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{{#Wiki_filter:e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 28, 1992 United States Nuclear Regulatory Commission                   Serial No. 92-122 Attention: Document Control Desk                             NURPC Washington, D. C. 20555                                       Docket Nos. 50-280 50-281 72-2 License Nos. DPR-32 DPR-37 SNM-2501 Gentlemen:
* VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 28, 1992 United States Nuclear Regulatory Commission Attention:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Surry Power Station Semi-Annual Radioactive Effluent Release Report for January 1, 1991 through June 30, 1991. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.B.3 and ISFSI Technical Specification 1 .4.1 of Appendix C, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the previous six months, as outlined in Regulatory Guide 1.21, Revision 1, June 1974.
Document Control Desk Washington, D. C. 20555 Gentlemen:
Very truly yours,
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 Serial No. 92-122 NURPC Docket Nos. 50-280 50-281 72-2 License Nos. DPR-32 DPR-37 SNM-2501 INDEPENDENT SPENT FUEL STORAGE INSTALLATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Surry Power Station Semi-Annual Radioactive Effluent Release Report for January 1, 1991 through June 30, 1991. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.B.3 and ISFSI Technical Specification 1 .4.1 of Appendix C, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the previous six months, as outlined in Regulatory Guide 1.21, Revision 1, June 1974. Very truly yours, l ~-11"'\., ) .\) l \ --1../\], '-,/ \~\l+/- W. L. Stewart Senior Vice President  
              ~ l
-Nuclear Attachment cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Mr. Robert M. Bernero, Director Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission  
          ) .\) l 1../\], '-
,--Washington, D. C. 20555 ' 9203050144 920228 1 PDR ADOCK 05000280 I R PDR )
W. L. Stewart
--SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY 1, 1991 THRU D~ 31, 1991 REC'D W/LTR D'I'D 02/28/92 *.*. 9203050144. -NOTICE-THE A TT ACHED FILES ARE OFFICIAL CORDS OF THE RECORDS & REPORTS MANAGEMENT BRANCH. THEY HAVE 'BEEN
                            \~\l+/-
* CHARGED TO YOU' FOR A LIMITED TIME .. -PERIOD AND MUST BE RETURNED TO THE RECORDS & ARCHIVES SERVICES SECTION P1-122 WHITE FLINT. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE (S) FROM DOCUMENT FOR DUCTION MUST BE REFERRED TO FILE PERSONNEL. -NOTICE-  
                      ~-11"'\.,
*
                      ~ ,/ \  --
* SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION (July 1, 1991 Through December 31, 1991) Prepared By: ~~.f.~-f-Supervisor Radiological Analysis Reviewed By: d. ;?'" /. ,#....L__
Senior Vice President - Nuclear Attachment cc:         U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.
Supervis Health Plbtysics Technical Services Approved By: 0~ Superintendent Radiological Protection FORWARD This report is submitted as required by Appendix A to Operating License No.'s DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket No.'s 50-280, 50-281, Section 6.6.B.3. and as required by Appendix C to Materials License No. SNM-2501, Technical Specifications for Environmental Protection for Surry Independent Spent Fuel Storage, Docket No. 72-2, Section 1.4.1.
Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Mr. Robert M. Bernero, Director Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission
Section No. 1 2 3 RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (July I, 1991 Tl!nrough December 31, 1991) Index Subject Purpose and Scope Page 1 Discussion Supplemental Information Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3 Revisions to Offsite Dose Calculation Manual (ODCM) Attachment 4 Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Attachment 5 Inoperability of Radioactive Liquid and Gaseous Effluent Instrumentation Attachment 6 Unplanned Releases Attachment 7 Lower Level of Detection (LLD) for Effluent Analysis 1&2 2 Page 1 of 2  
  ,--                 Washington, D. C. 20555
'     9203050144 920228 PDR ADOCK 05000280 1  I R                         PDR     )
 
SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY 1, 1991 THRU D ~ 31, 1991 REC'D W/LTR D'I'D 02/28/92 *.*. 9203050144.
                    -NOTICE-THE A TTACHED FILES ARE OFFICIAL RE-CORDS OF THE RECORDS & REPORTS MANAGEMENT BRANCH. THEY HAVE 'BEEN
* CHARGED TO YOU' FOR A         LIMITED TIME .. -
PERIOD AND MUST BE RETURNED TO THE RECORDS & ARCHIVES SERVICES SECTION P1-122 WHITE FLINT.       PLEASE DO NOT SEND   DOCUMENTS         CHARGED     OUT THROUGH THE MAIL.       REMOVAL OF ANY PAGE (S) FROM DOCUMENT FOR REPRO-DUCTION MUST BE REFERRED TO FILE PERSONNEL.
                  -NOTICE-
 
SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION (July 1, 1991 Through December 31, 1991)
* Prepared By: ~~.f.~-f-Supervisor Radiological Analysis Reviewed By: d. ;?'" /.,#....L__
Supervis Health Plbtysics Technical Services Approved By: 0             ~
Superintendent Radiological Protection
 
FORWARD This report is submitted as required by Appendix A to Operating License No.'s DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket No.'s 50-280, 50-281, Section 6.6.B.3. and as required by Appendix C to Materials License No.
SNM-2501, Technical Specifications for Environmental Protection for Surry Independent Spent Fuel Storage, Docket No. 72-2, Section 1.4.1.
 
RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (July I, 1991 Tl!nrough December 31, 1991)
Index Section No.        Subject                                               Page 1
1              Purpose and Scope 1&2 2              Discussion 2
3              Supplemental Information Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3     Revisions to Offsite Dose Calculation Manual (ODCM)
Attachment 4     Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Attachment 5 Inoperability of Radioactive Liquid and Gaseous Effluent Instrumentation Attachment 6     Unplanned Releases Attachment 7     Lower Level of Detection (LLD) for Effluent Analysis
 
Page 1 of 2


==1.0 Purpose and Scope==
==1.0 Purpose and Scope==
The Radioactive Effluent Release Report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, 11 Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 11 , Revision 1, June 1974, with data summarized on a quarterly basis following the format of Tables 1, 2 and 3 of Appendix B thereof. The report submitted within 60 days after January 1 of each year includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. The report also includes a list of unplanned releases during the reporting period. As required by Technical Specification 6.8B, changes to the ODCM for the time period covered by this report are included.
 
Information is provided to support the changes along with a package of those pages of the ODCM changed. Major changes to the radioactive liquid, gaseous and solid waste treatment systems are required to be reported in accordance with Technical Specification 6.9. If changes are made to these systems, the report shall include information to support the reason for the change and a summary of the 1 OCFR50.59 evaluation.
The Radioactive Effluent Release Report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, 11 Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 11 , Revision 1, June 1974, with data summarized on a quarterly basis following the format of Tables 1, 2 and 3 of Appendix B thereof. The report submitted within 60 days after January 1 of each year includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. The report also includes a list of unplanned releases during the reporting period.
In lieu of reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of the annual FSAR update. As required by the ODCM, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitors are provided in this report. 2.0 Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table lA of Attachment 1, is the ODCM section 6.3.l which requires that the dose rate for iodine -131, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mRem/yr to the critical organ at or beyond the site boundary.
As required by Technical Specification 6.8B, changes to the ODCM for the time period covered by this report are included. Information is provided to support the changes along with a package of those pages of the ODCM changed.
The critical organ is the child's thyroid, inhalation pathway. The basis for the calculation of percent of technical specification for the total body and skin in Table lA of Attachment 1, is the ODCM section 6.3.1 which requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal to 500 mRem/yr to the total body and less than or equal to 3000 mRem/yr to the skin. The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1, is the ODCM section 6.2.1 which states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 1 OCFR20, Appendix B, Table II, Column 2 . for radionuclides*
Major changes to the radioactive liquid, gaseous and solid waste treatment systems are required to be reported in accordance with Technical Specification 6.9. If changes are made to these systems, the report shall include information to support the reason for the change and a summary of the 1 OCFR50.59 evaluation. In lieu of reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of the annual FSAR update.
other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 X 10-4 microcuries/ml.
As required by the ODCM, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitors are provided in this report.
* Page 2 of 2 Percent of technical specification calculations are based on the total gaseous or liquid effluents released for that respective quarter. The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at the site boundary.
2.0 Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table lA of Attachment 1, is the ODCM section 6.3.l which requires that the dose rate for iodine - 131, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mRem/yr to the critical organ at or beyond the site boundary. The critical organ is the child's thyroid, inhalation pathway.
The maximum exposed member of the public from the release of airborne iodine -131, tritium and all radionuclides in particulate form with half lives greater than 8 days, is defined as an infant, exposed through the grass-cow-milk pathway, with the critical organ being the thyroid gland. The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas is defined as an adult, exposed by either the invertebrate or fish pathway, with the critical organ being either the thyroid gland or gastrointestinal-lower large intestine.
The basis for the calculation of percent of technical specification for the total body and skin in Table lA of Attachment 1, is the ODCM section 6.3.1 which requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal to 500 mRem/yr to the total body and less than or equal to 3000 mRem/yr to the skin.
The total body dose was also determined for this individual.
The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1, is the ODCM section 6.2.1 which states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 1 OCFR20, Appendix B, Table II, Column 2 . for radionuclides* other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 X 10-4 microcuries/ml.
 
Page 2 of 2 Percent of technical specification calculations are based on the total gaseous or liquid effluents released for that respective quarter.
The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at the site boundary. The maximum exposed member of the public from the release of airborne iodine - 131, tritium and all radionuclides in particulate form with half lives greater than 8 days, is defined as an infant, exposed through the grass-cow-milk pathway, with the critical organ being the thyroid gland. The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas is defined as an adult, exposed by either the invertebrate or fish pathway, with the critical organ being either the thyroid gland or gastrointestinal-lower large intestine. The total body dose was also determined for this individual.
Presented in Attachment 6 is a list of unplanned gaseous and liquid releases exceeding the ODCM limits of sections 6.3.1 and 6.2.1 respectively.
Presented in Attachment 6 is a list of unplanned gaseous and liquid releases exceeding the ODCM limits of sections 6.3.1 and 6.2.1 respectively.
The typical lower level of detection (LLD) capabilities of the radioactive effluent analysis instrumentation are presented in Attachment
The typical lower level of detection (LLD) capabilities of the radioactive effluent analysis instrumentation are presented in Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volumes and maximum delay time prior to analysis). Actual LLD values may be lower. If an isotope is not detected when analyzing effluent samples, then the activity of that isotope will be reported as Not Detected (N/D) on Attachment 1 of this report. When all isotopes listed on Attachment 1 for a particular quarter and release mode are less than the lower level of detection, then the totals for this period will be designated as Not Applicable (N / A).
: 7. These LLD values are based upon conservative conditions (i.e., minimum sample volumes and maximum delay time prior to analysis).
3.0 Supplemental Information Section 6.5.1 of the ODCM requires the identification of the cause for the unavailability of milk or leafy vegetation samples, and identification for obtaining replacement samples.
Actual LLD values may be lower. If an isotope is not detected when analyzing effluent samples, then the activity of that isotope will be reported as Not Detected (N/D) on Attachment 1 of this report. When all isotopes listed on Attachment 1 for a particular quarter and release mode are less than the lower level of detection, then the totals for this period will be designated as Not Applicable (N / A). 3.0 Supplemental Information Section 6.5.1 of the ODCM requires the identification of the cause for the unavailability of milk or leafy vegetation samples, and identification for obtaining replacement samples. All milk and leafy vegetation samples were available for collection during the period of July 1, 1991 through December 31, 1991. Section 6.5.2 of the ODCM requires the identification of new sample locations determined with the Land Use Census as yielding a calculated dose or dose commitment greater than the values currently being calculated.
All milk and leafy vegetation samples were available for collection during the period of July 1, 1991 through December 31, 1991.
No new sample location(s) that may yield a greater dose or dose commitment than are currently used were identified in the Land Use Census. Dry Cask Independent Spent Fuel Storage Installation Technical Specification Appendix C, 1.4.1 requires reporting the quantity of each of the principal radionuclides released from the installation to the environment in liquid and gaseous effluents during the previous 6 months of operations.
Section 6.5.2 of the ODCM requires the identification of new sample locations determined with the Land Use Census as yielding a calculated dose or dose commitment greater than the values currently being calculated. No new sample location(s) that may yield a greater dose or dose commitment than are currently used were identified in the Land Use Census.
There were no liquid or gaseous effluent releases from the Dry ,Cask Independent Spent Fuel Storage Installation during the period of July 1, 1991 through December 31, 1991.
Dry Cask Independent Spent Fuel Storage Installation Technical Specification Appendix C, 1.4.1 requires reporting the quantity of each of the principal radionuclides released from the installation to the environment in liquid and gaseous effluents during the previous 6 months of operations. There were no liquid or gaseous effluent releases from the Dry
* Attachment 1 EFFLUENT RELEASE DATA (July 1, 1991 Through December 31, 1991) This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, Appendix B .
      ,Cask Independent Spent Fuel Storage Installation during the period of July 1, 1991 through December 31, 1991.
* TABLE lA Attachment 1 Page 1 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD QTR. FOURTH QTR. .t' EST. ERROR A. FISSION & ACTIVATION GASES 1. TOTAL RELEASE CI 2. AVG RELEASE RATE FOR PERIOD UCI/SEC B. IODINE 1. TOTAL I-131 CI 2. AVG RELEASE RATE FOR PERIOD UCI/SEC C. PARTICULATE
 
: 1. RALF-LIVES  
Attachment 1 EFFLUENT RELEASE DATA (July 1, 1991 Through December 31, 1991)
>8 DAYS CI 2 *. AVG RELEASE RATE FOR PERIOD UCI/SEC 3. GROSS ALPHA RADIOACTIVITY CI D. TRITIUM 1. TOTAL RELEASE CI 2. AVG RELEASE RATE FOR PERIOD UCI/SEC ENTAGE OF T. S. LIMITS CHIT ICAL ORGAN DOSE RA TE TOTAL BODY DOSE RATE SKIN DOSE RATE
This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, Appendix B.
* 1. 498 01 1.878 00 2. 27E-04 2.858-05 2.168-04 2.728-05 6.91E-07 4.63E 00 5.828-01 4.41E-03 9.248-02 2.30E-02 1.25E 00 1. 58E-01 6. 72E-05 8.468-06 1.02E-04 1.298-05 2. 78E-07 9.04E 00 1.148 00 5.638-03 6.858-04 2.0lE-04 1.80E 01 2.BOE 01 2.808 01 3. lOE 01 
 
---------~-----------
TABLE lA                 Attachment 1 Page 1 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2     UNIT     THIRD QTR. FOURTH QTR.     .t' EST. ERROR A. FISSION & ACTIVATION GASES
-------------------------
: 1. TOTAL RELEASE                   CI       1. 498 01    1.25E 00            1.80E 01
TABI,E lB Attachment 1 Page 2 of 7 EFFI,UENT ANO ff/ASTE DISPOSAl, SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 GASEOUS EFFI,UENTS-MIXEO-MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER 1. FISSION & ACTIVATION GASES KR-B5 CI N/D N/D N/D N/D KR-B5M CI N/0 N/0 1.22E-03 N/0 KR-B7 CI N/D N/0 N/D N/D KR-BB CI N/D N/D N/0 N/D XE-133 CI 5.03E-Ol 6.B9E-01 2.00E 00 N/0 XE-135 CI 9.96E-02 6.59E-02 9.65E-02 N/D XE-135M CI N/0 N/0 N/D N/D XE-13B CI N/D N/D N/D N/0 XE-131M CI N/D N/D 1.38E-02 N/D XE-133M CI N/D N/D 2.49E-02 N/0 AR-41 CI 7.04E-02 N/0 2.02E-03 N/0 TOTA!, FOR PERIOD CI 6. 73E-01 7.55E-01 2.14E 00 N/A 2. IODINES I-131 CI 4.32E-07 1.15E-07 3.13E-07 N/0 I-133 CI 2.42E-07 N/0 1.llE-07 N/D I-135 CI N/D N/0 N/D N/D I-132 CI N/D N/D N/D N/0 TOTA!, FOR PERIOD CI 6. 74E-07 l.15E-07 4.24E-07 N/A 3. PARTICUI,ATES SR-B9 CI N/D N/D N/D N/D SR-90 CI N/D N/0 N/D N/0 CS-134 CI N/0 N/D N/0 N/0 CS-137 CI 3.97E-08 1.17E-07 N/0 N/D BA-140 CI N/0 N/0 N/0 N/D I,A-140 CI N/0 N/0 N/D N/0 C0-60 CI 1.24E-07 l.lOE-07 N/D N/0 C0-58 CI N/0 5.82E-09 N/0 N/0 CS-138 CI N/0 N/0 N/0 N/D SE-75 CI B.59E-09 N/0 N/0 N/D RB-BB CI N/0 N/0 2.09E-05 N/D *
: 2. AVG RELEASE RATE FOR PERIOD UCI/SEC       1.878 00    1. 58E-01 B. IODINE
* TABLE lC Attachment 1 Page 3 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MODE BATCH MOOE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH QUARTER THIRD QUARTER FOURTH QUARTER 1. FISSION & ACTIVATION GASES KR-85 KR-85M KR-87 KR-88 XE-133 XE-135 XE-135M XE-138 XE-131M XE-133M AR-41 TOTAL FOR PERIOD 2. IODINES
: 1. TOTAL I-131                    CI       2. 27E-04    6. 72E-05          2.BOE 01
* I-131 I-133 I-135 I-132 TOTAL FOR PERIOD 3. PARTICULATES SR-89 SR-90 CS-134 CS-137 BA-140 LA-140 C0-60 C0-58 CS-138 SE-75 RB-88
: 2. AVG RELEASE RATE FOR PERIOD UCI/SEC       2.858-05    8.468-06 C. PARTICULATE
* QUARTER CI N/0 CI 1. 308-04 CI 1. 06E-04 CI 1.50E-04 CI 4.83E 00 CI 4.518-01 CI 7.568-03 CI 4.64E-04 CI 2.278-03 CI N/0 CI 6.66E 00 CI 1. 20E 01 CI 2.258-04 CI 2.98E-04 CI 2.14E-05 CI N/0 N/0 1.llE-04 2.92E-04 6.00E-04 3. 97E-Ol 7.llE-03 1.0BE-02 3. 278-04 N/0 N/0 2.85E-02 4.338-01 6.38E-05 1.658-04 N/0 N/0 N/0 N/0 N/0 N/0 9.57E-02 N/0 N/0 N/0 N/0 N/0 N/0 9.578-02 8.68E-07 4. lBE-08 N/0 N/0 N/0 N/0 N/0 N/0 6.59E-02 N/0 N/0 N/0 N/0 N/0 N/0 6.59E-02 3.28E-06 1.54E-07 N/0 1.24E-08 CI 5.448-04 2.29E-04 9.IOE-07 3.45E-06 CI CI CI CI CI CI CI CI CI CI CI N/0 N/0 5.96E-06 1.0lE-04 N/0 N/0 9. 758-05 1.llE-05 8.67E-05 N/D N/D N/0 N/0 4. 25E-07* 5.668-05 N/0 N/0 4.51E-05 N/0 4.06E-05 N/D N/0 N/0 N/0 N/0 2.46E-07 N/0 N/0 5.0BE-08 N/0 N/0 N/0 N/0 N/0 N/0 N/0 N/0 N/0 N/0 N/0 N/0 N/D N/0 N/0
: 1. RALF-LIVES >8 DAYS             CI       2.168-04    1.02E-04            2.808 01 2 *. AVG RELEASE RATE FOR PERIOD UCI/SEC     2.728-05    1.298-05
* TABLE 2A Attachment I Page 4 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD QTR. FOURTH QTR. .%' EST. ERROR A. FISSION AND ACTIVATION PRODUCTS 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CI 3.42E-01 1. 47E-02 2. OOE 01 2. AVG OIL. CONC. DURING PERIOD UCI/ML 5.89E-10 2.56E-11 3. PERCENT OF APPLICABLE LIMIT .%" l.55E-03 1.23E-04 B. TRITIUM 1. TOTAL RELEASE CI 2.03E 02 2. 74E 02 2. OOE 01 2. AVG OIL. CONC. DURING PERIOD UCI/ML 3.49E-07 4.76E-07 3. PERCENT OF APPLICABLE LIMIT .%" 1.16E-02 1.59E-02 c. DISSOLVED AND ENTRAINED GASES 1. TOTAL RELEASE CI 2.llE-02 2.59E-02 2. OOE 01 2. AVG OIL. CONC. DURING PERIOD UCI/ML 3.63E-11 4.50E-11 3. PERCENT OF APP LI CABLE LIMIT .%" 1.BlE-05 2.25E-05 ~ROSS ALPHA RADIOACTIVITY TOTAL RELEASE CI O.OOE-01 O.OOE-01 2. OOE 01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)
: 3. GROSS ALPHA RADIOACTIVITY       CI       6.91E-07    2. 78E-07 D. TRITIUM
LITERS 3.34E 07 2.85E 08 3.00E 00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 5.BlE 11 5. 76E 11 3.00E 00 * 
: 1. TOTAL RELEASE                   CI       4.63E 00    9.04E 00            3. lOE 01
-----TABLE 2B Attachment 1 Page 5 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER SR-89 CI N/D N/D N/D N/D SR-90 CI N/D N/D N/D N/D CS-134 CI N/D N/D 5.79E-03 2.43E-04 CS-137 CI 1.28E-02 l.09E-02 4.69E-02 2.09E-03 I-131 CI N/D N/D 4.19E-04 N/D C0-58 CI 4.0JE-08 N/D 2.20E-02 1.46E-04 C0-60 CI 2.lOE-04 2.59E-04 6.94E-02 3.94E-04 FE-59 CI N/D N/D 4.92E-04 N/D ZN-65 CI N/D N/D N/D N/D MN-54 CI N/D N/D 1.56E-03 6.54E-06 CR-51 CI N/D N/D 1.llE-02 N/D ZR-95 CI N/D N/D 6.09E-04 N/D NB-95 CI N/D N/D 2.55E-03 N/D M0-99 CI N/D N/D N/D N/D TC-99M CI N/D N/D N/D N/D BA-140 CI N/D N/D 4.87E-05 N/D LA-140 CI N/D N/D 7.03E-04 N/D CE-141 CI N/D N/D N/D N/D C0-57 CI N/D N/D 4.14E-05 N/D
: 2. AVG RELEASE RATE FOR PERIOD UCI/SEC       5.828-01    1.148 00 ENTAGE OF T. S. LIMITS CHITICAL ORGAN DOSE RA TE                     4.41E-03    5.638-03 TOTAL BODY DOSE RATE                         9.248-02    6.858-04 SKIN DOSE RATE                                2.30E-02    2.0lE-04
* SB-125 CI N/D N/D 8.31E-02 6.64E-04 AG-llOM CI N/D N/D 6. 71E-03 2.lBE-05 SB-124 CI N/D N/D 2.58E-03 N/D I-133 CI N/D N/D 3.53E-05 N/D RU-103 CI N/D N/D 4.96E-05 N/D TE-132 CI N/D N/D 6.0BE-06 N/D NA-24 CI N/D N/D 9.91E-06 N/D FE-55 CI N/D N/D 7.52E-02 N/D SR-92 CI N/D N/D N/D 7. 79E-06 TOTAL FOR PERIOD CI 1.30E-02 1.llE-02 3.29E-01 3.58E-03 XE-133 CI N/D 2.05E-02 1. 66E-02 5.46E-05 XE-135 CI N/D 5.358-03 4.42E-03 1.008-05 AR-41 CI N/D N/D 1.538-05 N/D X8-135M CI N/D N/D 3.65E-06 N/D
 
* Attachment 1 Page 6 of 7 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 07/01/91-12/31/91 SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL(Not irradiated fuel) 1. Type of waste Unit 6-month Est.Total Period Error,% a. Spent resins, filter sludges, evaporator m3 9.17E+OO l.OOE+Ol bottoms, etc. Ci l .56E+02 3.00E+Ol b. Dry compressible waste, contaminated m3 4.33E+02*
TABI,E lB                Attachment 1 Page 2 of 7 EFFI,UENT ANO ff/ASTE DISPOSAl, SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 GASEOUS EFFI,UENTS-MIXEO-MODE RELEASES CONTINUOUS MODE        BATCH MODE SURRY POWER STATION UNITS 1&2         UNIT      THIRD    FOURTH  THIRD      FOURTH QUARTER    QUARTER  QUARTER      QUARTER
l.OOE+Ol equip., etc. Ci 1.96E+OO 3.00E+Ol c. Irradiated components, control m3 O.OOE+OO O.OOE+OO rods, etc. Ci O.OOE+OO O.OOE+OO d. Organic waste(i.e.
: 1. FISSION & ACTIVATION GASES KR-B5                        CI      N/D        N/D      N/D          N/D KR-B5M                      CI      N/0        N/0  1.22E-03        N/0 KR-B7                        CI      N/D        N/0      N/D          N/D KR-BB                        CI      N/D        N/D      N/0          N/D XE-133                      CI  5.03E-Ol  6.B9E-01  2.00E 00        N/0 XE-135                      CI  9.96E-02  6.59E-02  9.65E-02        N/D XE-135M                      CI      N/0        N/0      N/D          N/D XE-13B                      CI      N/D        N/D      N/D          N/0 XE-131M                      CI      N/D        N/D  1.38E-02        N/D XE-133M                      CI      N/D        N/D  2.49E-02        N/0 AR-41                        CI  7.04E-02      N/0  2.02E-03        N/0 TOTA!, FOR PERIOD                    CI  6. 73E-01  7.55E-01 2.14E 00        N/A
oil and scintillation m3 O.OOE+OO O.OOE+OO e-fluid) Ci O.OOE-00 O.OOE+OO 2. Estimate of major nuclide composition(by type of waste) a. Co-60 QI 70 6.20E+Ol Fe-55 % 1.75E+Ol Ni-63 % 7.64E+OO Co-58 % 6.18E+OO Cs-137 % 4.27E+OO Cs-134 0/ l.26E+OO iO b. Co-60 % 3.04E+Ol Ni-63 % 2.90E+Ol Fe-55 % 2.86E+Ol Cs-137 % 1.05E+Ol Cs-134 % 1.39E+OO c. % d. % ---
: 2. IODINES I-131                        CI  4.32E-07  1.15E-07  3.13E-07        N/0 I-133                        CI  2.42E-07      N/0  1.llE-07        N/D I-135                        CI      N/D        N/0      N/D          N/D I-132                        CI      N/D        N/D      N/D          N/0 TOTA!, FOR PERIOD                    CI  6. 74E-07  l.15E-07  4.24E-07        N/A
* TABLE 3 Attachment 1 Page 7 of 7 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND ffiRADIATED FUEL SHIPMENTS PERIOD 07/01/91-12/31/91
: 3. PARTICUI,ATES SR-B9                        CI      N/D        N/D      N/D          N/D SR-90                        CI      N/D        N/0      N/D         N/0 CS-134                      CI      N/0        N/D       N/0         N/0 CS-137                      CI  3.97E-08  1.17E-07      N/0         N/D BA-140                      CI       N/0        N/0       N/0          N/D I,A-140                      CI       N/0        N/0      N/D         N/0 C0-60                        CI   1.24E-07  l.lOE-07      N/D          N/0 C0-58                        CI       N/0    5.82E-09      N/0          N/0 CS-138                      CI       N/0       N/0       N/0          N/D SE-75                        CI   B.59E-09      N/0      N/0          N/D RB-BB                        CI       N/0        N/0  2.09E-05        N/D
: 3. Solid Waste Disposition Number of Shipments 3 10 (continued)
 
Mode of Transportation Truck Truck Destination Barnwell, SC Oak Ridge, TN B. IRRADIATED FUEL SHIPMENT(Disposition)
TABLE lC                  Attachment 1 Page 3 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES SURRY POWER STATION UNITS 1&2    UNIT CONTINUOUS MODE THIRD QUARTER FOURTH QUARTER BATCH MOOE THIRD QUARTER FOURTH QUARTER
* Number of Shipments 0 Mode of Transportation Destination
: 1. FISSION & ACTIVATION GASES KR-85                    CI        N/0        N/0        N/0          N/0 KR-85M                    CI   1. 308-04  1.llE-04        N/0         N/0 KR-87                    CI   1. 06E-04  2.92E-04        N/0          N/0 KR-88                    CI    1.50E-04  6.00E-04        N/0          N/0 XE-133                    CI   4.83E 00  3. 97E-Ol  9.57E-02      6.59E-02 XE-135                    CI    4.518-01  7.llE-03        N/0          N/0 XE-135M                  CI   7.568-03  1.0BE-02        N/0          N/0 XE-138                    CI    4.64E-04  3. 278-04      N/0          N/0 XE-131M                  CI   2.278-03      N/0         N/0         N/0 XE-133M                  CI       N/0       N/0         N/0         N/0 AR-41                    CI   6.66E 00  2.85E-02        N/0         N/0 TOTAL FOR PERIOD                  CI   1. 20E 01  4.338-01  9.578-02      6.59E-02
*NOTE: Dry active waste was shipped to a licensed waste processor for volume reduction.
: 2. IODINES I-131                    CI   2.258-04  6.38E-05  8.68E-07      3.28E-06 I-133                    CI   2.98E-04  1.658-04  4. lBE-08    1.54E-07
Therefore,, this volume is not representative of the actual volume buried. The total volume of dry active waste buried for the reporting period was 5.00E+Ol m3.
* I-135 I-132 TOTAL FOR PERIOD CI CI CI 2.14E-05 N/0 5.448-04 N/0 N/0 2.29E-04 N/0 N/0 9.IOE-07 N/0 1.24E-08 3.45E-06
1st Quarter 2nd Quarter 3rd Quarter 4th Quarter Annual ANNUAL AND OUARTERL Y DOSES Attachment 2 Page 1 of 1 An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway is made pursuant to the ODCM, section 6.6.2 requirement.
: 3. PARTICULATES SR-89                    CI        N/0        N/0        N/0          N/0 SR-90                    CI        N/0        N/0        N/0          N/0 CS-134                    CI    5.96E-06  4. 25E-07*      N/0          N/0 CS-137                    CI    1.0lE-04  5.668-05 2.46E-07            N/0 BA-140                   CI        N/0        N/0        N/0          N/0 LA-140                   CI        N/0        N/0        N/0          N/0 C0-60                     CI    9. 758-05  4.51E-05 5.0BE-08            N/0 C0-58                    CI   1.llE-05      N/0        N/0          N/0 CS-138                    CI   8.67E-05  4.06E-05        N/0          N/D SE-75                    CI       N/D        N/D        N/0         N/0 RB-88                    CI       N/D        N/0         N/0         N/0
LIQUID GASEOUS Total Body Thyroid GI-LLI Gamma Beta Thyroid (mRem) (mRem) (mRem) (mRad) (mRad) (mRem) 5.35E-03 6.67E-05 1.71E-02 4.49E-05 l.09E-04 8.16E-04 8.54E-03 2.67E-04 5.32E-02 l.34E-02 2.57E-02 3.39E-03 1.20E-03 7.38E-05 9.30E-03 l.23E-01 5.37E-02 4.62E-03 l.42E-04 5.95E-05 9.07E-05 9.SOE-04 l.19E-03 1.59E-03 l.52E-02 4.67E-04 7.97E-02 l.37E-01 8.07E-02 1.04E-02 Attachment 3 Page 1 of 1 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)_ As required by Technical Specification 6.8.B, revisions to the ODCM, effective for the time period covered by this report, are synopsized in this attachment.
 
Revision 1 to the Virginia Power Offsite Dose Calibration Manual was effective July 01, 1991. Revision 2 to the Virginia Power Offsite Dose Calculation Manual was effective September 01, 1991. A copy of Revision 2 of the Offsite Dose Calculation Manual is attached.
TABLE 2A              Attachment I Page 4 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2    UNIT        THIRD QTR. FOURTH QTR.    .%' EST. ERROR A. FISSION AND ACTIVATION PRODUCTS
Changes made effective with Revision 1 and Revision 2 are indicated by marking the borders of the revised areas with the effective date of the change. All changes marked II Rev. l II were effective July O 1, 1991. All changes marked 11 Rev. 2 11 were effective September 01, 1991. Additionally, changes were made in the presentation of text. Effective with Revision 1, formulas or equations within the ODCM were assigned a number. Future references to the equation are made via this equation number. Also effective with Revision 1, words or phrases that were capitalized in Revisions 0, if they were defined by Technical Specifications, were un-capitalized.
: 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)        CI          3.42E-01    1. 47E-02         2. OOE 01
: 2. AVG OIL. CONC. DURING PERIOD UCI/ML        5.89E-10    2.56E-11
: 3. PERCENT OF APPLICABLE LIMIT    .%"        l.55E-03    1.23E-04 B. TRITIUM
: 1. TOTAL RELEASE                CI         2.03E 02    2. 74E 02          2. OOE 01
: 2. AVG OIL. CONC. DURING PERIOD UCI/ML      3.49E-07    4.76E-07
: 3. PERCENT OF APPLICABLE LIMIT    .%"        1.16E-02    1.59E-02
: c. DISSOLVED AND ENTRAINED GASES
: 1. TOTAL RELEASE                  CI          2.llE-02    2.59E-02          2. OOE 01
: 2. AVG OIL. CONC. DURING PERIOD UCI/ML        3.63E-11    4.50E-11
: 3. PERCENT OF APPLICABLE LIMIT    .%"        1.BlE-05    2.25E-05
~ROSS ALPHA RADIOACTIVITY TOTAL RELEASE                CI          O.OOE-01    O.OOE-01          2. OOE 01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)          LITERS      3.34E 07    2.85E 08          3.00E 00 F. VOLUME OF DILUTION WATER USED DURING PERIOD            LITERS      5.BlE 11    5. 76E 11          3.00E 00
 
TABLE 2B                Attachment 1 Page 5 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 LIQUID EFFLUENTS CONTINUOUS MODE        BATCH MODE SURRY POWER STATION UNITS 1&2     UNIT      THIRD  FOURTH    THIRD    FOURTH QUARTER    QUARTER  QUARTER      QUARTER SR-89                    CI      N/D      N/D      N/D          N/D SR-90                    CI       N/D      N/D      N/D          N/D CS-134                    CI      N/D      N/D  5.79E-03    2.43E-04 CS-137                    CI  1.28E-02 l.09E-02  4.69E-02     2.09E-03 I-131                    CI      N/D      N/D  4.19E-04          N/D C0-58                    CI   4.0JE-08      N/D  2.20E-02     1.46E-04 C0-60                    CI  2.lOE-04 2.59E-04  6.94E-02    3.94E-04 FE-59                    CI      N/D      N/D  4.92E-04          N/D ZN-65                    CI       N/D      N/D      N/D          N/D MN-54                    CI      N/D      N/D  1.56E-03    6.54E-06 CR-51                    CI      N/D      N/D  1.llE-02          N/D ZR-95                    CI      N/D      N/D  6.09E-04          N/D NB-95                    CI      N/D      N/D  2.55E-03          N/D M0-99                    CI      N/D      N/D      N/D          N/D TC-99M                    CI       N/D       N/D       N/D           N/D BA-140                    CI       N/D       N/D   4.87E-05          N/D LA-140                    CI       N/D       N/D   7.03E-04         N/D CE-141                    CI       N/D      N/D      N/D          N/D C0-57                    CI       N/D       N/D   4.14E-05          N/D SB-125                    CI       N/D      N/D   8.31E-02     6.64E-04
* AG-llOM SB-124 I-133 RU-103 TE-132 NA-24 CI CI CI CI CI CI N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D
: 6. 71E-03 2.58E-03 3.53E-05 4.96E-05 6.0BE-06 9.91E-06 2.lBE-05 N/D N/D N/D N/D N/D FE-55                    CI      N/D       N/D   7.52E-02          N/D SR-92                    CI       N/D       N/D       N/D       7. 79E-06 TOTAL FOR PERIOD                  CI  1.30E-02  1.llE-02 3.29E-01    3.58E-03 XE-133                    CI       N/D   2.05E-02 1. 66E-02    5.46E-05 XE-135                    CI       N/D   5.358-03 4.42E-03    1.008-05 AR-41                    CI      N/D       N/D   1.538-05          N/D X8-135M                  CI       N/D       N/D   3.65E-06          N/D
 
Attachment 1 Page 6 of 7 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 07/01/91-12/31/91 SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL(Not irradiated fuel)
: 1. Type of waste                                Unit      6-month    Est.Total Period      Error,%
: a. Spent resins, filter sludges, evaporator  m3        9.17E+OO    l.OOE+Ol bottoms, etc.                              Ci        l .56E+02  3.00E+Ol
: b. Dry compressible waste, contaminated      m3        4.33E+02*  l.OOE+Ol equip., etc.                              Ci        1.96E+OO    3.00E+Ol
: c. Irradiated components, control            m3        O.OOE+OO    O.OOE+OO rods, etc.                                 Ci        O.OOE+OO    O.OOE+OO
: d. Organic waste(i.e. oil and scintillation  m3        O.OOE+OO    O.OOE+OO e-fluid)                                    Ci        O.OOE-00    O.OOE+OO
: 2. Estimate of major nuclide composition(by type of waste)
QI
: a. Co-60                                      70        6.20E+Ol Fe-55                                      %        1.75E+Ol Ni-63                                      %        7.64E+OO Co-58                                      %         6.18E+OO Cs-137                                    %        4.27E+OO 0/
Cs-134                                    iO        l.26E+OO
: b. Co-60                                      %        3.04E+Ol Ni-63                                      %        2.90E+Ol Fe-55                                      %        2.86E+Ol Cs-137                                    %        1.05E+Ol Cs-134                                    %        1.39E+OO
: c.                                           %
: d. - - -                                      %
 
Attachment 1 Page 7 of 7
* TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND ffiRADIATED FUEL SHIPMENTS PERIOD 07/01/91-12/31/91 (continued)
: 3. Solid Waste Disposition Number of Shipments              Mode of Transportation    Destination 3                            Truck            Barnwell, SC 10                            Truck            Oak Ridge, TN B. IRRADIATED FUEL SHIPMENT(Disposition)
Number of Shipments            Mode of Transportation    Destination 0
    *NOTE: Dry active waste was shipped to a licensed waste processor for volume reduction. Therefore,, this volume is not representative of the actual volume buried. The total volume of dry active waste buried for the reporting period was 5.00E+Ol m3.
 
Attachment 2 Page 1 of 1 ANNUAL AND OUARTERLY DOSES An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway is made pursuant to the ODCM, section 6.6.2 requirement.
LIQUID                                            GASEOUS Total Body        Thyroid          GI-LLI          Gamma            Beta          Thyroid (mRem)          (mRem)            (mRem)          (mRad)          (mRad)         (mRem) 1st Quarter    5.35E-03        6.67E-05          1.71E-02      4.49E-05          l.09E-04        8.16E-04 2nd Quarter     8.54E-03        2.67E-04          5.32E-02        l.34E-02        2.57E-02        3.39E-03 3rd Quarter    1.20E-03        7.38E-05          9.30E-03        l.23E-01        5.37E-02        4.62E-03 4th Quarter    l.42E-04        5.95E-05          9.07E-05        9.SOE-04        l.19E-03        1.59E-03 Annual        l.52E-02        4.67E-04         7.97E-02        l.37E-01        8.07E-02       1.04E-02
 
Attachment 3 Page 1 of 1 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)_
As required by Technical Specification 6.8.B, revisions to the ODCM, effective for the time period covered by this report, are synopsized in this attachment.
Revision 1 to the Virginia Power Offsite Dose Calibration Manual was effective July 01, 1991.
Revision 2 to the Virginia Power Offsite Dose Calculation Manual was effective September 01, 1991.
A copy of Revision 2 of the Offsite Dose Calculation Manual is attached.
Changes made effective with Revision 1 and Revision 2 are indicated by marking the borders of the revised areas with the effective date of the change. All changes marked II Rev. l II were effective July O1, 1991. All changes marked 11 Rev. 2 11 were effective September 01, 1991.
Additionally, changes were made in the presentation of text. Effective with Revision 1, formulas or equations within the ODCM were assigned a number.
Future references to the equation are made via this equation number. Also effective with Revision 1, words or phrases that were capitalized in Revisions 0, if they were defined by Technical Specifications, were un-capitalized.
Punctuation, spelling and other grammatical errors were corrected in Revision 1 and Revision 2. These minor changes are not specifically identified, as they do not affect the text content. Page numbers were changed as required, to reflect the relocation of text by Revision 1 and Revision 2.}}
Punctuation, spelling and other grammatical errors were corrected in Revision 1 and Revision 2. These minor changes are not specifically identified, as they do not affect the text content. Page numbers were changed as required, to reflect the relocation of text by Revision 1 and Revision 2.}}

Latest revision as of 22:37, 2 February 2020

Forwards Semiannual Radioactive Effluent Release Rept for Jul-Dec 1991 & Rev 2 to Station Administrative Procedure VPAP-2103, Odcm.
ML18152A500
Person / Time
Site: Surry  Dominion icon.png
Issue date: 02/28/1992
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18151A413 List:
References
92-122, NUDOCS 9203050144
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Text

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 February 28, 1992 United States Nuclear Regulatory Commission Serial No.92-122 Attention: Document Control Desk NURPC Washington, D. C. 20555 Docket Nos. 50-280 50-281 72-2 License Nos. DPR-32 DPR-37 SNM-2501 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS 1 AND 2 INDEPENDENT SPENT FUEL STORAGE INSTALLATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Surry Power Station Semi-Annual Radioactive Effluent Release Report for January 1, 1991 through June 30, 1991. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.B.3 and ISFSI Technical Specification 1 .4.1 of Appendix C, includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released during the previous six months, as outlined in Regulatory Guide 1.21, Revision 1, June 1974.

Very truly yours,

~ l

) .\) l 1../\], '-

W. L. Stewart

\~\l+/-

~-11"'\.,

~ ,/ \ --

Senior Vice President - Nuclear Attachment cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, Georgia 30323 Mr. M. W. Branch NRC Senior Resident Inspector Surry Power Station Mr. Robert M. Bernero, Director Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission

,-- Washington, D. C. 20555

' 9203050144 920228 PDR ADOCK 05000280 1 I R PDR )

SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT JULY 1, 1991 THRU D ~ 31, 1991 REC'D W/LTR D'I'D 02/28/92 *.*. 9203050144.

-NOTICE-THE A TTACHED FILES ARE OFFICIAL RE-CORDS OF THE RECORDS & REPORTS MANAGEMENT BRANCH. THEY HAVE 'BEEN

  • CHARGED TO YOU' FOR A LIMITED TIME .. -

PERIOD AND MUST BE RETURNED TO THE RECORDS & ARCHIVES SERVICES SECTION P1-122 WHITE FLINT. PLEASE DO NOT SEND DOCUMENTS CHARGED OUT THROUGH THE MAIL. REMOVAL OF ANY PAGE (S) FROM DOCUMENT FOR REPRO-DUCTION MUST BE REFERRED TO FILE PERSONNEL.

-NOTICE-

SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION (July 1, 1991 Through December 31, 1991)

  • Prepared By: ~~.f.~-f-Supervisor Radiological Analysis Reviewed By: d. ;?'" /.,#....L__

Supervis Health Plbtysics Technical Services Approved By: 0 ~

Superintendent Radiological Protection

FORWARD This report is submitted as required by Appendix A to Operating License No.'s DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Units 1 and 2, Virginia Electric and Power Company, Docket No.'s 50-280, 50-281, Section 6.6.B.3. and as required by Appendix C to Materials License No.

SNM-2501, Technical Specifications for Environmental Protection for Surry Independent Spent Fuel Storage, Docket No. 72-2, Section 1.4.1.

RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (July I, 1991 Tl!nrough December 31, 1991)

Index Section No. Subject Page 1

1 Purpose and Scope 1&2 2 Discussion 2

3 Supplemental Information Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3 Revisions to Offsite Dose Calculation Manual (ODCM)

Attachment 4 Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Attachment 5 Inoperability of Radioactive Liquid and Gaseous Effluent Instrumentation Attachment 6 Unplanned Releases Attachment 7 Lower Level of Detection (LLD) for Effluent Analysis

Page 1 of 2

1.0 Purpose and Scope

The Radioactive Effluent Release Report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, 11 Measuring, Evaluating, and Reporting Radioactivity in Solid Wastes and Releases of Radioactive Materials in Liquid and Gaseous Effluents from Light-Water-Cooled Nuclear Power Plants 11 , Revision 1, June 1974, with data summarized on a quarterly basis following the format of Tables 1, 2 and 3 of Appendix B thereof. The report submitted within 60 days after January 1 of each year includes an assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site during the previous calendar year. The report also includes a list of unplanned releases during the reporting period.

As required by Technical Specification 6.8B, changes to the ODCM for the time period covered by this report are included. Information is provided to support the changes along with a package of those pages of the ODCM changed.

Major changes to the radioactive liquid, gaseous and solid waste treatment systems are required to be reported in accordance with Technical Specification 6.9. If changes are made to these systems, the report shall include information to support the reason for the change and a summary of the 1 OCFR50.59 evaluation. In lieu of reporting major changes in this report, major changes to the radioactive waste treatment systems may be submitted as part of the annual FSAR update.

As required by the ODCM, a list and explanation for the inoperability of radioactive liquid and/or gaseous effluent monitors are provided in this report.

2.0 Discussion The basis for the calculation of the percent of technical specification for the critical organ in Table lA of Attachment 1, is the ODCM section 6.3.l which requires that the dose rate for iodine - 131, for tritium, and for all radionuclides in particulate form with half-lives greater than 8 days shall be less than or equal to 1500 mRem/yr to the critical organ at or beyond the site boundary. The critical organ is the child's thyroid, inhalation pathway.

The basis for the calculation of percent of technical specification for the total body and skin in Table lA of Attachment 1, is the ODCM section 6.3.1 which requires that the dose rate for noble gases to areas at or beyond site boundary shall be less than or equal to 500 mRem/yr to the total body and less than or equal to 3000 mRem/yr to the skin.

The basis for the calculation of the percent of technical specification in Table 2A of Attachment 1, is the ODCM section 6.2.1 which states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 1 OCFR20, Appendix B, Table II, Column 2 . for radionuclides* other than dissolved or entrained noble gases. For dissolved or entrained noble gases, the concentration shall be limited to 2 X 10-4 microcuries/ml.

Page 2 of 2 Percent of technical specification calculations are based on the total gaseous or liquid effluents released for that respective quarter.

The annual and quarterly doses, as reported in Attachment 2, were calculated according to the methodology presented in the ODCM. The beta and gamma air doses due to noble gases released from the site were calculated at the site boundary. The maximum exposed member of the public from the release of airborne iodine - 131, tritium and all radionuclides in particulate form with half lives greater than 8 days, is defined as an infant, exposed through the grass-cow-milk pathway, with the critical organ being the thyroid gland. The maximum exposed member of the public from radioactive materials in liquid effluents in unrestricted areas is defined as an adult, exposed by either the invertebrate or fish pathway, with the critical organ being either the thyroid gland or gastrointestinal-lower large intestine. The total body dose was also determined for this individual.

Presented in Attachment 6 is a list of unplanned gaseous and liquid releases exceeding the ODCM limits of sections 6.3.1 and 6.2.1 respectively.

The typical lower level of detection (LLD) capabilities of the radioactive effluent analysis instrumentation are presented in Attachment 7. These LLD values are based upon conservative conditions (i.e., minimum sample volumes and maximum delay time prior to analysis). Actual LLD values may be lower. If an isotope is not detected when analyzing effluent samples, then the activity of that isotope will be reported as Not Detected (N/D) on Attachment 1 of this report. When all isotopes listed on Attachment 1 for a particular quarter and release mode are less than the lower level of detection, then the totals for this period will be designated as Not Applicable (N / A).

3.0 Supplemental Information Section 6.5.1 of the ODCM requires the identification of the cause for the unavailability of milk or leafy vegetation samples, and identification for obtaining replacement samples.

All milk and leafy vegetation samples were available for collection during the period of July 1, 1991 through December 31, 1991.

Section 6.5.2 of the ODCM requires the identification of new sample locations determined with the Land Use Census as yielding a calculated dose or dose commitment greater than the values currently being calculated. No new sample location(s) that may yield a greater dose or dose commitment than are currently used were identified in the Land Use Census.

Dry Cask Independent Spent Fuel Storage Installation Technical Specification Appendix C, 1.4.1 requires reporting the quantity of each of the principal radionuclides released from the installation to the environment in liquid and gaseous effluents during the previous 6 months of operations. There were no liquid or gaseous effluent releases from the Dry

,Cask Independent Spent Fuel Storage Installation during the period of July 1, 1991 through December 31, 1991.

Attachment 1 EFFLUENT RELEASE DATA (July 1, 1991 Through December 31, 1991)

This attachment includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulatory Guide 1.21, Appendix B.

TABLE lA Attachment 1 Page 1 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD QTR. FOURTH QTR. .t' EST. ERROR A. FISSION & ACTIVATION GASES

1. TOTAL RELEASE CI 1. 498 01 1.25E 00 1.80E 01
2. AVG RELEASE RATE FOR PERIOD UCI/SEC 1.878 00 1. 58E-01 B. IODINE
1. TOTAL I-131 CI 2. 27E-04 6. 72E-05 2.BOE 01
2. AVG RELEASE RATE FOR PERIOD UCI/SEC 2.858-05 8.468-06 C. PARTICULATE
1. RALF-LIVES >8 DAYS CI 2.168-04 1.02E-04 2.808 01 2 *. AVG RELEASE RATE FOR PERIOD UCI/SEC 2.728-05 1.298-05
3. GROSS ALPHA RADIOACTIVITY CI 6.91E-07 2. 78E-07 D. TRITIUM
1. TOTAL RELEASE CI 4.63E 00 9.04E 00 3. lOE 01
2. AVG RELEASE RATE FOR PERIOD UCI/SEC 5.828-01 1.148 00 ENTAGE OF T. S. LIMITS CHITICAL ORGAN DOSE RA TE 4.41E-03 5.638-03 TOTAL BODY DOSE RATE 9.248-02 6.858-04 SKIN DOSE RATE 2.30E-02 2.0lE-04

TABI,E lB Attachment 1 Page 2 of 7 EFFI,UENT ANO ff/ASTE DISPOSAl, SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 GASEOUS EFFI,UENTS-MIXEO-MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES KR-B5 CI N/D N/D N/D N/D KR-B5M CI N/0 N/0 1.22E-03 N/0 KR-B7 CI N/D N/0 N/D N/D KR-BB CI N/D N/D N/0 N/D XE-133 CI 5.03E-Ol 6.B9E-01 2.00E 00 N/0 XE-135 CI 9.96E-02 6.59E-02 9.65E-02 N/D XE-135M CI N/0 N/0 N/D N/D XE-13B CI N/D N/D N/D N/0 XE-131M CI N/D N/D 1.38E-02 N/D XE-133M CI N/D N/D 2.49E-02 N/0 AR-41 CI 7.04E-02 N/0 2.02E-03 N/0 TOTA!, FOR PERIOD CI 6. 73E-01 7.55E-01 2.14E 00 N/A
2. IODINES I-131 CI 4.32E-07 1.15E-07 3.13E-07 N/0 I-133 CI 2.42E-07 N/0 1.llE-07 N/D I-135 CI N/D N/0 N/D N/D I-132 CI N/D N/D N/D N/0 TOTA!, FOR PERIOD CI 6. 74E-07 l.15E-07 4.24E-07 N/A
3. PARTICUI,ATES SR-B9 CI N/D N/D N/D N/D SR-90 CI N/D N/0 N/D N/0 CS-134 CI N/0 N/D N/0 N/0 CS-137 CI 3.97E-08 1.17E-07 N/0 N/D BA-140 CI N/0 N/0 N/0 N/D I,A-140 CI N/0 N/0 N/D N/0 C0-60 CI 1.24E-07 l.lOE-07 N/D N/0 C0-58 CI N/0 5.82E-09 N/0 N/0 CS-138 CI N/0 N/0 N/0 N/D SE-75 CI B.59E-09 N/0 N/0 N/D RB-BB CI N/0 N/0 2.09E-05 N/D

TABLE lC Attachment 1 Page 3 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES SURRY POWER STATION UNITS 1&2 UNIT CONTINUOUS MODE THIRD QUARTER FOURTH QUARTER BATCH MOOE THIRD QUARTER FOURTH QUARTER

1. FISSION & ACTIVATION GASES KR-85 CI N/0 N/0 N/0 N/0 KR-85M CI 1. 308-04 1.llE-04 N/0 N/0 KR-87 CI 1. 06E-04 2.92E-04 N/0 N/0 KR-88 CI 1.50E-04 6.00E-04 N/0 N/0 XE-133 CI 4.83E 00 3. 97E-Ol 9.57E-02 6.59E-02 XE-135 CI 4.518-01 7.llE-03 N/0 N/0 XE-135M CI 7.568-03 1.0BE-02 N/0 N/0 XE-138 CI 4.64E-04 3. 278-04 N/0 N/0 XE-131M CI 2.278-03 N/0 N/0 N/0 XE-133M CI N/0 N/0 N/0 N/0 AR-41 CI 6.66E 00 2.85E-02 N/0 N/0 TOTAL FOR PERIOD CI 1. 20E 01 4.338-01 9.578-02 6.59E-02
2. IODINES I-131 CI 2.258-04 6.38E-05 8.68E-07 3.28E-06 I-133 CI 2.98E-04 1.658-04 4. lBE-08 1.54E-07
  • I-135 I-132 TOTAL FOR PERIOD CI CI CI 2.14E-05 N/0 5.448-04 N/0 N/0 2.29E-04 N/0 N/0 9.IOE-07 N/0 1.24E-08 3.45E-06
3. PARTICULATES SR-89 CI N/0 N/0 N/0 N/0 SR-90 CI N/0 N/0 N/0 N/0 CS-134 CI 5.96E-06 4. 25E-07* N/0 N/0 CS-137 CI 1.0lE-04 5.668-05 2.46E-07 N/0 BA-140 CI N/0 N/0 N/0 N/0 LA-140 CI N/0 N/0 N/0 N/0 C0-60 CI 9. 758-05 4.51E-05 5.0BE-08 N/0 C0-58 CI 1.llE-05 N/0 N/0 N/0 CS-138 CI 8.67E-05 4.06E-05 N/0 N/D SE-75 CI N/D N/D N/0 N/0 RB-88 CI N/D N/0 N/0 N/0

TABLE 2A Attachment I Page 4 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD QTR. FOURTH QTR. .%' EST. ERROR A. FISSION AND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CI 3.42E-01 1. 47E-02 2. OOE 01
2. AVG OIL. CONC. DURING PERIOD UCI/ML 5.89E-10 2.56E-11
3. PERCENT OF APPLICABLE LIMIT .%" l.55E-03 1.23E-04 B. TRITIUM
1. TOTAL RELEASE CI 2.03E 02 2. 74E 02 2. OOE 01
2. AVG OIL. CONC. DURING PERIOD UCI/ML 3.49E-07 4.76E-07
3. PERCENT OF APPLICABLE LIMIT .%" 1.16E-02 1.59E-02
c. DISSOLVED AND ENTRAINED GASES
1. TOTAL RELEASE CI 2.llE-02 2.59E-02 2. OOE 01
2. AVG OIL. CONC. DURING PERIOD UCI/ML 3.63E-11 4.50E-11
3. PERCENT OF APPLICABLE LIMIT .%" 1.BlE-05 2.25E-05

~ROSS ALPHA RADIOACTIVITY TOTAL RELEASE CI O.OOE-01 O.OOE-01 2. OOE 01 E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 3.34E 07 2.85E 08 3.00E 00 F. VOLUME OF DILUTION WATER USED DURING PERIOD LITERS 5.BlE 11 5. 76E 11 3.00E 00

TABLE 2B Attachment 1 Page 5 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/91 TO 12/31/91 LIQUID EFFLUENTS CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT THIRD FOURTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER SR-89 CI N/D N/D N/D N/D SR-90 CI N/D N/D N/D N/D CS-134 CI N/D N/D 5.79E-03 2.43E-04 CS-137 CI 1.28E-02 l.09E-02 4.69E-02 2.09E-03 I-131 CI N/D N/D 4.19E-04 N/D C0-58 CI 4.0JE-08 N/D 2.20E-02 1.46E-04 C0-60 CI 2.lOE-04 2.59E-04 6.94E-02 3.94E-04 FE-59 CI N/D N/D 4.92E-04 N/D ZN-65 CI N/D N/D N/D N/D MN-54 CI N/D N/D 1.56E-03 6.54E-06 CR-51 CI N/D N/D 1.llE-02 N/D ZR-95 CI N/D N/D 6.09E-04 N/D NB-95 CI N/D N/D 2.55E-03 N/D M0-99 CI N/D N/D N/D N/D TC-99M CI N/D N/D N/D N/D BA-140 CI N/D N/D 4.87E-05 N/D LA-140 CI N/D N/D 7.03E-04 N/D CE-141 CI N/D N/D N/D N/D C0-57 CI N/D N/D 4.14E-05 N/D SB-125 CI N/D N/D 8.31E-02 6.64E-04

  • AG-llOM SB-124 I-133 RU-103 TE-132 NA-24 CI CI CI CI CI CI N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D N/D
6. 71E-03 2.58E-03 3.53E-05 4.96E-05 6.0BE-06 9.91E-06 2.lBE-05 N/D N/D N/D N/D N/D FE-55 CI N/D N/D 7.52E-02 N/D SR-92 CI N/D N/D N/D 7. 79E-06 TOTAL FOR PERIOD CI 1.30E-02 1.llE-02 3.29E-01 3.58E-03 XE-133 CI N/D 2.05E-02 1. 66E-02 5.46E-05 XE-135 CI N/D 5.358-03 4.42E-03 1.008-05 AR-41 CI N/D N/D 1.538-05 N/D X8-135M CI N/D N/D 3.65E-06 N/D

Attachment 1 Page 6 of 7 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 07/01/91-12/31/91 SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL(Not irradiated fuel)

1. Type of waste Unit 6-month Est.Total Period Error,%
a. Spent resins, filter sludges, evaporator m3 9.17E+OO l.OOE+Ol bottoms, etc. Ci l .56E+02 3.00E+Ol
b. Dry compressible waste, contaminated m3 4.33E+02* l.OOE+Ol equip., etc. Ci 1.96E+OO 3.00E+Ol
c. Irradiated components, control m3 O.OOE+OO O.OOE+OO rods, etc. Ci O.OOE+OO O.OOE+OO
d. Organic waste(i.e. oil and scintillation m3 O.OOE+OO O.OOE+OO e-fluid) Ci O.OOE-00 O.OOE+OO
2. Estimate of major nuclide composition(by type of waste)

QI

a. Co-60 70 6.20E+Ol Fe-55  % 1.75E+Ol Ni-63  % 7.64E+OO Co-58  % 6.18E+OO Cs-137  % 4.27E+OO 0/

Cs-134 iO l.26E+OO

b. Co-60  % 3.04E+Ol Ni-63  % 2.90E+Ol Fe-55  % 2.86E+Ol Cs-137  % 1.05E+Ol Cs-134  % 1.39E+OO
c.  %
d. - - -  %

Attachment 1 Page 7 of 7

  • TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND ffiRADIATED FUEL SHIPMENTS PERIOD 07/01/91-12/31/91 (continued)
3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 3 Truck Barnwell, SC 10 Truck Oak Ridge, TN B. IRRADIATED FUEL SHIPMENT(Disposition)

Number of Shipments Mode of Transportation Destination 0

  • NOTE: Dry active waste was shipped to a licensed waste processor for volume reduction. Therefore,, this volume is not representative of the actual volume buried. The total volume of dry active waste buried for the reporting period was 5.00E+Ol m3.

Attachment 2 Page 1 of 1 ANNUAL AND OUARTERLY DOSES An assessment of radiation doses to the maximum exposed member of the public due to radioactive liquid and gaseous effluents released from the site for each calendar quarter for the calendar year of this report, along with an annual total of each effluent pathway is made pursuant to the ODCM, section 6.6.2 requirement.

LIQUID GASEOUS Total Body Thyroid GI-LLI Gamma Beta Thyroid (mRem) (mRem) (mRem) (mRad) (mRad) (mRem) 1st Quarter 5.35E-03 6.67E-05 1.71E-02 4.49E-05 l.09E-04 8.16E-04 2nd Quarter 8.54E-03 2.67E-04 5.32E-02 l.34E-02 2.57E-02 3.39E-03 3rd Quarter 1.20E-03 7.38E-05 9.30E-03 l.23E-01 5.37E-02 4.62E-03 4th Quarter l.42E-04 5.95E-05 9.07E-05 9.SOE-04 l.19E-03 1.59E-03 Annual l.52E-02 4.67E-04 7.97E-02 l.37E-01 8.07E-02 1.04E-02

Attachment 3 Page 1 of 1 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)_

As required by Technical Specification 6.8.B, revisions to the ODCM, effective for the time period covered by this report, are synopsized in this attachment.

Revision 1 to the Virginia Power Offsite Dose Calibration Manual was effective July 01, 1991.

Revision 2 to the Virginia Power Offsite Dose Calculation Manual was effective September 01, 1991.

A copy of Revision 2 of the Offsite Dose Calculation Manual is attached.

Changes made effective with Revision 1 and Revision 2 are indicated by marking the borders of the revised areas with the effective date of the change. All changes marked II Rev. l II were effective July O1, 1991. All changes marked 11 Rev. 2 11 were effective September 01, 1991.

Additionally, changes were made in the presentation of text. Effective with Revision 1, formulas or equations within the ODCM were assigned a number.

Future references to the equation are made via this equation number. Also effective with Revision 1, words or phrases that were capitalized in Revisions 0, if they were defined by Technical Specifications, were un-capitalized.

Punctuation, spelling and other grammatical errors were corrected in Revision 1 and Revision 2. These minor changes are not specifically identified, as they do not affect the text content. Page numbers were changed as required, to reflect the relocation of text by Revision 1 and Revision 2.

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