.10 GAL PEls'OLEUM ETHER; (P/N E139-4, E-139-5):
0.50 GAL PMO$PHORIC ACIDS (P/N A-242):
0.18 GAL PLATINIZING SOLUTION:
19.14 LS5 i
POTASSIUM HYDROXIDE; (P/N P-250):
I I
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1 MCGUIRE NUCLEAR STATION f
POSSIBLE DISCHARGES THROUGN RADWASTE AMOUNT PRODUCT NAME 16.60 L85 l
POTASSIUM PERMANGANATE:
(P/N P-279):
39.60 L85 PRUSSIAN BLUEJ (P/N 35) 44.00 GAL RIGID DARK CUTTING OILi (P/M 80-6100-3260-1):
1,29 OAL 4
SCOTCNKOTE ELECTRICAL COATINGJ 2.10 GAL SILVER NITRATES (P/N 5-181):
0.50 L85 SILVER SULPATEJ 15.20 L85 SODIUM SISULFATE: (P/N 5-654/ FISHER):
SODIUM FLUORIDE; (P/N 5-299/ FISHER):
5.50 LBS SODIUM NYDROXIDE PELLET $i (P/N 3-318):
14.80 LBS SODIUM MYDR0XIDE Sox SOLUTION (FISHER P/N S0-5-254):
6058.3 GAL SODIUM NITRITE; (P/N 5-347/ FISHER):
2091.3 LBS SODIUM REFERENCE STANDARD SOLUTION; (P/N S0-5-1391:
0.51 GAL SPARTAN EP 460 0!La (P/N 475375 - 05375):
401.85 GAL 785.00 GAL SPARTAN EP-150 OIL:
10264 GAL SULFURIC ACID (95%); (FISNER P/M A-300):
237.00 LBS SURETT N-80K OIL; (P/N N-8K):
SYNESSTIC 32 QIL (P/N 343101 - 03101):
322.00 GAL 147.66 GAL TAP MAGIC CUTTING FLUID:
55.00 GAL TERESSTIC 1003 (P/N 376045 - 01180):
1162.2 GAL TERESSTIC 150 27 5.25 GAL TERESSTIC 220 60069 GAL TERESSTIC 32:
995.75 GAL TERESSTIC 46:
4038.3 GAL TERESSTIC 68:
5.60 GAL TOLUENE; (P/N T-3245/ FISHER):
558.59 L85 UNIREX N2 LUBRICATING GREASE:
0.25 L85 URANYL NITRATE; (P/N 0-7):
22.50 GAL VACUUM PUMP PRECISION OILJ (CAT 8-69126):
12.00 GAL XYLENEi 1
l i
i
4 Discharge 005 - Wastewater Collection Basin (Collection Basin, 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 gallons.
The basin provides sedimentation, natural 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 4
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.
l l
l l
I i
MCOUIRE NUCLEAR STATION POSSIBLE DISCHARGE 5 THROUGH WWCB AMOUNT PRODUCT NAME ACETIC ACID, GLACIALs (FISHER P/N A-38):
9.35 GAL (P/Ns A-184).
32.97 GAL ACETONE, ACS GRADES ALKALINE ICDIDE-AZIDE REAGENT PONDER PILLOW 5:
10.00 BOX 4.00 GAL ALL CLIMATE HIGH VACUUM PUMP OIL:
1.10 LB5 AMMONIUM ACETATE CRYSTAL 5s (P/N C-64):
AMMONIUM CHLORIDES (P/N A-661):
16.11 L85 AMMONIUM HYDROXIDES (FISHER P/N A-669):
225.20 GAL BENZENES (P/M B-414, B-245):
2,s0 GAL BUFFER SOLUTION, PH 4.00s (P/N S0-B-99(CONC) 4 50-B-101) 4.38 GAL 1.00 GAL CARBON TETRACHLORIDE:
1.50 GAL CHROMERGEs (P/N C-577):
COPPER REFERENCE.5TANDARD SOLUTION; (P/N 50-C-194):
0.40 GAL COPPER'5ULFATE; (P/N C-493, C-495):
1.10 L55 206000 GAL DIESEL FUEL OIL 025 0.52 LB5 FERRIC CHLORIDES (FISHER P/N 1-88):
15.40 L85 FERRIC NITRATES (P/N I-110):
1.10 L85 FERRQUS AMMONIUM SULFATES (P/N I-77):
1100 GAL GASOLINE, UNLEADED:
99C,80 GAL HYDRAZINE SOLUTION (54%):
11.48 GAL HYDROCHLORIC ACIDS (FISHER P/N A-144):
396.01 GAL' KEROSENES (P/N K10-inFIsi1ER):
LEAD REFERENCE STANDARD SOLUTION (P/N,50-L-21):
0.13 GAL 0.25 L85 MERCURIC CHLORIDES (P/N M-155):
MERCURIC' THIOCYANATE:
(P/N M-197):
19.20 L55 5.98 GAL METHAN0La (FISHER P/N A-4124):
5.64 GAL METHYL ISOBUTYL KETONES (P/N M-213):
NITRIC ACID (BAKER P/N 4401); (FISHER P/N A2005, A200, A 11.05 GAL PETROLEUM ETHER: (P/N E139-4. E-139-5):
8.10 GAL 0.50 GAL PH0SPHORIC ACIDS (P/N A-242):
O 18 GAL PLATINIZING SOLUTION:
19.14 LB5 POTASSIUM HYDROXIDES (P/N P-250):
16.60 LB5 POTASSIUM PERMANGANATE. (P/N P-279):
2.10 GAL SILVER NITRATE; (P/N 3-181):
0.50 LB5 SILVER SULFATE 15.20 LS5 SODIUM BISULFATE (P/N 5-654/ FISHER):
5.50 L85 SODIUM FLUORIDE; (P/N $-299/ FISHER):
14.80 L85 SODIUM HYDROXIDE-PELLET $s (P/N 5-318):
SODIUM HYDROXIDE 50% SOLUTION: (FISHER P/N $0-5-254):
6058.3 GAL SODIUM REFERENCE STANDARD SOLUTION; (P/N 50-5-139):
0.51 GAL 10264 GAL SULFURIC ACID (93%); (FISHER P/N A*300):
1162.2 GAL TERESSTIC 150s 4038.3 GAL TERESSTIC'68:
5.60 GAL TOLUENE (P/N T-3245/ FISHER):
0.25 LB5 URANYL NITRATE:
(P/N U-7):
22.50 GAL VACUUM PUMP PRECISION OILS (CAT 8-69126):
12.00 GAL XYLENE:
l
1 l
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l Plot Plan l
McGuire Nuclear Station NPDES Discharge Locations I
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INFORMAT ON l
DuxE POWER GOMPANY P.O. DOx 33189 CHARLOTTE, M.o. 98949 HAL B. TUCKER
,,t,,,,,,
[ [",
(704) 373-4801 M
i December 28, 1988 Mr. R. Paul Wilms, Director Division of Environmental Management h
Department of Natural Resources and g
f I,
Connunity Development V
P. O. Box 27687 Raleigh, NC 27611
Subject:
McGuire Nuclear Station
/
Renewal of NPDES Permit NC0024392 File: MC-702.13
Dear Mr. Wilms:
The subject NPDES permit expires August 31, 1989. Federal regulation 40 CFR 122.21 and North Carolina regulation 15 NCAC 2H.0106(b) as well as Part II.B.10 of the subject permit require submittal of an application for renewal at least 180 days prior to expiration.
Please find enclosed triplicate copies of the application for renewal of the subject permit and a check (no. 158304) for $200.00 for the permit processing fee. We request notification that the application is complete.
Should you have any questions or desire additional information, please contact R. T. Simril [(704) 373-2310).
Sincerely, 1
/
,fl I
al B. Tu ker, Nice President Nuclear Production Department t
WTG/75/rhm Enclosures
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n Y~s W a ConsolidatedPermitsProgram s.71 Y-upons For each outfall. list the latitude miel longitude of its nocetion to the neerest 15 seconds and the name of the roosiving vuoter.
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001 35 25 59 80 56 55 Lake Norman 002 35 25 59 80 56 55 Catawba River 003 35 25 59 80 56 55 Catawba River via Discharge 005 004 35 25 59 80 56 55 Lake Norman via Discharge 001 005 35 25 59 80 56 55 Catawba River 35 25 59 80 56 55 Catawba River A. Attach a line drowing showing the water flow through tw focality. Indiesta sourtse of intake water, operations contributing westoweter to the effluent.
and trestrnent units lebe6ed to correspond to the more detailed description in 11em B. Construct a water betones on the linn drewteg by showing everspi flows between intakes, operations, trestrnent units. and outteils if a meter belence eennot be determined (e4, for corner,r mining areWeir% provide e pictorial cleocription of the nature and amount of any sources of water and any collectiori or treatment rnesoures.
B. For each outfall. provide e descripuon of: H) All operations contributing westoweter to the effluent, kialud6ng proomes _ ____ __. eenitary wenewetero t N up eye nN d or A a
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Condenser Cooling Water 2487.02 MGD Discharge to surface water 4-A 001 Low Pressure Service v 3r 9.36 MGC Discharge to surface water 4-A Nuclear Service Water 28.80 MGD Discharge to surface water 4-A Liquid Radwaste (See Diser arge D04)
Conventional Wastewater Treat-0.41 MGD Sedimentation 1-0 002 ment (WC) System which receives Skimming X-X input from the following:
Precipitation 2-C turbine building sumps, Co-Precipitation X-X water treatment room sump, Neutralization 2-K condensate demineralized Chemical Oxidation 2-B backwash, lab drains, steam Mixing 1-D generator blowdown, wet lay-up Flocculation / Coagulation 1-G 2-D solutions, floor wash, metals Diccharge to surface water 4-A cleaning waste.
Sewage Treatment System 0.040 MGD Screening 1-T 003 (Monitoring only; discharges Aerated lagoon 3-B through Discharge 005)
Chlorination 2-F Liquid Radwaste Treatment 0.012 MGD Filtration, Mixing 1-0 1-0 004 System Demineralization, Oxidation 2-J 2-B Coagulation / Flocculation 2-D 1-G Discharge to surface water 4-A or eici Ai. wea oauy verfi.,ne ruuwam,..,5.e.wreness,
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FORM U.S. eMVtRONMENT AL PROToCTeoM AG efeCV
- APPLICATION FOR PERMIT TO OBSCHARGE WASTEWATER.. >
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' : v EXISTING MANUFACTURING, ConWERCIAL, MINING AND SILVICULTURAdOPERATIONS
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A. Attach a line drawing showing the water flow through the facihty. Indicate sources of intake water, operstions sentrituuting westoweter to the effluent, and treatment unite laboied to correspond to the more detailed descriptions in item 5. Construct a water tietence on the line drowing tpy showing everage flows between intakes, operations, treatment units, and outfalls. If a water belance connot tue determined ly, fler seres /st minder scefr/eles), provide e pictoriel description of the nature and amount of any sources of water and any collection of treatment measures.
- 8. For each outte41, prtnnde e description of: (1) All operothone wantributing westowster to the effluent, induding prosses westoweter, sanitary westoweter, cooling water, and storm water runoff; (2) The overage flow,tmtributed try each operation; and (3) The treatment received try the westoweter Continue on additionel shoots if necessary, t. S u T.
- a. ope R ATsoN(s) CoMTRiouTING Flow
- 3. TREATMENT
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- e. OseC RIPTION Wastewater Collections 2.40 MGD Sedimentation 1-U 005 Basin (WWCB)
Natural Neutralization 2-C Skimming X-X Discharge to surface water 4-A Cowans Ford Dam Underdrain
<0.03 MGD Discharga to surface water 4-A System I
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- 3. FREQU ENCY
- a. Flow I. ouTF ALL,
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.in d.>s, 002 Chemical metal cleaning Frequency and duration cannot be predicted from past, waste as necessary. Various Need based on the therreal-hydraulic performance, plant systems cleaned / flushed j
using any of the following:
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i EDTA, hydrazine, citric acid, i
phosphoric acid, oxalic acid, trisodium phosphate, soda ash.
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'(See description of chemical l
- cleaning.)
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- 002,
, Closed Cooling Systems drain, The sygtems may be drajned ind vidually for non-routin 004 ing. Contains nitrite, borax mainteriance. Maximum it dividual system volume is 30,00 benzotriazole corrosion gallond.
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A Oces da e4.ent gv.ce ne..r-tat.on promwigatea oy EP A wac" Sec' n 30a af tne Cean Water Act apply to your facehtyP y v ts.. ump s tc item til B-
- No Ito to Section IVI B. Are tne hmitations in the apohcable effluent guidthne expressed in terms of production (or otherinessiers of operstrond 14 Es complete item til Cp f No 190 to Sectson IV)
C If you answered "yes" toltem til 8. hst the cuantity which represents an actualmeasurement of your levelof production, empressed in the terms and units used in tne apphcable effluent guidehne. and indicate the affected outf alls
,,,,1. AVERAGE DAILY PRODUCTION oufrALLS c. o*e s aveo=. e ne ou sv. -.es sia6. s ee,
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A Arn,h ion reagireg o, any Federai. State or tocas author ty to meet any moiementation schedule for the construction upgrading or operat on of waste water tre atment equipme6t or practices or any otner envernarmentai prograrns wnicn may effect the discnarges cescribed in Inis appocat.on) To s ac' ces out 5 not i.mited to, permit conditions, administrative or enforcement orcers, enforcement comphance schedule letters, stipulations. cowrt orders. amo pant or soan cond t,ons.
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Ind cate w et9er eacn program is now underway or plannec and.nd cate voor act.ai ar e
r_os/r distnarpest g ou 90w "a_ve underway or whicn yoa plaa
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NC0024392 e,,,e,,,,,,,,,, p 3,,,
CONTINUED FROM PACE 2 A, 8, & C.
See instructions tafore proconding - Compiete one set of tectes for seCh outfall - Annotate the outfall number en the space provided.
NOTE; Tables V A, V4, and V4 ore included on seperste sneets numtwred V.1 through V4.
D. Use the space below to list any of the collutants hated in Tobie 2c 3 of tne instructions, wnien you know or have reeson to beheve is discharged or may me discharged from any outfall. For every poilutant you list, briefly describe the reasons you beisew it to be present end report any enelytical date in you r 1
possemon.
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asovact i acLLurant a sounct i
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le any pollutant listed in item V C e subetence or a component of a tubetence whaCh you Curtently use or manuf acture se en intermedeste or fined product or tryproduct?
O s se (Int att such pottutents belows
$ >eo Ito to It** VI 3)
N/A i
CONTINUED FROM THE ORoNT
' ' Do you have any knowedge or reason to tielieve that any biotocicol teet for acute or eronic toescary hee tisen made on any of your oisenerges or on a receMng m en reteten to your discharge withen the last 3 years?
Q v se tidenhts the testino end deeernbe theor puroc,ees belows C no (so to sectson Vitti Fathead minnow acute 96-hour flow-through test.
Ceriodaphnia 7-day chronic survival and reproduction test.
The purpose of both tests was for in-house knowledge of whether the discharges were toxic. The results of the tests indicate that there is no toxicity in the discharges.
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Were any of the snelysse ruoorted in item V performed by a contract lacoratory or coneutting ferm?
G vEs flJet the nons, addnren. and telephone number of, and polJetener C No 100 to seetton ZX1 esslysed by, each suen laboratory or frrm below) l S.Acontes l
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l Enwright Laboratories, Inc.
P.O. Box 5287 (803) 373-0707 Part V-C parameters Greenville, SC 29607 and analysis of samples on Discharg 004 (Radwaste).
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l Icertoty unelerpeneky of sew that shis document onef eH attachments were propered uneler my droetsers or esonerweien in eeterdence wuth a system desogned to secure that quehhedpereennelareportygather andevekoete the ordermotoon submotted Gesed on my knesnry of the person erpersons who menege the syttem or these pereene M reopenenNe forgathenrig the utermetsoot the snformetoon as6mntreds to the best ofmy knowieqe eruf behet. true, accurate. and complete I em ewere ther there are spehcent penekses for submortmg telee mformetsers inclu6ng the penehdty of hne ennt eterisonment for knowong vuoletions.
- a. m Aus a orricia6 tat 6s (type or arinto e rwoms no sewe roar a no -
H. B. Tucker, Vice President Nuclear Production Department (704) 373-4531
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l NPDES Supplemental Information for McGuire Nuclear Station December 22, lo88 i
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1
TABLE OF CONTENTS Page STATION INTAKE 3
Surface Intake 3
Subsurface Intake 3
l NUCLEAR SERVICE WATER 4
I Containment Spray Heat Exchangers 4
CONVENTIONAL T4W PRESSURE SERVICE WATER 5
FIRE PROTECTION SYSTEM S
OUTFALL 001 6
Condenser Cooling Water 6
OUTFALL 002 7
Water Treatment Room Sump 8
Filtered Water System 8
Drinking Water System 9
Demineralized Water System 9
Turbine Building Sump 9
Diesel Generator Room Sumps 10 Lab Drains 10 Floor Wash 10 condensate Polisher Backwash 10 Condensate Polisher Element Cleaning 11 Wet Lay-up 11 Auxiliary Electric Boiler Blowdown 12 Groundwater Drainage System 12 CCW System Unwatering 12 Standby Shutdown Facility / Closed Cooling Systems 12 Steam Generator Cleaning 13 Miscellaneous System / Component Cleaning 13 OUTFALL 003 15 OUTFALL 004 15 Floor, Equipment, and Laundry Drains 16 Ventilation Unit Drains 17 Chemical Volume and Control System 17 OUTFALL 005 17 Standby Nuclear Service Water Pond 18 Sanitary Waste Treatment System 18 Lab and Floor Drains 18 Administrative Building Drains 18 CCW System Unwatering 18 Yard Drains 19 COWANS FORD DAM UNDERDRAIN SYSTEM 19 APPENDIX: Boror 9;a ind Control 20 2
O The McGuire Nuclear Station is a two (2) unit nuclear fission steam electric generating station. It is owned and operated by Duke power Company. Each unit is a four loop pressurized water reactor. Reactor fuel is zircaloy clad sintered uranium oxide pellets. Reactor heat absorbed by the Reactor Coolant System produces steam in four (4) steam generators sufficient to drive a turbine generator unit with a design net electrical rating of 1180 megawatts.
The nuclear reaction is controlled by control rods and chemical neutron absorption. Boric acid is used as a chemical neutron absorber and to provide borated water for safety injection. During reactor operation, changes are made in the reactor coolant boron concentration. Appended is a description of how boron concentration changes are implemented.
A schematic diagram of water use and discharges indicating average rates of flow for individual waste streams of McGuire Nuclear Station is attached.
Actual flows through individual systems may vary significantly depending on operational needs and meteorological conditions. Normally, liquid radio-active waste are discharged only through Outfall 004. However, it is possible for any of the discharges to be contaminated by low levels of radioactivity. All discharges of radioactivity are regulated by the Nuclear Regulatory Commission in accordance to 10 CFR Part 20 and 10 CFR Part 50.
The follcwing is a brief description of the major systems.
STATION INTAKE All water for McGuire Nuclear Station is withdrawn from Lake Norman through a duel intake system - a surface and a subsurface system. These systems supply the Main condenser Cooling Water (CCW), Conventional Low Pressure Service Water, Nuclear Service Water, Fire Protection System, and Filtered Water Make-up.
Surface Intake McGuire Nuclear Station has two (2) power generating units with.four (4) CCW pumps per unit. There are two (2) intake screens per pump for a total of 16 screens. The intake screens are backwashed on an intermittent basis to prevent pressure differential buildup across the intake screens. The frequency of cleaning is determined by the amount of debris on the screens. The normal frequency is daily. Approximately 8,500 gallons of water are used to backwash each screen. The water is returned to Lake Norman at the intake bay. The debris collected from the screens is placed in sanitary containers and transported to a licensed sanitary landfill. No chemicals are used in the backwash water.
Subsurface Intake l
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The subsurface intake (Low Level Intake) is located near the bottom of I
Lake Norman at Cowans Ford Dem. There are six (6) low level intake l
pumps with a capacity of 150,000 gpm each. This pump system pumps cool
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water from the lake hypolimnion and mixes it with the warmer water in
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l the surface intake structure during times of high lake surface water l
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temperatures. The Low Level Intake is also the primary source of water for the Containment Ventilation Cooling Water System and the Nucler i
Service Water System.
NUCLEAR SERVICE WATER The Nuclear Service Water System is a safety related once-through non-contact cooling water system. The Nuclear Service Water System supplies cooling water to various heat loads in both the primary and secondary i
portions of each unit. There are two (2) pumps per unit (four (4) pumps total) that are capable of delivering 17,500 gpm per pump. The water supply is from Lake Norman or the Standby Nuclear Service Water Pond. Water from Lake Norman can be supplied by the main condenser circulating water system from the surface intake or by the Low Level Intake. The normal source of water is the Low Level Intake system. The normal discharge is to Lake Norman through Outfall 001.
The Standby Nuclear Service Water Pond (SNSWP) is a 34.9 acre pond designed to provide water for the safe shutdown of the station in the unlikely event that Cowans Ford Dam is lost. The level in the pond is maintained, per requirements of the McGuire Nuclear Station Operating License Technical Specifications, by pumping water from Lake Norman into the pond. The pond overflows to the Catawba River via the Wastewater Collection Basin (WWCB, Discharge 005). The pond also receives runoff from a drainage area of 171 acres. When the Nuclear Service Water System is aligned to take suction from the SNSWP, discharge is back to the SNSWP. This recirculation mode is normally implemented for three (3) hours every six (6) weeks. This testing frequency can change based on the results of the test.
As a result of accelerated corrosion of the nuclear service water system piping, a corrosion inhibitor program is being considered. Corrosion inhibitors under evaluation include
- zinc, nitrites, polyphosphates, phosphates,
- borates, polysilicates, molybdates, benzotriazole (BZT),
toyltriazole (TT), and mercaptobenzothiazole (MBT). Low levels of one or two of these corrosion inhibitors will be discharged at environmentally acceptable levels. Macrofouling by Corbicula (Asiatic clams) can impact the safe operation of the station; microbial influenced corrosion (MIC) has caused frsilures of piping and heat exchanger tubing due to pitting. Non-oxidizing biocides or chlorine (or sodium hypochlorite) will be used at concentrations that result in environmentally acceptable discharge levels to address macrofouling and MIC.
Containment Spray Heat Exchangers As part of normal heat exchanger maintenance, one (1) of four (4) heat exchangers per month is treated with an alkaline flush. These flushes may consist of 1-2% sodium hydroxide, 1-2% sodium metasilicate, 1-2%
sodium carbonate, 1-3% trisodium phosphate, and 1% surfactant solution and an approved biocide. The waste volume is approximately 5000 gallons per cleaning. Approved biocides (sodium hypochlorite and organic biocides) are used to control biological growth in these heat exchangers. The flush water may be discharged via the Condenser Cooling Water (CCW) System or the Standby Nuclear Service Water Pond (SNSWP). Alternative flushes may be performed using mild organic acids l
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l (citric, oxalic, or formic) if needed to remove excessive corrosion--
deposits or Corbicula. In this case, if treatment. is necessary, the waste can'be directed to the Conventional Waatewater Treatment' (WC) system.
In order to mitigate corrosion of the carbon steel, wet lay-up syst. ems are being installed. Various corrosion inhibitor solutions including.
- zinc, ortho-phosphates, polyphosphates, polysilicates,
- nitrites, borates, and molybdates may be used. Organic biocides or' sodium hypochlorite (chlorine) will oe added. for biofouling. control. The-corrosion inhibitor solution will be released during the flow balance and heat exchanger performance. testing.
CONVENTIONAL I4N PRESSURE SERVICE WATER The Conventional Low pressure Service. Water System supplies low pressure cooling water for various functions on the secondary side of the station.
The system takes suction from the condenser cooling water cross-over lines and supplies cooling water to various motor bearings, seals, lube ' oil coolers, vacuum breaker valves, and blowdown separator. Discharge is back into the condenser cooling water system. The Low Pressure Service Water System is the supply for process water.
FIRE PROTECTION SYSTEN l
The Fire Protection System provides the plant site with protection from l
postulated fires. The system is equipped with two (2) 200 gym jockey pumps which take suction from the Condenser Cooling Water System. One pump is capable of maintaining system pressure; however, the second pump is used to
- supplement the jockey pump system capacity. In the event the jockey pumps can no longer supply enough water to maintain system pressure, the three (3).2500 gpm main fire pumps will start sequentially. The fire protection l
system is continuously chlorinated to a concentration of'approximately 1-3 ppm to assure that Corbicula are not present in the system's piping. The fire protection system is used as the source of water for bearing lubrication and gland seal on the low level intake pumps.
System operability is demonstrated by periodically performing specific tests on the system. A sununary of the current testing schedule follows.
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Monthly, the main fire pumps are started, then stopped, to assure operability. Very little, if any, water is discharged during this test. Each valve on each hydrant is stroked annually to assure proper operation; no water is discharged. At this same time, each hydrant is opened and flushed to verify flow. Very little water is discharged; any water discharged flows across paved lots, dirt, or grass to yard drains from which it discharges to the SNSWp or Wastewater Collection Basin (WWCB). Generally twice per month, a valve at the farthest point from chlorine injection in the system is opened, flushed, and the water tested for chlorine to assure the system is properly chlorinated. Administrative procedures are in plac6 to assure that the water flows across dirt or grass to yard drains. This test is performed only if the system is being chlorinated (i.e., the jockey pumps are operating and the chlorine cylinders are open).
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l The transformer emulsifier system is tested annually. The transformers are subjected to a wet or dry test, whichever is appropriate for that l
particular transformer. Any water discharged flows across paved lots, j
dirt, or grass to yard drains.
Also annually, the head curve for each of the three (3)' main fire l
pumps is verified. For the test, each pump is isolated; the flow path is from the lake, through the pump and a test header, and discharged back to the lake. No chlorine is in the water since the pump is i
isolated from the fire protection loop.
j Every 18 months, the system is tested to verify sequential starts of the pumps and automatic valve actuation. The water that is discharged during the test flows across paved lots, dirt, or grass to the yard drain system.
Every three (3) years, flow through the hydrant loop in the station yard is evaluated to assure the hy& ants maintain the proper pressure and flow. The water discharged flows across paved lots, dirt, or grass to the yard drain system.
There is a non-routine test performed at the discretion of the system coordinator.
During the
- test, several hydrants are opened simultaneously to verify the velocity and chlorination level. The water discharged flows across paved lots, dirt, or grass to the yard drain system, and hence to the SNSWP or WWCB. Any chlorine residual present should be dissipated by the chlorine demand of the water in the SNSWP or WWCB.
Additional testing is performed on the system. These tests, however, do not discharge any water. These tests include visual inspections of the system to verify flow path by verifying valve alignment and to verify the condition of the system and/or equipment. Other tests include simulating conditions that will actuate alarms.
OUTFALL 001 outfall 001 is comprised of the main Condenser Cooling Water (CCW),
Conventional Low Pressure Service Water, Nuclear Service Water, and Liquid Radioactive Waste (Radwaste). Outfall 001 discharges into Lake Norman.
Condenser Cooling Water The CCW System is a once-through non-contact cooling water system that removes heat rejected from the main and feedwater pump turbine condensers and other selected heat exchangers. Each of the two (2) power generating units has four (4) CCW pumps for a total of eight (8) pumps. The flow for each unit depends on the number of pumps operating as shown by the following table.
Number of pumps Operating Total Flow / Unit (cpm) 1 254,000 2
640,000 3
867,000 4
1,016,000 l
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The operational schedule of the pumps of each unit is a function of the intake water temperature and the unit load. At 100 per cent load and the intake temperature near its sumer high, three and sometimes four CCW pumps are used. When the unit load is less than 100 per cent and intake temperatures are lower, fewer pumps may be needed.
Condenser cleaning is by mechanical means (trade name "Amertap"). This syste'n circulates small sponge rubber balls through the condenser continuously.. It may become necessary to institute chemical control for macroinvertebrate infestation, general corrosion, and microbiologically induced corrosion (MIC). Chemicals anticipated to be added include chlorine (sodium or calcium hypochlorite), organic
- biocides, dispersants, and corrosion' inhibitors.
The corrosion 3nhibitors may include zinc, nitrite, polyphosphates, phosphates, borates, sil.icates, and molybdates. Discharge concentrations will be maintained below approved discharge levels.
A 316(a) study was submitted August 9,1985. and a 3. 6(a) variance was granted October 18,1985. Plant operating conditionr, and load factors are unchanged and are expected to remain so for the term of the reissued permit.
A Lake Norman aquatic environment maintenance monitoring program was implemented July 8, 1987. Duke Power Company is not aware of any changes to plant discharges or other discharges in the plant site area which could interact with the thermal discharge or to the biotic community of Lake Norman. Duke therefore requests a continuation of the existing 316(a) variance, or as modified by the outstanding 316(a) permit modification request.
OUTFALL 002 Outfall 002 discharges treated wastewater from the Conventional Wastewater Treatment (WC) System through a Parshall flume to the Catawba River below Cowans Ford Dam. The WC system consists of a concrete lined initial holdup pond (IHP, 200,000 gallons), two (2) parallel clay-lined settling ponds (2.5 million gallons each), and a concrete lined final holdup pond (FHP, 1 million gallons). Normally, inputs are received in the IHP but can be routed directly to an in-service settling pond. The IHP serves as a consnon mixing point for all wastewater, a surge-dampening function to the remainder of the system, and allows the heavy solids to settle for periodic removal. Retention time in the IHP is 12 to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. Solids removed from the IHP are dewatered and disposed of on a State licensed landfarm or landfill.
Flow is directed to the in-service settling pond through the chemical addition building where caustic, acid, and/or other chemicals may be injected into the water by a metering pump. Sulfuric acid and sodium hydroxide are added for pH control or to precipitate various chemical compounds. Coagulants may be added to facilitate the settling of lighter solids.
Additional treatment may include chemical oxidation with hypochlorite (calcium or sodium) or catalyzed hydrogen peroxide. Retention time for each of the settling ponds range between 6 and 12 days.
The settling ponds can discharge to the FHP or directly to the Catawba River.
Treatment and discharge are normally on a batch basis.
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The FHP is aerated and is used to remove any persistent oxygen demand or to provide additional holdup capacity. The FHp retention time is 1 to 2 days.
The capability is available for recirculation intra-or inter-basin. Flow to the Catawba River may be by gravity at a rate of approximately 200 gpm
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or be pumped at a rate of approximately 500 gpm. The pH of the discharge j
from the WC system is adjusted by the automatically controlled addition of 1
carbon dioxide.
The WC system accepts all nonradioactive plant waste except sanitary sewage.
The inputs can be contaminated with very low levels of radioactivity. Any discharges of radioactivity are monitored and accounted for, being regulated by the Nuclear Regulatory Connission (NRC). Inputs to i
the system are from the turbine building sumps, water treatment room sump, condensate demineralized backwashes, standby shutdown facility (SSF), and laboratory drains. Steam generator blowdown, wet lay-up, and the unwatering pump discharges may be routed through this system.
Water Treatment Room Sump, Inputs to the Water Treatment Room Sump consist of drainage from all equipment including pump seal leakoff and bearing cooling water located in the Water Treatment Room.
Other inputs include the Diatomaceous Earth (DE) Slurry Tank drain, acid and caustic day-tank storage overflow drains, carbon filter backwash and sluice, pressure i
filter backwash, demineralized regeneration waste, and backflow l
preventer drains. In addition, floor wash and sample line flush water are routed to this sump. Antifoaming agents and wax strippers are routinely present in this waste stream. The drains in the plant I
" boiler room" are also routed to this sump. The drains contain sodiuut nitrite / borax /benzotriazole (BZT) corrosion inhibitor and microbicide due to leakoff and sample purging from the HVAC systems.
Filtered Water System Water from Lake Norman is treated for both process and potable use.
Filtration is performed by DE filters. Water from the Low pressure Service Water System is treated with chlorine for disinfection purposes and polyelectrolytes to coagulate colloidal material. The water is filtered through one (1) 750 gpm DE filter while a second l
filter is on standby. The filtered water is stored in three (3) 42,500 gallon Filtered Water Storage Tanks.
When the administratively determined pressure differential across the filter is achieved, the filter is backwashed thereby removing the filter cake. The system utilizes approximately 100 pounds of DE and 16 ounces of polyelectrolyte per day. Backwashing requires approximately 3,000 gallons of water per day.
Approximately every 2-5 years, citric acid is used to clean the filter elements because of tube fouling. The approximately 110 gallons per year of waste citric acid is collected in drums and treated with caustic to adjust the pH and precipitate any metals that may be present. The waste is then discharged to the WC system.
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Drinking Water System The Drinking Water System takes suction from the Filtered Water-System and pumps it to the 5,000 gallon Drinking Water Storage Tank.
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Demineralized Water System L
The Demineralized. Water System provides high purity water ' for l
make-up to the. primary and secondary systems and ' for ' laboratory.-
usage. There are two (2) carbon filters and two (2) mixed bed '
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regenerative domineralizers with a. system design flowrate of.475 gpm. Normally, two (2) carbon beds and one (1)-domineralizer_is in use while the other is being regenerated or is on standby.
The Demineralized Water System takes suction from the ' Filtered Water System. The carbon filters remove organic substances and any. residual ~ chlorine.
These filters may be. cleaned.by backwashing, steam cleaning, and rinsing. The cleaning occurs twice per month; 15,000 gallons of water are used for the cleaning.'Each carbon bed is replenished every six - to twelve months.
With normal demineralized water requirements, regeneration of one domineralizer occurs approximately every five.(5) days. To regenerate the resins, sulfuric acid and sodium hydroxide are-flushed through the bed. At the present time, each normal regeneration takes approximately 90 gallons of 93% sulfuric acid, 400 gallons of 50% sodium hydroxide, and 75,000 gallons of water.
The amounts of required acid and caustic will vary as dictated by operational requirements. The domineralizer beds are surfactant cleaned approximately two to four times per year, caustic soaked annually, and brine soaked as necessary to remove foulants from the resin. The frequency of cleaning may vary depending on. the need as determined by the quality of the water produced..The demineralized beds are sluiced and replenished approximately every four (4) to seven (7) years.
Turbine Building Sump The Turnine Building Sumps receive inputs from leakage, drainage, and liquid wastes from equipment and floor drains located in the Turbine Building. Inputs include Groundwater Drainage Sump, Auxiliary Electric Boiler illowdown, Steam Generator Blowdown, filter air handling units, Diesel Generator Room Sumps, lab drains, floor washes, and condensate polisher backwashes. Other possible inputs include CCW Unwatering, and steam generator wet lay-up. Chemicals that may be in this flow include the following:
anunonia hydrazine morpholine (planned for future use) nitrite / borax /benzotriazole (BZT) corrosion inhibitor microbiocides industrial cleaning products laboratory chemicals 9
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The Turbine Building Sumps normally are routed to the WC ' System.
l However, if radioactivity limits are exceeded, these sumps can be routed through Radwaste or to the radwaste discharge point depending on the treatment needed. Very low levels of radioactivity can be routed to the WC System. All radioactivity is accounted for and regulated by the NRC.
l Diesel Generator Room Sumps l
The Diesel Generator Room Sumps receive inputs from leakage or draining the diesel generator engine cooling water, fuel oil, and lubrication systems. Each diesel generator room has two (2) l sumps. The smaller ' sump has a volume of 600 gallons and one (1)
I pump with a capacity of 25 gpm. The larger sump has a volume of I
approximately 4,000 gallons, two (2) pumps with a capacity of 450 gpm, and a third pump with a capacity of 50 gpm.
The diesel generator engine cooling water systems have a volume of 800 gallons each. The systems are treated with a mixture of sodium nitrite, borax (sodium tetraborate), sodium bicarbonate, and sodium mercaptobenzothiazole (MBT) to maintain a minimum concentration of 2000 mg/l nitrite. The system is drained and flushed to the WC System approximately once per year.
Additionally, the fuel oil contains residual biocide to reduce bacterial breakdown of the oil.
Lab Drains There are several laboratories that provide analyses on the processes within the plant and which drain to sumps that discharge to the WC system. The discharges contain the standard and typical laboratory chemicals used in analytical procedures performed to verify the quality of process streams.
Floor Wash The floors throughout the station are maintained by a contract vendor. Products used to clean and maintain the floors consist of the typical commercial products.
Condensate Polisher Backwash over time, trace impurities in the condensate system increase in concentration.
In order to maintain the integrity of the condensate system, the condensate is processed through powdered ion exchange resin. A condensate polisher is backwashed on' an average of once per day. The backwash contains approximately 15-20 cubic feet of resin, 120 milliliters of polymer, and requires approximately 10,000 gallons of water. The resin may contain trace quantities of radioactivity from primary to secondary leaks.
The NRC-approved Technical Specifications specify whether the resin is to be treated in the WC System or by Radwaste based on the amount of radioactivity present.
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Condensate polisher Element Cleaning The stainless steel filter elements used in the Condensate polisher tube bundles will be acid washed to clean any fouled elements. During the cleaning process, the elements will be placed in an acid bath consisting either of phosphoric acid, oxalic acid, citric acid or sulfamic acid.
Initially, because of its effectiveness, a twenty (20) percent phosphoric acid solution will be used although the option is available for switching to any of the other three (3) acids. Elements washed with acid will be placed in a rinse tank to remove the bulk of the acid adhered to the elements. From the rinse tank, the elements are backwashed at a flow rate of approximately 60 gpm on a flush stand.
With 1218 elements per bundle, approximately 2400 gallons of flush water will be generated monthly assuming one bundle is cleaned each month. Wastewater from the acid and rinse tanks will' be routed to two (2) 500-gallon treatment tanks for pH adjustment or metal precipitation utilizing a dilute sodium hydroxide solution. Wastewater from the flush stand can be routed to a holding tank of approximately 4000 gallons before discharge. All waste will be discharged via a turbine building sump to the WC System or Radwaste depending on the presence of radioactive contamination.
Wet Lay-up Each of the four (4) steam generators per unit has a volume of 40,000 gallons. Each unit is provided with a Steam Generator Blowdown Recycle System. Steam generator blowdown is continuous at a rate of approximately 5000 gallons per hour to maintain l
acceptable steam generator water chemistry. The blowdown is directed to either the condensate polisher domineralizer or to the steam generator blowdown domineralizer. If the blowdown water quality is unacceptable, it is discharged. It can be discharged to the WC system or to radwaste depending on whether it is contaminated with radioactivity.
During normal operation hydrazine is added to the condensate system for oxygen scavenging. The hydrazine concentration is maintained within a concentration range of 25-200 ppb. Ammonia is added for pH control. The steam generators and hotwell are placed in wet lay-up if a unit is to be in cold shutdown for two days or more.
Each unit is normally shutdown on a 10 month cycle for refueling.
Wet lay-up is the method used for protecting the steam generators against corrosive attack during inactive periods.
Chemical l
additions are made up in a 150 gallon Conventional Condensate Addition System tank. Normally, 55 gallons of 54% hydrazine and 30 gallons of agua ammonia are made up for transfer to the steam generators. Any remaining chemical solution is drained to the WC I
system via the turbine building sump. prior to returning the unit 11
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- (s to operation, this wet lay-up solution (75-250 ppm hydrazine) is drained to the WC System or Radwaste via the turbine building sump.
The hotwell on each unit has a volume of approximately 250,000 gallons. During each unit shutdown that is two days or more in length, the hotwell is placed l in wet' lay-up. Maximum chemical concentrations should be approximately 50 mg/l hydrazine with the.
pH adjusted to 10.2.with amonium hydroxide, prior to returning-the unit to operation, this wet lay-up solution is drained to the WC system or hadwaste via the turbine building sump.
Auxiliary Electric Boiler Blowdown The Auxiliary Electric Boiler is supplied feedwater from the condensate system which contains hydrazine and ammonia. Trisodium phosphate is added as an electrolyte. The blowdown from the boiler contains these three chemicals and approximately 1,000-2,000 ppb suspended solids. Blowdown is routed to' the WC System via. the Turbine Building Sump. The system is used approximately 10 days per year.
Groundwater Drainage System The - Groundwater Drainage System. is designed to relieve hydro-static pressure from the Reactor and Auxiliary Buildings by discharging groundwater collected in sumps to either a yard drain or the turbine building sumps. There are three (3) groundwater sumps with two (2) 250-gpm sump pumps each.
Two of the sumps discharge to the turbine building sumps while the third sump discharges to a yard drain that is routed to the SNSWp.
CCW Unwatering The CCW system for each of the two (2) units has a volume of approximately 2 million gallons. Whenever a unit is scheduled down for refueling, periodically daring other shutdowns, and-for condenser tube
- leaks, the system must be unwatered for maintenance purposes. The water ' is essentially lake water. The principle discharge route is through the Wastewater Collection Basis (WWCB), but it can be routed through the WC System for short periods of time.
Standby Shutdown Facility / Closed Cooling System The Standby Shutdown Facility (SSF) is an alternate and independent means to shutdown the station during emergencies should the need arise. The independent power supply for the SSF is a diesel generator system. The SSF contains a sump to collect system leakage, floor wash, and drainage of the equipment for maintenance. The cooling system for the diesel generator system is a closed cooling system. The cooling system is maintained at l
approximately 2000 to 3000 ppm of a sodium nitrite / sodium tetraborate / sodium benzotriazole (BZT) corrosion inhibitor. The 12
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cooling system is flushed to the WC system annually to maintain efficiency.
There are approximately 10 to 15 closed cooling systems within the station. The largest system has a volume of approximately 30,000 gallons.
The main portions of these systems are constructed of carbon steel. A sodium nitrite (2000 mg/l)/ borax (sodium tetraborate)/ sodium benzotriazole (BZT) corrosion inhibitor is added to control corrosien. An organic biocide is added to control biofouling. These systems may need to be drained, individually, for non-routine maintenance. Should this occur, these systems would be drained to the CCW discharge, WC System, or Radwaste if contaminated with radioactivity.
Steam Generator Cleaning Each electrical generating unit contains four (4) steam generators that have a capacity of approximately 40,000 gallons each. There have been no chemical cleaning of the steam generators to date. However, whenever a chemical cleaning is performed, all four steam generators will be cleaned based on need as determined by the thermal-hydraulic performance. One possible cleaning
- solution, based on previous experience, consists of 15% ammoniated ethylene diamine tetracetic acid (EDTA), 1% CCI 80/1 (a proprietary corrosion inhibitor), 1%
hydrazine and ammonium hydroxide for pH adjustment. The spent solvent may contain radioactivity, iron, and other metals in trace quantities. It will possibly be treated by demineralization and neutralization / precipitation.
Treatment will be either performed in Radwaste or the WC System depending on the level of radioactivity. Additionally, rinse / passivation (300 ppm hydrazine with the pH adjusted to 10.2 with ammonium hydroxide) water will be required. The rinse water will be processed followed by neutralization / precipitation in the WC System. The process may be modified for each cleaning depending on the scale deposited within the steam generators.
Other solutions may be utilized in the cleaning.
Miscellaneous System / Component Cleaning other systems may need to be cleaned periodically because of scaling or plugging. Other components will be cleaned as necessary for various fouling problems. Solutions utilized will j
be those used in standard chemical cleaning methodologies.
l Chemicals utilized by these methodologies, alone or in combination, include the following:
Alkaline Boilout Solutions non-ionic surfactants anionic surfactants cationic surfactants sodium hydroxide soda ash 13 m__
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O trisodium phosphate sodium metasilicate
-disodium phosphate monosodium phosphate sodium bicarbonate Acid Solutions hydrochloric acid sulfuric acid phosphoric acid formic acid hydroxyacetic acid sulfamic acid citric acid nitric acid Acid Solution Additives thiourea ammonium bifluoride oxalic acid EDTA Compounds and HEDTA pH adjusted tetra-amonium EDTA tetra-ammonium EDTA di-ammonium EDTA hydroxyethylenediaminetriacetic acid tetra-sodium EDTA Miscellaneous Compounds chlorothene sodium chloride j
potassium permanganate agua amonia amonium persulfate sodium nitrite i
antifoam sodium sulfite chlorine corrosion inhibitors (e.g., phosphates, borax-nitrite, silicates, etc.)
organic biocides These solutions are described in the Development Document for Effluent Limitations Guidelines and New Source Performance Standards for the Steam Electric Power Generating Point Source Category (Development Document).
The spent solvents from these cleanings will be treated in the WC l
System or the Radwaste System. The acid compounds will be l
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neutralized; the other compounds will be mixed, oxidized, and/or precipitated as necessary for treatment.
OUTFALL 003 Outfall 003 discharges treated sanitary waste from the Sanitary Waste Treatment System to the WWCB. The Sanitary Waste Treatment System is a four (4) cell aerated lagoon system. The system was designed to process domestic sewage from rest rooms, showers, lab drains, and station cafeteria. The lagoon provides a 5-day retention time and will allow for variable level discharge. The wastewater ef fluent from the aerated lagoon flows through chlorinators, a chlorine contact chamber and a Parshall flume before discharging to the WWCB.
The lagoon is lined with a flexible synthetic material such as hypalon; it is divided into four (4) cells by a curtain material such as a polymer coated polyester with a weighted chain ballast and floatation collar. The first cell provides for a two day retention time and is kept in complete suspension by surface mechanical aerators. The second and third cells are kept partially suspended providing for partial settling. Each of these two cells has a retention time of one day. The final cell is the settling cell with a retention time of one day. The surface of this cell is kept slightly agitated to minimize algal growth. If it becomes necessary to control algae growth, an algicide, such as CUTRINE-PLUS, may be added to the lagoon. From the final cell, the wastewater discharges to a chlorination installation.
After passing through the chlorinators, a retention time in excess of 30 minutes is provided by a contact chamber before being discharged to the WWCB.
The sewage lagoon has a multiple level discharge capability at 5. 6 1/2, and 8 feet. At each of these different levels of operation, th'e lagoon is able to provide a 5-day retention time for influent wastewater flow rates of 40,000 gpd, 52,000 gpd, and 64,000 gpd, respectively.
Accumulated solids are removed from the lagoon approximately every 12 to 18 months to facilitate removal of non-biodegradable material and to optimize the treatment process. The sludge bottoms are dewatered utilizing a filter press or other suitable method. The solids are treated with lime and disposed of in a State licensed landfill or landfarm. The filtrate is returned to the sewage lagoon or is treated by neutralization and carbon adsorption or other suitable methods when released directly to the WWCB. An alternative method of sludge disposal is to tank it to a municipal sewage treatment system.
OUTFALL 004 Outf all 004 discharges flow from the liquid radwasta system. This flow combines with the CCW before discharging through the concrete discharge structure (Outfall 001) into Lake Norman. All radioactive and potentially radioactive liquids are collected, segregated and processed prior to release. These effluents are classified as ' recyclable or non-recyclable liquids. Recyclable liquids are recirculated back to the process streams.
Non-recyclable liquids are collected and processed to Nuclear Regulatory Commission (NRC) requirements (10 CFR Part 20 and 10 CFR Part 50) prior to l
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release with the type of processing depending on the type of waste. The maximum discharge rate from radwaste is 150 gpm. The discharge flow for a waste Monitor Tank release is a function of activity level, the number of CCW pumps in operation, and the resultant boron concentration in Lake Norman.
The liquid radwaste system collects waste in three (3) sub-systems (floor and equipment drains, laundry waste, and ventilation unit drains).
Chemicals that may be present in the liquid radwaste system include:
. borax nitrate anrnonia morpholine (planned for future use) lithium hydroxide ethylene glycol j
benzotriazole (BZT) nitrite / borax corrosion inhibitor hydrazine chlorine /hypochlorite hydrogen peroxide l
ethylene diamine tetracetic acid (EDTA)
I containment spray heat exchanger lay-up chemicals i
pump bearing cleaning chemicals laboratory chemicals detergents surfactants polyelectrolytes industrial cleaning products chemical metals cleaning waste The Turbine Building Sump can become contaminated with radioactivity. When this occurs, it can be pumped to the Floor Drain Tank (FDT) or to the Radwaste release point in the CCW crossover line. The decision on the method of treatment depends on the amount of radioactivity in the waste stream. Any chemicals listed as being in the Turbine Building Sump may be in Radwaste when the waste stream is routed to Radwaste.
Any solids generated in the treatment process are solidified or dewatered and transported to a State and NRC licensod low level radioactive waste disposal facility.
Floor, Equipment, and Laundry Drains All floor drains in the auxiliary building, drains from all equipment (pumps,
- tanks, heat exchangers, etc.)
which process aerated radioactive waste, waste from showers in the change rooms and washing equipment which is used to decontaminate protective clothing, and waste from the Unit 1 and Unit 2 containment floor and equipment sumps are routed to the Floor Drain Tank (FDT), Waste Evaporator Feed Tank (WEFT), Auxiliary Floor Drain Tank ( AFDT), Auxiliary Waste Evaporator Feed Tank (AWEFT), and/or Laundry and Hot Shower Tank (LHST). The total tank volume is 125,000 gallons. These collection tanks are used
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l 16
4 interchangeably and/or as backup and surge capacity for waste collection upstream of processing.
1 Waste from these collection tanks is then processed using filters and/or domineralizers. The processed effluent is collected in waste monitor tanks for sampling and analysis prior to release.1 Release is to Lake Norman via the CCW crossover line.
Ventilation Unit Drains The Ventilation Unit Condensate Drain Tanks (VUCDT) collect condensate from air handling units from each reactor building. Each VUCDT has a volume of 4,000 gallons.
This. waste typically has little radionuclides contamination and no chemical contamination.
The waste is sampled for radionuclides contamination. If this sampling indicates the need, the VUCDT contents are transferred to the FDT for processing. If no need for processing is indicated,.the waste is released from the VUCDT via the CCW to Lake Norman.
Twice per year a portion of the ice in the annulus in the reactor building.is melted and drained to the VUCDT. The VUCDT could contain boric acid from the ice melt.
Chemical Volume and Control System The Chemical Volume and Control System regulates the concentration of chemical neutron absorber in the Reactor Coolant System to control reactivity changes and maintain the required water inventory in the Reactor Coolant System. Boron is used as the chemical neutron absorber. Appended is a description of the changes in the boron concentration.
Other control elements introduced into the Reactor Coolant System by the Chemical Volume and Control System include lithium and hydrazine.
Approximately 120 pounds of lithium hydroxide monohydrate are used in each unit per year for pH control.
The lithium is removed by domineralizers in the Reactor Coolant System of the liquid radwaste system.
During cold shutdown, hydrazine is used as an oxygen scavenging agent. It is removed during start up and is not used at any other time. During shutdown, hydrogen peroxide is added to the Reactor Coolant System to facilitate the removal of activated corrosion products.
OUTFALL 005 l
Outfall 005 discharges flow from the Wastewater Collection Basin (WWCB).
- The WWCB is a 13.4 acre collection basin having a total capacity of approximately 40 million gallons; drawdown ' capacity is approximately 11 million gallons. Discharge from the basin ranges from 0 to 20,000 gpm. If the Standby Nuclear Service Wat3r pond (SNSWP) is being flushed, no holdup of the WWCB is possible; otherwise, holdup is minimal.
The WWCB provides 17 L
- sedimentation, natural neutralization, and skiming. The overflow from the WWCB mixes with the discharge from the WC System (Discharge 002) in a concrete apron and is discharged to the Catawba River downstream of Cowans Ford Dam. An algicide, such as CUTRINE-pLUS, may be needed to control algae growth in the pond.
Inputs into the basin include overflow from the SNSWp, treated sanitary waste effluent, yard drains, a lab sink and floor drains, miscellaneous Administrative Building drains, and CCW system unwatering.
Standby Nuclear Service Water Pond The SNSWp is a 34.9 acre pond designed to provide water for the safe shutdown of the station in the unlikely event that Cowans Ford Dam is lost. The level in the pond is maintained, per requirements of the McGuire Nuclear Station Operating License Technical Specifications, by pumping water from Lake Norman into the pond. The pond will receive runoff from a drainage area of 171 acres. The containment spray heat exchanger cleaning solutione may occasionally be routed to the SNSWP.
Sanitary Waste Treatment System The sanitary waste treatments system is a four (4) cell aerated lagoon system. It provides approximately 5 days retention and allows for variable level discharge. The effluent flows through chlorinators, a chlorine contact chcmber, and a parshall flume before discharging into the WWCB. The sanitary waste treatment system is regulated as Discharge 003.
Lab and Floor Drains The lab sink and floor drains discharge approximately three (3) liters of chemical waste per month. These chemicals are standard and typical j
laboratory chemicals used in analytical procedures performed to verify the quality of process streams.
Flow from these drains go to a groundwater sump then to the SNSWp and then to the WWCB.
Administrative Building Drains The Administrative Building drains include an HVAC sump, floor drains, hot water boiler and chilled water system discharge. Any chemicals in the drains would include the typical comercial products used to clean and maintain the floors as well as sodium nitrite / borax /benzotriazole corrosion inhibitor, phosphate corrosion inhibitor, and microbicide l
from leakage / drainage of the HVAC systems.
l CCW System Unwatering The CCW System for each of the two (2) units has a volume of approximately 2 million gallons. Whenever a unit is scheduled down for refueling, periodically during other shutdowns, and for condenser tube leaks, the system must be unwatered for purposes of maintenance.
Unwatering must continue while maintenance is performed because of leakage by the valves in the approximately ll-foot diameter CCW 18
piping. The maximum unwatering rate is approximately 2000 gpm; the water is essentially lake water. Discharge is via the turbine building sumps. Administrative controls are in place, however, to restrict inputs to the sumps during unwatering. Treated liquid radioactive waste effluent (Discharge 004) discharges into a crossover line between the CCW system of the two units. During unwatering, the possibility exists for trace amounts of radioactivity to be released into the water from the unwatering process because of isolation valve
~
leak-by. All radioactivity is accounted for and regulated.by the NRC.
The principle discharge route of the unwatering is through the WWCB.
However, it may be routed through the WC System for short periods of time.
Yard Drains Most yard drains discharge to the WWCB or SNSWP. The drainage area for the plant site is approximately 250 acres.
COWANS M)RD DAM UNDERDRAIN SYSTEM The Cowans Ford Dam underdrain system discharges flow to a ravine that leiads to the Catawba River. Prior to the construction of Cowans Ford Dam and McGuire Nuclear Station, there were indigenous springs in the area.
When the dam, and subsequently the station, were constructed, the dam underdrain system and the springs / groundwater in the vicinity of the Low Level Intake Pump structure were collected and piped away from the area.
Part of the water was piped to a ravine. The water is believed to be lake or groundwater based on the quality of the water as demonstrated by the Part V analyses. Fire protection water is used as bearing lubrication and gland seal water for the Low Level Intake pumps. This water is processed by cyclone separators to remove any silt or sediment that could damage the pumps. The drains from the separators discharge into the underdrain system.
Yard drains in the area discharge through this system.
1 i
l 19
e i
APPENDIX Boron Use and Control Boric acid is used as a chemical neutron absorber in the reactor coolant system for reactivity control and to provide water for safety injection.
During reactor operation, changes are made in the reactor coolant boron concentration for the following conditions:
Reactor start-up - boron concentration must be decreased from shutdown concentration.
Load follow
- boron concentration must be either increased or decreased following a change in load.
Fuel burn-up
- boron concentration must be decreased to compensate for fuel burn-up and the buildup of fission products in the fuel.
Cold shutdown
- boron concentration must be increased to the cold shutdown concentration.
The concentration of boron in the Reactor Coolant System varies from 0 to 2500 ppm depending on core life.
The boron concentration is controlled through the Chemical and volume Control System. The boric acid is stored in the Concentrated Boric Acid Storage Tank at a concentration of 7,000-7,700 ppm boron. The boron concentration in the Reactor Coolant System is varied by blending reactor makeup water from the Reactor Makeup Water Storage Tank and boric acid from
]
the Boric Acid Storage Tank as needed to reach the desired concentration.
l Excess liquid effluents from the reactor coolant system which contains 0 to 2500 ppm boron are diverted (or letdown) to the Recycle Holdup Tanks in the Boron Recycle System. Water from the Recycle Holdup Tanks can be processed as a batch through the boric acid evaporators where the boron is recovered and recycled to the boric acid tanks. Any boric acid that is not of sufficient quality to be recycled is processed further in the Radwaste System. It is further concentrated, solidified, and transported to a State and Nuclear Regulatory Connission (NRC) licensed low level radioactive landfill. The distillate from the evaporators is either returned to the Recycle Water Holdup Tank or transferred to the Reactor Make-up Water Storage Tank.
Water containing boron can also be released to the monitor tanks for discharge as a result of system leakage and flushing operations. The maximum concentration of boron that can be present in the liquid radwaste l
l system discharge is estimated to be 200 ppm. The maximum release rate from l
the liquid radwaste system is approximately 150 gpm. The liquid radwaste system discharges through a valve which is controlled by a radiation monitor and flow meter. This valve is designed as an interlocking device which will not open unless the radioactivity is within limits specified by l
the Nuclear Regulatory Connission in 10 CFR part 20 and a minimum flow rate l
1s established in the CCW System so that the offsite dose will be within f
20 l
l
j limits specified in 10 CFR Part 50. The resulting concentration in Lake -
d Norman is less than 0.75 ppm as_specified by the' Administrative'e Limits.
f 21
FOR YOUR
= 0Sua' "
INFORMAT:0N DtJKE POWER COMPA.NY l
P.O. BOX W180 CHARLOTTE. N.C. 28242 teLrrM >=r II.U 15. Tl'CKER irom ir+ an y
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June 12, 1987 vg j
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U. S. Nuclear Regulatory Commission Attention:
Document Control Desk
/
Washington, D. C. 20555
/
8 Re: Catawba Nuclear Station, Units 1 and 2
/
j Docket Nos. 50-413 and 50-414
(
Technical Specification Amendment Radioactive Liquid Efflutnt Monitoring
Dear Sir:
This letter contains a proposed amendment to the Technical Specifications for Facility Operating License Nos. NPF-35 and NPF-52 for Catawba Units 1 and 2.
The attachment request involves adding operability and surveillance requirements for radioactive liquid ef fluent monitoring instrumentation for the Turbine Building sump and will provide radioactive liquid waste sampling and analysis program requirements for the Turbine Building sump domineralizer skid and radiation monitor EHF-31. The attachment contains the proposed change and a discussion of the justification and safety analysis. The analysis is included pursuant to 10 CFR 50.91 and it Las been concluded that the proposed amendment does not involve significant hazceds considerations.
This request involves une amendment request to Catawba's Technical Specifications.
Accordingly, pursuant to 10 CFR 170.21 a check for $150.00 is enclosed.
Pursuant to 10 CFR 50.91 (b) (1) the appropriate South Carolina State Official is being provided a copy of this amendment request.
Very truly yours, s/Hal B. Tucker Hal B. Tucker RWO/62/sbn I
Attachment I
e fl*
U. S. Nuclear Regulatory Commission
-June 12, 1987 3
Page Two I
i
{
xc:
Dr. J. Nelson Grace, Regional Administrator U. S. Nuclear Regulatory Commission l
Region II l
101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323 Mr. Hayward Shealy, Chief Bureau of Radiological Health
.f l
South Carolina Department of Health &
Environmental Control 1
2600 Bull Street Columbia, South Carolina 29201 American. Nuclear Insurers l
e/o Dottie Sherman, ANI Library
' The Exchange, Suite 245 270 Farmington Avenue Farmington, CT 06032 M&M Nuclear Consultants 1221 Avenue of the Americas New York, New' York 10020 INPO Records Center Suite 1500 1100 circle 75 Parkway Atlanta, Georgia 30339 Mr. P. K. Van Doorn NRC Resident Inspector Catauba Nuclear Station j
l i
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l 1
1 l
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U. S. Nuclear Regulatory Commission
]
June 12, 1987 l
i Page Three bxc:
M. L. Birch D. G. Browne A. V. Carr R. C. Futrell_
E. M. Geddie R. L. Gill W. A. Haller J. W. Harapton l
C. L. Hartzell D. R. Kulla i
J. M. McCarry M. D. McIntosh L. T. Parker R. M. Propst N. A. Rutherford R. O. Sharpe P. L. Stiles J. E. Thomas J. G. Torre R. F. Wardell L. L.' Williams W
~
NC MPA-1 NCDiC PMPA i
$ REC Group File:
CN-801.01 o
l
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+-
U. S. Nuclear Regulatory Concission June 12, 1987 Page Four RAL B. TUCKER, 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 revision to the Catawba Nuclear Station Technical Specifications, Appendix A to License Nos. NPF-35 and NPF-52; and that all statements and matters set foren therein are true and correct to the best of his knowledge.
s/Hal B. Tucker Hal B. Tucker, Vice President Subscribed and sworn to before me this 12th day of June, 1987.
s/ Linda L. Kessier Notary Public My Commission Expires:
May 1, 1989 j
il Discussion and Analysis of No Sienificane Hazards Consideration The proposed amendment to Technical Specification Tables 3. 3-12, 4. 3-8 and 4.11-1 would add operability and surveillance requirements for radioactive liquid effluent monitoring instrumentation for the Turbine Building sump and provide radioactive liquid waste sampling and analysis program requirements for the Turbine Building Sump Domineralizer Skid and radiation monitor EMF-31.
Primary to secondary leaks can develop through reparable defects in the steam generator heat exchangers and into the sormally non-radioactive turbine steam system (" secondary side") water.
Such leaks would be repaired as they occur, but require continued unit operation with leakage until the leak can be fully identified and characterized. When these leaks occur, the Turbine Building sump i
can become radioactively contaminated.
)
The volume of wastewater produced during these leaks can exceed the treatment capacity of the Liquid Radioactive Waste Treatment System.
Duke Power Company plans to provide portable equipment as needed to treat the water from these potential situations. The treated wastewater will be discharged into the Low Pressure Service Water (RL) System. The attached flow schematic indicates the flow path. The radioactive release rates will meet 10 CFR Part 20 Appendix B limits.
The KRC dose limit imposed by the Technical Specifications and 10 CFR Part 50 will also be met.
A Nuclear Station Modification (NSM) is being installed which will provide influent I
and effluent flow paths for Chem-Nuclear Company equipment during a primary to secondary leak. The processed water will be discharged through Radiation Monitor EMF-31 to the RL discharge piping in the Turbine Building from the Turbine Building sump.
i The purpose of this modification is to allow very low levels of radioactivity to be discharged through the Conventional Wastewater Treatment (WC) System from the Turbine Building sump as a result of primary to secondary leaks as well as the Auxiliary Building drain sump when contaminated.
During a primary to secondary leak, the Turbine Building sump can be contaminated with very low levels of radioactivity. The quality and quantity of this wastewater may not be amenable to trea tment in the Radwaste Treatment System or by the portable equipment.
h The decision of whether the wastewater will be routed to the Radwaste Treatment System or the WC system would depend on the level of activity, anticipated volumes of sump effluent, anticipated volu=es of liquid waste requiring processing through radvaste, and the need to process normal nonradioactive wastes.
The Radwaste System has a process capacity of only 16,000 to 18,000 gallons per day. Depending on the type of primary to secondary side leakage, sumps could add in excess of 72,000 gallons per day.
1 Technical Specification 3/4.11.1, Table 4.11-1 already identifies the WC System as l
a radioactive release point. All releases through the WC System will be made in accordance with the Technical Specifications and will not result in unacceptable concentrations of radioactive effluents released offsite.
Neither will there be any increased risk to public health and safety.
i l
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w-_-____-__-___-______
l l
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I It should be emphasized that the Radwaste Treatment System will remain the primary l
system for processing highly contaminated radioactive wastes and their treatment subsequent release.
The proposed modifications will be utilized for processing secondary side and trace-contaminated wastes such as Auxiliary Building ventilation
[
condensate. These waste waters will be controlled and their radioactive concent reduced to within 10 CFR Part 20, 10 CFR Part 50 and Technical Specification I
limits.
The WC System will be monitored and discharged in compliance with all applicable radiological effluent concentrations and dose requirements stated in the stations Technical Specifications and Federal Regulations.
It will also be sampled and monitored in compliance with the NPDES permit.
Please note that these changes are being requested for clarification and consistency. The 10 CFR 50.59 review which was performed during the review of the above mentioned NSM concluded that Technical Specification changes were not required since discharge through the Conventional Vaste Water Treatment line is already addressed in Technical Specification Table 4.11-1, 10 CFR 50.92 states that a proposed amendment involves no significant hazards considerations if operation in accordance with the proposed amendment would not:
(1)
Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) Create the possibility of a new or different kind of accident from any accident previously evaluated; or (3)
Involve a significant reduction in a =argin of safety.
The proposed amendment does not involve an increase in the probability or consequences of any previously evaluated accident.
The probability of an accident is not increased because these chac;cc involve addition of components to mitigate the consequences of previously evaluated accidents. The offsite dose consequences resultiny, from primary to secondarj laaks will be decreased as a result of this
)
modification and Technical Specification amendment.
These changes will allow
{
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installation of processing equipment capable of reducing offsite doses.
l This modification and Technical Specification amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated since these changes do not affect the design or operation of any Safety-Related Systems.
These changes do not involve a significant reduction in a margin of safety since these changes do not affect the design or operation of any Safety-Related System.
For the reasons stated above, it is concluded that the proposed amendment does not involve significant hazards consideration.
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N ACTION STATEMENTS f
^CTICN 40 - With the number of channels OPERABLE less than recuicec ey tre 1
Minimum Channels OPERABLE recu1rement, effluent releases via tn.s pathway may continue for up to 14 cays provicec that prior
- .o I
initiating a release:
At least two independent samples are analyzed in accorcance a.
with Specification 4.11.1.1.1, and At least two technically qualified members of the facility b.
staff independently verify:
1.
The discharge line valving, and i
The manual portion of the computer input for the release 2.
rate calculations performed on tne computer, or the entire release rate calculations if such calculations are performed manually.
Otherwise, suspend release of radioactive effluents.via this pathway.
ACTION 41 - With the number of channels OPERASLE less than recuired by theefflu Minimum Channels OPERA 8LE requirement, pathway may continue for up to 30 days provided the flow rate is Pump estimated at least once per 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> during actual releases.
perfor,ance curves generated in place may be used to estimate flow.
.With the number of channels OPERABLE less than required by the Minimum Channels OPERABLE requirement, effluent releases via ACTICN 4*
this pathway may continue for up to 30 days provided grab samples are analyzed for radioactivity at a lower limit of detection of no more tnan 10 7 microcurie /ml:
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> when the specific activity of the secondary coolant is greater tnan 0.01 microcurie / gram CCSE EQUIVALENT I-131, or At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> wnen tne specific activity of the secondary coolant is less tnan or ecual to 0.01 microcurie / gram D.
DOSE EQUIVALENT I-131.
ACTION 43 - With the number of channels OPERABLE less tn via tDe atmosoneric vent valves (off-normal moce) may continue pro-viced grao samples of steam generator water are analyzec for racio-activity ~for uo to 30 days' at a lower limit of cetection of no more than 10- microcurie /ml:
- a. At least once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> wnen the scecific activity of tre secondary coolant is greater tnan 0.01 microcurie / gram OCSE EQUIVALENT I-131, or At least once per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> wnen the specific activity of the secondary coolant is less than or equal to 0.01 microcurie /gran b.
OOSE EQUIVALENT I-131.
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TABLE a.11-1 RAOICACTIVE LIQUID WASTE SAMPLI.G ANO aNAlv5:5 :#C N
.C'aER. w: ~
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'CF lETE:T':1 MINIMUM i
LIQUID RELEASE SAMPLING ANALYSIS TYPE CF ACTIVITY (LLO)(*'
s e
TYPE FREQUENCY FREQUENCY ANALYSIS
(,Cini)
P Release Each Baten Each Baten Principal Gamma 5x10 7 P
1.
Baten Waste Emitters (3) 1x10
- Tanks 1-131 Any tank which Dissolvec ano
.x.,J >
M P
discharges Entrainec Gases l
liquid wasteJ One Saten/M (Gamma Eststars) 1 by tne licuic
'l e/ fluent moni-le;J d M
n-3 l
- c, EMF-49 P
g Each Baten Composite Gross Alena 14 07 i
i 5 x '.0 8
Q lSr-89,Sr-90 P
Composite (4)
".x '.; i Eacn Baten 1
Orinc :a1 Gamma 5 C.
7 i
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Releases (')
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Jme 5, 1987 Cocket Nos.: 50-369 and 50-370 Mr. H. B. Tucker, Vice President Nuclear Production Ceoartment Duke Power Company 422 South Church Street l
Charlotte, North Carolina 282a2 Cear Mr. Tucker:
Issuance of knendment No. 72 to Facility Operating License NPF-9 and knendment No. 53 to Facility Coerating License NPF McGuire
Subject:
Nuclear Station Units 1 and 2 (TACS 61179/61180)
The Nuclear Regulatory Commission has issued the enclosed Amendment No. 7 Facility Operating License NPF-9 and knendment No. 53 to Facility Operating These arrend-License NPF-17 for the McGuire Nuclear Station, Units 1 and 2.
ments consist of changes to the Technical Specifications in response toas s your application dated March 19, 1986, June 4, 1987.
'be amendments change Technical Specification Figu The amendments are effective as of their date of issuance.
A cooy of the related safety evaluation succorting Amendment No.72 to Facility Operating License NPF-9 and Amendment No. 53 to Facility Operj License NPF-17 15 enclosed.
Notice of issuance of amendments will be included in tre Comij ci-weekly Federal Register _ notice, Sincerely, N
o -
Carl Hood, Pro,ect Manager Project Directorate [!-3 Division of Reactor Projects-I/ :
Enclosures:
1.
knendment No. 72 to NPF-9 2.
Amendment No. 53 to NPF-17 3.
Safety Evaluation l
cc w/ enclosures:
See next page
$}7Fm] &,l *19 w
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l Mr. H. B. Tucker McGuire Nuclear Station Duke Power Company CC:
Mr. A.V. Carr, Esq.
Dr. John M. Barry Department of Environmental Pealth Duke Power Company I
P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard i
Charlotte, North Carolina 2F242 Charlotte, North Carolina 28203 i
County Manager of Mecklenburg County 720 East Fourth Street Charlotte, North Carolina 28202 Chainnan, North Carolina Utilities 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, Eso.
Division of Facility Services Bishop, Liberman Cook, Purcell
' Department of Human Resources 701 Barbour Drive and Reynolds 1200 Seventeenth Street, N.W.
Raleigh, North Carolina 27603-2008 i
I 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, Gecrgia 30323 f
L. L. Williams J
Area Manager, Mid-South Area a
ESSO Projects l
Westinghouse Electric Corporation MNC West Tower - Bay 239 P. O. Box 355 Pittsburgh, Pennsylvania 15230 l
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u UNITED STATER NUCLEAR REGULATORY JMMISSION g
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DUKE POWER COMPANY DOCKETNO.50-36j McGUIRE NUCLEAR STATION, UNIT 1 AMENDMENT TO FACILITY OPERATING LICENSE Amendment No. 72 License No. NPF-9 1.
The Nuclear Regulatory Comission (the Comission) has found that:
The application for amendmt to the McGuire Nuclear Station, A.
Unit 1 (the facility) Facility Operating License No. NPF-9 filed by the Duke Power Company (the Itcensee) dated March 19, 1986, as supplemented December 3, 1986 and June 4, 1987, complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; The facility will operate in confonnity with the application, as B.
amended, the orovisions of the Act, and the rules and regulations 3
of the Comission There is reasonable assurance (i) that the activities authorized by l
C.
this amendment can be conducted without endangering the health and safety of the public, and (11) that such activities will be conducted in ecmpliance with the Comission's regulations set forth in 10 CFR Chapter I; The issuance of this amendment will not be inimical to the comon D.
defense and security or to the health and safety of the public; and The issuance of this amendment is in accordance with 10 CFR Part 51 E.
of the Comission's regulations and all applicable requirements have I
been satisfied.
V'f f i /) / _ ///A W WVI) Q
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2 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 Accendix A, as revised through Amendment No. 72, are hereby incorootated 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 COM41SSION DU B. J. Youngbl od, Director Project Directorate 11-3 Division of Reactor Projects-I/II
Attachment:
Technical Specification Charges Date of Issuance: June 5, 1987 l
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NUCLEAR REGULATORY COMMISSION a ssiuorou.o.c.rosss
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DUKE PCWER COMPANY DOCKET NO. 50-370
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McGUIRE NUCLEAR STAT!CN, UNIT 2 1
AMEN 0 MENT TO FACILITY OPERATING LICENSE
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Amendment No. 53 License No NPF-17 I
1
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1.
The Nuclear Regulatory Comission (the Commission) has found that:
i I
The application for amendment to the McGuire Nuclear Station, A.
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 and requirements of the Atomic Energy Act of 1954, as amended (the Act) and the Comission's rules and regulations as set forth in 10 CFR Chapter I; The facility will operate in confonnity wi:n the application, as B.
amended, the provisions of the Act, and the rules and regulations of the Comission; There is reasonable assurance (1) that the activities authorized by C.
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; The issuance of this amendment will not be inimical to the comon C.
defense and security or to the health and safety of the public; and The issuance of this amendment is n accordance with 10 CFR Part E.
the Comission's regulations and al, applicable requirements have been satisfied.
s' 2
Accordingly, the license is hereby amended by page changes to the Technical 2.
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 N'JCLEAR REGULATORY COMISSION L *\\/
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a B. s oungb1 d, Director Prd. ec Directorate II-3 Division of Reactor Projects-I/II
Attachment:
Technical Specification Changes June 5, 1987 Date of Issuance:
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o ATTACHMENT TO LICENSE AMENDMENT NO. 72 FACILITY OPERATING LICENSE NO. NPF-9 DOCKET NO. 50-369 AND
. TO LICENSE AMENDMENT NO. 53 FACILITY OPERATING LICENSE NO. NPF-17_
DOCKET NO. 50-370 Replace the following page of the Apoendix "A" Technical Specifications with the enclosed page. The reviseo page is identified by Amendment nunter and contains vertical lines indicating the area of change.
knended Page 5-5
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SITE BQuNcARY FOR LIQUtt EFFLUENT 1
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Amendment No.
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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 AMENOMENT NO. 53 TO FACILITY OPERATING LICENSE NPF-17 OUXE POWER COMPANY
^^iKET NOS. 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 By letter only to Lake Noman, an upstream impoundment of the Catawba River.
dated March 19, 1986, Duke Power Company (the licensee) requested a change to the TSs for McGuire Nuclear Station, Units 1 and 2.
This proposed change would 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 The change would affect only the discharge location, and would not increase existing TS limits regarding (1) the quantity of radioactive material system.
contained in the treatment cond, (2) allowable doses to the public from releases to unrestricted areas, and would not decrease existing TS requirements regarding liquid discharge monitoring. The licensee provided additional infomation 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 but retaining the existing arrow at the river and its label, on June 20, 1986, (The existing arrow, label, and footnote were
" Liquid Waste Discharge Point."
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 Catawba River.
another discharge point directly to the Catawba River.
Water from the turbine building sump is normally released through the conven-The quantity of radioactive material tional wastewater treatment system.
contained in each treatment pond, and in each batch of slurry (used power resins) to be transferred to the treatment ponds, is limited consistent with i
10 CFR 20, Appendix B. Table II by existing TS 3/4.11.1.5 and is not changed f)/f (WV' 7
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_ by these amendments. There are provisions for releasing turbine building sumo l
water through the liquid radwaste system.if the sumo water is contaminated with radioactivity. The liquid radwaste system is cecable of processing 27,500 god, whereas the turbine building sumps can add up to 120,000 god during operation with crimary to secondary leakage. Thus, the liquid radwaste system is not capable of handling the turbine sump discharge on a continuing basis as would be required by the present technical specifications if there 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 solutiens were unduly costly and were unwarranted in view of the low levels of radioactivity and doses involved. Therefore the licensee requested approval to release low level liquid radwaste through the conventional wastewater treatment system.
The TS change does not cecrease the existing monitoring requirements (TS 3.3.3.8 and referenced TS Table 3.3-12) which assure that instantaneous radioactive release rates remain within 10 CFR 20, Appendix B limits, and that radioactive 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 The licensee has comitted to make these measurements with the system.
sensitivity necessary to assure that the concentrations are below the levels needed for compliance with the dose design objectives of 10 CFR 50 Apoendix I.
Specifically, the licensee comitted to maintaining a lower limit of detection of 0.1 oCi/L or less for Cs-137 These provisions satisfy General Design
-Criterion 64 which require that a means be provided for monitoring effluent discharge paths.
The dose or dose comitment to a member of the oublic from radioactive materials in liquid effluents released from each McGuire unit is limited consistent with 10 CFR 50, Appendix I by existing TS 3/4.11.1.2 and is not The licensee has cemitted to ensuring that changed by these amendments.
the use of this new release point does not increase the total oermitted release from the station. To accomplish this, doses at both the new and old release points will be added and the total will be maintained below the limits of Technical Specification 3.11.1.2.
The concentration of radioactive material released in liquid effluerts to unrestricted areas is limited consistent with 10 CFR 10, Appendix 3, Table II by existing T5 3/4.11.1.1 anc 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 Norman reaches the Catawba River af ter some delay. Use of the new release point is a more direct release path for some of the material into the River.
This will lower concentrations in Lake Norman without materially changing the concentrations i.n 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 are not affected by the delay. Also in the low concentrations pennitted by the technical specifications the short lived materials are inconsequential.
p 4 The staff concludes that this proposed technical specification change is in accordance with release requirements of 10 CFR Part 50.35a, Part 50 Appendix I and 10 CFR 20 Appendix B; and in accordance with 10 CFR Part 50 Acoerdix A, General Design Criterion 64 requirements for menitoring radioactivity releases.
The change does not increase the licuid effluent release rates
- Thus, or the annual dose resulting from station liquid effluent releases.
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 detennined 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 Accordingly, the amendments treet has been no public comment on such finding.
the eligibility criteria for categorical exclusion set forth in 10 CFR Pursuant to 10 CFR 51.22(b) no environmental impact statement or 51.22(c)(9).
environmental assessment need be prepared in connection with the issuance of these amendments.
CONCLUSION f
The Comission made a proposed detennination that the amendments involve no significant hazards consideration which was published in the Feceral 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 consideration The Comission consulted with the state of North Carolina. No determination.
public coments were received, and the state of North Carolina did not have any Coff7 Dents.
(1)
We have concluded, based on the considerations discussed above, that:
there is reasonable assurance that the health and safety of the public will not be 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 defens security or to the health and safety of the public.
Principal Contributors:
D. Hood, PD#11-3 C. Willis, PRPB Cated:
June 5,1987