GNRO-2002/00033, 2001 Annual Radioactive Effluent Release Report (ARERR)

2001 Annual Radioactive Effluent Release Report (ARERR)

ML021150807
Person / Time
Site:	Grand Gulf
Issue date:	04/22/2002
From:	Bottemiller C Entergy Operations
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
GNRO-2002/00033, TS 5.6.3
Download: ML021150807 (215)

Text

nter erati 6.

Waterloo Road P.O. Box 756 Pot-l Gibson, MS 39150 Tel 601 437 6299 WkS er Manager Plant Licensinq April 22, 2002 U.S. Nuclear Regulatory Commission Washington, D.C. 20555 ATTENTION: Document Control Desk

SUBJECT:

2001 Grand Gulf Nuclear Station (GGNS) 2001 Annual Radioactive Effluent Release Report (ARERR)

Grand Gulf Nuclear Station Docket No. 50-416 License No. NPF-29 GNRO-2002100033 Gentlemen:

Attached is the GGNS Annual Radioactive Effluent Release Report (ARERR) for the period January 1, 2001 through December 31, 2001. This report is submitted in accordance with the requirements of 10CFR50.36a(a)(2) and the GGNS Technical Specification (TS) 5.6.3.

The ARERR also complies with the GGNS Offsite Dose Calculation Manual (ODCM).

If you have questions or require additional information concerning these reports, please contact Mr. B. D. Bryant at (601) 437-6316, or this office at (601) 437-6685. This letter does not contain any commitments.

Yours truly, CAB/M JL attachments: 2001 Annual Radioactive Effluent Release Report cc: (See Next Page)

April 22, 2002 GNRO-2002100033 Page 2 of 2 cc:

Hoeg T. L. (GGNS Senior Resident) (w/a>

Levanway D. E. (Wise Carter) (w/a>

Reynolds N. S. (w/a>

Smith L. J. (Wise Carter) (w/a)

/ Thomas 1 H. L. 1 I (w/o) I Mr. E. W. Merschoff (w/2) ALL LETTERS Regional Administrator U.S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011 U.S. Nuclear Regulatory Commission ALL LETTERS - U.S. POSTAL ATTN: Mr. S. P. Sekerak, NRR/DLPM (w/2) SERVICE MAIL DELIVERY ATTN: FOR ADDRESSEE ONLY ADDRESS ONLY ATTN: U.S. Postal Delivery Address Only Mail Stop 07Dl Washington, D.C. 205550001

January 1,200l-December 31,200l

TABLE OF CONTENTS SUBJECT PAGE I. INTRODUCTION 4 II. DETAILED INFORMATION 5 A. Regulatory Limits 5

1. 10CFR20 Limits 5

a. Fission and Activation Gases 5

b. Radioiodines and Particulates 5

c. Liquid Effluents 5

2. 10CFR50, Appendix I Limits 6

a. Fission and Activation Gases 6

b. Radioiodines and Particulates 6

c. Liquid Effluents 6

3. 40CFR190 Limits 7 B. Effluent Concentrations 7

1. Airborne 7

2. Liquid 7 C. Average Energy 7 D. Measurements and Approximations of Total Activity 8

1. For Fission and Activation Gases 8

2. For Particulates and Radioiodines 9

3. For Continuous Releases 9

4. For Batch Releases: Gases 9

5. For Batch Releases: Liquid Effluents 10 E. Batch Releases 10

1. Liquid 10

2. Gaseous 10 F. Unplanned Releases 11 I. Liquid 11

2. Gaseous II

TABLE OF CONTENTS (CONTD)

SUBJECT PAGE G. Estimate of Total Error 11

1. Liquid 11

2. Gaseous 12

3. Solid Radioactive Waste 12 H. Solid Radioactive Waste Shipments 12 I. Meteorological Data 12 J. Radioactive Effluent Monitoring Instrumentation Operability 12 K. Annual Sewage Disposal Summary 12 Ill. RADIATION DOSE

SUMMARY

13 A. Water-Related Exposure Pathway 13 B. Airborne-Related Exposure Pathway 13 IV. OFFSITE DOSE CALCULATION MANUAL/RADIOACTIVE WASTE TREATMENT SYSTEM CHANGES 15 A. Offsite Dose Calculation Manual (ODCM) 15 B. Radioactive Waste Treatment Systems 15 LIST OF TABLES PAGE IA Gaseous Effluents - Summation of All Releases 16 19 Gaseous Effluents - Elevated Releases 17 AC Gaseous Effluents - Ground-Level Releases - Continuous 18 1D Radioactive Gaseous Waste Sampling and Analysis Program 19 2A Liquid Effluents - Summation of All Releases 20 2B Liquid Effluents - Continuous and Batch Modes 21 2c Radioactive Liquid Waste Sampling and Analysis Program 22 3 Solid Radioactive Waste and Irradiated Fuel Shipments 23 LIST OF ATTACHMENTS PAGE Attachment I - Offsite Dose Calculation Manual, Revision 23 25 491 env-tedARERR0.i -3

I. INTRODUCTION This Annual Radioactive Effluent Release Report (ARERR) for the period of January 1 through December 31,ZOOl is submitted in accordance with Offsite Dose Calculation Manual (ODCM), Section 5.6.3 of Grand Gulf Nuclear Station (GGNS) License No. NPF-29.

The monitoring of radioactive effluents is referenced in ODCM Appendix A, Sections 6.11 and 6.12.

Airborne discharges at GGNS are considered ground-level releases. All liquid and airborne discharges to the environment were analyzed in accordance with ODCM requirements. All effluent releases were within the concentration and total release limits specified by the ODCM. Projected offsite doses were within the dose limits specified by the ODCM.

The summation of all gaseous releases during the reporting period is given in Table IA, while elevated releases and ground-level releases are given in Tables 1 B and 1 C, respectively. Table 1 D describes the radioactive gaseous sampling and analysis program implemented at GGNS.

The summation of all liquid releases during the reporting period is given in Table 2A, while continuous and batch mode releases are given in Table 28. Table 2C describes the radioactive liquid waste sampling and analysis program implemented at GGNS.

Solid radioactive waste and irradiated fuel shipments during the reporting period are summarized in Table 3.

The annual summary of meteorological data (ioint frequency distribution) will be maintained on site in a file that shall be provided to the Nuclear Regulatory Commission (NRC) upon request. The option to maintain meteorological data on site is in accordance with ODCM Administrative Controls Section 5.6.3.

II. DETAILED INFORMATION A. Regulatory Limits

1. 1 OCFRZO Limits

a. Fission and Activation Gases - The release rate limit at any time for noble gases to areas at or beyond the site boundary shall be such that:

& = average total body dose rate in the current year (mremlyr)

= XIQ Zi Ki Q i < 500 mremlyr DS = average skin dose rate in the current year (mrem/yr)

= XIQ Xi (L, + 1 .I Mi ) Q i 5 3000 mremlyr where the terms are defined in the GGNS ODCM.

b. Radioiodines and Particulates - The release rate limit for the sampling period for all radioiodines, tritium and radioactive materials in particulate form with half-lives greater than 8 days shall be such that:

D, = average organ dose rate in current year (mremlyr)

= Ci W Pi 5, < 1500 mremlyr where the terms are defined in the GGNS ODCM.

C. Liquid Effluents - The concentration of radioactive materials released in liquid effluents to unrestricted areas from the site shall not exceed at any time ten times the values specified in 1 OCFR20, Appendix B, Table 2, Column 2. The concentration of dissolved or entrained noble gases, released in liquid effluents to unrestricted areas from all reactors at the site, shall be limited to 2 x 1 Oe4microcurieslml total activity.

II. DETAILED INFORMATION (CONTD)

2. IOCFRSO, Appendix I Limits

a. Fission and Activation Gases - The dose from noble gases in gaseous effluents to areas at or beyond the site boundary shall be such that:

Dy = air dose due to gamma emissions from noble gases

= 3.17 x 10. Zi Mi XIQ Qi 5 5 mradlqtr 2 IO mradlyr

= air dose due to beta emissions from noble gases DP

= 3.17 x 1 O-8Ci Ni XIQ Q, c 10 mradlqtr I 20 mradlyr where the terms are defined in the GGNS ODCM.

b. Radioiodines and Particulates - The dose to an individual from tritium, l-l 31, I-l 33 and radioactive material in particulate form with half-lives greater than 8 days in gaseous effluents shall be such that:

D,= dose to an individual from tritium, l-l 31, l-l 33 and radionuclides in particulate form with half-lives greater than 8 days (mrem)

= 3.17 x 1 O-*Xi Ri w Qi < 7.5 mremlqtr Any Organ 5 15 mrem/yr Any Organ where the terms are defined in the GGNS ODCM.

c. Liquid Effluents - The dose from radioactive materials in liquid effluents shall be such that:

m DTau = c [AiTau C At, Ci, F, ] 2 1.5 mremlqtr Total Body i I=1 5 5 mremlqtr Any Organ 2 3 mremlyr Total Body 2 10 mremlyr Any Organ where the terms are defined in the GGNS ODCM.

Il. DETAILED INFORMATION (CONTD)

3. 4OCFRl90 Limits Doses are calculated for Fission and Activation Gases; Radioiodines and Particulates; and Liquid Effluents according to equations contained in Sections 2.(a), (b), and (c) respectively, with the exception that the limits applied are:

525 mremlyr, Total Body or any Organ except Thyroid 275 mrem/yr, Thyroid 110 mrad ylqtr or r20 mrad ylyr, Fission and Activation Gases 220 mrad Plqtr or 540 mrad P/yr, Fission and Activation Gases 515 mremlqtr or 530 mrem/yr, any Organ, Iodine and Particulates 23 mremlqtr or 56 mrem/yr, Total Body, Liquid Effluents

= 8 days 1 1. Total Release Ci 1.583-05 7.393-06 8.503-06 1.29'3-06 3.303-05 1 II 3.

2. Average Percent Release of TS LimitRate uCi/sec

% 2.10E-04 2.043-06 2.733-04 9.393-07 1.483-04 l.O7E-06 7.743-08 1.633-07 2.51E-04 l.O5E-06 II Tritium II

1. Total Release Ci 2.24E+Ol 1.65E+Ol 1.72E+Ol 2.06E+Ol 7.683+01

2. Average Release Rate uCi/sec 2.883+00 2.10E+OO 2.17E+OO 2.60E+OO 2.44E+OO

3. Percent of TS Limit  % 4.22E-01 3.11E-01 3.243-01 3.883-01 7.23E-01 Gross Alwha Radioactivitv II 2.

1. Average Total Release Release Rate uCi/sec Ci 2.243-10 1.743-09 O.OOE+OO O.OOE+OO 2.033-09 1.61E-08 5.663-10 1.783-08 II

TABLE IB ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - ELEVATED RELEASES JANUARY - DECEMBER 2001 (Not Applicable - GGNS Releases Are Considered Ground-Level)

TABLE 1 C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT GASEOUS EFFLUENTS - GROUND-LEVEL RELEASE-CONTINUOUS REPORT FOR 2001 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR

_____------------- ----- ------- e-v----- _------- -------- -------- --------

Fission and Activation Gases AR-41 Ci 5.673-03 5.863-02 1.67E-01 O.OOE+OO 2.323-01 RR-85M Ci O.OOE+OO 1.01E-03 O.OOE+OO O.OOE+OO l.OlE-03 KR-87 Ci O.OOE+OO 4.293-03 O.OOE+OO O.OOE+OO 4.293-03 RR-88 Ci 1.33E-01 1.88E-01 3.883-01 2.06E-01 9.16E-01 XE-133 Ci 3.133+00 4.40E+OO 9.1OE+OO 4.843+00 2.15E+Ol m-135 Ci 2.993+00 4.21E+OO 8.71E+OO 4.633+00 2.05E+Ol XE-135M Ci 3.533-01 5.01E-01 1.033+00 5.463-01 2.433+00 XE-138 Totals for Period.....

Ci Ci 8.01E-02 6.693+00 Iodines 1.50E-01 9.51E+OO 3.773-01 1.98E+Ol 1.24E-01 l.O3E+Ol 7.323-01 4.633+01 1

I-131 Ci O.OOE+OO 3.923-05 4.303-05 O.OOE+OO 8.223-05 I-132 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO I-133 Ci 5.08E-06 1.733-05 9.39E-06 O.OOE+OO 3.183-05 I-135 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO Totals for Period..... Ci 5.083-06 5.65E-05 5.24E-05 O.OOE+OO l.l4E-04 Particulates Half Life >= 8 days CO-58 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO CO-60 Ci O.OOE+OO 1.333-06 8.193-07 O.OOE+OO 2.143-06 CR-51 Ci 1.493-05 4.123-06 5.383-06 1.293-06 2.573-05 cs-137 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO FE-59 Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO MN-54 Ci O.OOE+OO 1.493-06 2.30E-06 O.OOE+OO 3.793-06 RU-106 Ci 9.133-07 4.503-07 O.OOE+OO O.OOE+OO 1.363-06 Totals for Period..... Ci 1.583-05 7.39E-06 8.503-06 1.293-06 3.303-05 Tritium H-3 Ci 2.24E-k01 1.65E+Ol 1.72E+Ol 2.063+01 7.683+01 Totals for Period..... Ci 2.243+01 1.65E+Ol 1.72E+Ol 2.06E+Ol 7.683+01 Gross Alpha Radioactivity ALPHA Ci 1.743-09 O.OOE+OO O.OOE+OO 1.61E-08 1.783-08 Totals for Period..... Ci 1.743-09 U.UOE+OO O.OOE+00 1.61E-08 1.7832-08 I

TABLE 1 D ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT Radioactive Gaseous Waste Sampling and Analysis Program JANUARY-DECEMBER 2001 Lower Limit Sampling Minimum Analysis Type of Activity of Detection Gaseous Release Type Frequency Frequency Analysis

( j%l, 9

4. (1) Radwaste Building 31 Days 31 Days Principal Gamma Ventilation Exhaust Grab Sample (f) Emitters (b,e) 1x104 H-3 1X10 (2) Fuel Handling Area Continuous 7 Days (c) l-l 31 1x1 O-l2 Ventilation Exhaust NW-I Charcoal Sample l-l 33 1xlo-o (3) Containment Continuous 7 Days (c) Principal Gamma 1x10-Ventilation Exhaust W)(f) Particulate Emitters (e) (l-l 31, Sample Others)

(4) Turbine Building Continuous 31 Days Gross Alpha 1x10-Ventilation Exhaust WQ Composite Particulate Sample Continuous 92 Days Sr-89, Sr-90 1x10-W)(f) Composite Particulate Sample Continuous (f) Noble Gas Noble Gases Gross 1xl o-6 Monitor Beta or Gamma B. (1) Offgas Post 31 Days Grab 31 Days Principal Gamma lx104 Treatment Exhaust, Sample (f) Emitters (e) whenever there is flow (2) Standby Gas 31 Days Grab 31 Days Principal Gamma lx104 Treatment A Sample (f) Emitters(e)

Exhaust, whenever there is flow (3) Standby Gas 31 Days Grab 31 Days Principal Gamma 1x10 Treatment B Sample (f) Emitters(e)

Exhaust, whenever there is flow NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.4-I

TABLE 2A ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT I RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - SUMMATION OF ALL RELEASES REPORT FOR 2001 Units QTR 1 QTR 2 QTR 3 QTR 4 YEAR

______----------- ------ ------- -m-w---- __------ -------- -------- --------

Fission and Activation Products II 1. Total Release Ci 1.283-03 8.453-03 1.383-02 1.20E-02 3.553-02 1

3. Avg.

2. PercentDiluted of Limit Cont.  %

uCi/ml 2.843-02 3.673-08 5.993-01 3.623-08 3.643-01 7.043-08 4.933-01 2.243-07 5.99E-01 6.863-08 II Tritium

1. Total Release Ci 6.233+00 3.09E+Ol 1.70E+Ol 6.353+00 6.043+01

2. Avg. Diluted Cont. uCi/ml 1.793-04 1.323-04 8.683-05 l.l8E-04 1.17E-04

3. Percent of Limit  % 1.79E+OO 1.32E+OO 8.683-01 1.18E+OO l.l7E+OO Dissolved and Entrained Gases

1. Total Release Ci O.OOE+OO 2.393-05 O.OOE+OO l.O7E-05 3.463-05

2. Avg. Diluted Cont. uCi/ml O.OOE+OO l.O2E-10 O.OOE+OO 1.99E-10 6.683-11

3. Percent of Limit  % O.OOE+OO 5.10E-05 O.OOE+OO 9.953-05 3.343-05 Gross Alpha Radioactivity

1. Total Release Ci O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO volume of liquid waste liters 3.913+05 2.393+06 1.753+06 6.203+05 5.15E+06 Volume of dil. water liters 3.453+07 2.313+08 1.943+08 5.313+07 5.123+08

TABLE 2B ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT LIQUID EFFLUENTS - CONTINUOUS AND BATCH MODES REPORT FOR 2001 units QTR I. QTR 2 QTR 3 QTR 4 YEAR

________--------~~~~~~~ ------- -------- -------- -------- __------ _-------

Fission and Activation Products AS-76 Ci O.OOE+OO 6.203-06 O.OOE+OO O.OOE+OO 6.203-06 CO-58 Ci O.OOE+OO 7.463-05 7.00E-05 1.423-04 2.873-04 CO-60 Ci 4.513-05 2.693-03 6.703-04 1.86E-03 5.273-03 CR-51 Ci 2.673-04 2.433-03 9.76$-03 3.193-03 1.563-02 cs-137 Ci O.OOE+OO 1.883-05 4.983-05 O.OOE+OO 6.863-05 cu-64 Ci O.OOE+OO 1.51E-05 O.OOE+OO O.OOE+OO 1.51E-05 FE-55 Ci 9.693-04 6.223-04 2.863-03 2.913-03 7.363-03 FE-59 Ci O.OOE+OO l.l8E-03 4.163-05 5.203-04 1.743-03 I-131 Ci O.OOE+OO 4.253-06 O.OOE+OO O.OOE+OO 4.253-06 MN-54 Ci O.OOE+OO 8.543-04 2.243-04 3.203-03 4.273-03 NH-95 Ci O.OOE+OO O.OOE+OO O.OOE+OO l.l5E-05 l.l5E-05 SB-124 Ci O.OOE+OO O.OOEtOO O.OOEtOO 9.021-06 9.023-06 ZN-65 Ci O.OOE+OO 5.483-04 7.803-05 1.543-04 7.803-04 ZN-69M Ci O.OOE+OO 8.903-06 8.653-06 2.11E-05 3.873-05 Totals for Period..... Ci 1.283-03 8.453-03 1.383-02 1.20E-02 3.553-02 Tritium H-3 Ci 6.233+00 3.09E+Ol 1.70E+Ol 6.353+00 6.04E+Ol Totals for Period..... Ci 6.23E+OO 3.09E+Ol 1.70E+Ol 6.353+00 6.04E+Ol Dissolved and Entrained Gases Totals for Period.....

Gross Alpha Radioactivity

• • No Nuclide Activities** O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO O.OOE+OO

TABLE 2C ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT RADIOACTIVE LIQUID WASTE SAMPLING AND ANALYSIS PROGRAM JANUARY-DECEMBER 2001 Lower Limit Sampling Minimum Analysis Type of Activity of Detection Llquld Release Type Frequency Frequency Analysis W-D)

( @i/ml)(a)

A. Batch Waste Release Prior to Release Prior to Release Principal Gamma Tanks (c) Each Batch Each Batch Emitters (d) 5x1 o-7 I-1 31 1X10" Prior to 31 Days Dissolved and 1xl O!j Release One Entrained Gases Batch IM (Gamma Emitters)

Prior to 31 Days ji-zJ 1xlo5 Release Each Composite (b) Gross Alpha 1 xl o-7 Batch Prior to 92 Days Sr-89. Sr-90 5x10" Release Each Composite (b) Fe-55 1xl o-"

Batch B. SSW Basin (Before Blowdown) Prior to Prior to Release Principal Gamma Release Each Each Batch Emitters (d) 5x1 o-7 Blowdown l-l 31 1x10~

NOTE: Footnotes indicated are listed in GGNS ODCM, Appendix A, Table 6.11.1-I.

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS JANUARY-DECEMBER 2001 A. Solid Waste Shipped Offsite for Burial or Disposal

1. TYPE OF WASTE 2NDQTR 3RDQTR 4THQTR TOTAL ERROR (%)

a. RESIN M3 1.75E+Ol 1.42E+Ol 7.23E+Ol 155E+Ol

\ _\ *Ci 592E+Ol 542E+Ol 4.44E+Ol 2.71 E+Ol 7.2E+Ol hu. I-iAW Y#-B..

M3 w..

4. ..,.v-c;8F+nn -- 7 7fIF+OO

-.--- 6.43E+OO 8.1 OE+OO I

1 *Ci 1 6.40E-02 1 1.21E +oo 1.27E+OO 1.94E+OO 6.9E+Ol

c. IRR

..\I..

CY-WID VVI.I. .

I I

M3 I.,

I I

NtWlfA

. ..r. ..s I

I NAtlc?

I Nnnn I

None I *Ci None I None I None I None I N/A II I: I II a-l

-. nTUFR

-...-*. I I

M3

..* I I

Nntl0

.--..- I NfWW

._-..- I NntlG!

.-..- I None

• Ci None I None I None I None I N/A

• Total curie quantity determined by measurement. Total volume used is burial container volume. Resin and DAW solid waste was Class A as defined by 1 OCFR Part 61.

2. Estimate of major nuclide composition (by type of waste as identified above) 8 12 12 12 65 75 68 70 5 4 12 15

<I 3 3 1 4 3 1 :I 12 3 2 1 ALL OTHERS Ill <I cl <I Nuclide 1 StQTR 2nd QTR 3rd QTR 4 QTR Co-60 10 10 11 11 H-3 3 4 4 <I Fe-55 83 84 84 84 Mn-54 4 4 4 4 I All nthnrr c-l 3 1 1

c. IRR. CCMP.

II Nuclide

. ---..-- I _...

1 StQTR I 2nd QTR I 3rd QTR Co-60 N/A N/A N/A N/A Ni-63 N/A N/A N/A NIA Fe-55 N/A N/A N/A N/A Mn-54 N/A N/A N/A N/A All Others N/A N/A N/A N/A

d. OTHER Nuclide 1 st QTR 2nd QTR 3rd QTR 4th QTR N/A N/A NIA N/A NIA

TABLE 3 ENTERGY OPERATIONS, INC.

GRAND GULF NUCLEAR STATION UNIT 1 RADIOACTIVE EFFLUENT AND WASTE DISPOSAL ANNUAL REPORT SOLID RADIOACTIVE WASTE AND IRRADIATED FUEL SHIPMENTS (CONTD)

JANUARY-DECEMBER 2001 A. Solid Waste Shipped Off Site for Burial or Disposal

3. Solid Waste Disposition

a. Some resins were dewatered in High Integrity Containers aooording to the requirements of the GGNS Process Control Program and shipped to Barnwell, South Carolina, for burial. Most resin was shipped to Allied Technologies Group (ATG) of Oak Ridge, Tennessee or Studsvik, LLC. of Erwin, Tennessee for volume reduction prior to burial.

ATG and Studsvik shipped waste to Barnwell, South Carolina or Envirocare of Utah. Resin was dewatered and shipped in steel liners and High Integrity Containers. No solidification agents or absorbents were used.

b. Dry Active Waste (DAW) was packaged in 20 sealand containers or metal B-25 boxes and shipped to Duratek of Oak Ridge, Tennessee for volume reduction. Duratek shipped reduced waste to Barnwell, South Carolina or Envirocare of Uta h. Reduced volume was used in providing information given in A.1 .b.

C. No waste in this category.

d. No waste in this category.

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION 25 Truck Barnwell, SC 68 Truck Envirocare, UT B. Irradiated Fuel Shipments (Disposition)

/

NUMBER OF SHIPMENTS MODE OF TRANSPORTATION DESTINATION None N/A N/A

c. Annual Sewage Sludge Summary No sewage sludqe was shipped during the reporting period.

/

NUMBER OF AVERAGE Co-60 AVERAGE Mn-54 AVERAGE Cs-137 SHIPMENTS TOTAL GALLONS ACTIVITY (pCi/kg) ACTIVITY (pCi/kg) ACTIVITY (pCi/kg)

None N/A N/A N/A N/A em-tec/ARERROf - 24

ATTACHMENT I OFFSITE DOSE CALCULATION MANUAL REVISION 23

OFFSITE DOSE CALCULATION MANUAL GRAND GULF NUCLEAR STATION GRANDGULF, UNIT I. Revision 23 - 03/01