ML18152A770
| ML18152A770 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1987 |
| From: | STEWART W L VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
| References | |
| 88-087, 88-87, NUDOCS 8803070236 | |
| Download: ML18152A770 (20) | |
Text
e POW 24 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION (July 1, 1987 Through December 31, 1987) /'* ~--:-::--=-=-:=-=-:::~----
/,., ~8~3070236 871231 FDR ADOCK 05000?80 R -* .. D.CD e 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.
Section No. 1 2 3 e RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (July l, 1987 Through December 31, 1987) Subject Purpose and Scope Discussion Index Supplemental Information Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3 Revisions to Off site Dose Calculation Manual (ODCM) Attachment 4 Revisions to Process Control Program (PCP) Attachment 5 Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Attachment 6 In operability of Radioactive Liquid and Gaseous Effluent Instrumentation Attachment 7 Unplanned Releases Attachment 8 Lower Level of Detection (LLD) for Effluent Analysis Page 1 1&2 2 1.0 e Page 1 of 2 The Radioactive Effluent Release Report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in ry Guide 1.21, "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", 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. This report includes changes to the PCP with information and documentation necessary to support the rationale for the changes as required by Technical Specification 6.8A. Major changes to the radioactive liquid, gaseous and solid waste treatment systems are reported as required by Technical Specification
6.9. Information
to support the reason for the change and a summary of the 10CFR50.59 evaluation are included.
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 Technical Specification
- 3. 7E.2, 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 Technical Specification 3.llB.l.a (ii). Technical Specification 3.1 lB. l.a (ii) 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 Technical Specification 3.llB.l.a (i). This Technical Specification 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 Technical Specification 3.11 A.1.a. Technical Specification 3.11 A. l.a states that the concentration of radioactive material released in liquid effluents to unrestricted areas shall be limited to the concentrations specified in 10CFR20, 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 1 o-4 micro curies/ ml.
3.0 e 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 site ry. 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. The maximum exposed er 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 or GI-LLI. The total body dose was also determined for this individual.
Unplanned releases presented in Attachment 7 are defined in Technical Specification 6.6.B.3 as those gaseous releases exceeding Technical Specification 3.11.B. l.a and those liquid releases exceeding Technical Specification 3.11.A.1.a.
The typical lower level of detection (LLD) capabilities of the radioactive effluent analysis instrumentation are presented in Attachment
- 8. 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). Supplemental Information Technical Specification 3.11.D. l.d requires the identification of the cause for the unavailability of milk or leafy vegetation samples, required by Technical Specification, Table 4.9-3, and identification for obtaining replacement samples. All milk and leafy vegetation samples required by Table 4.9-3 were available for collection during the period of July 1, 1987 through December 31, 1987. Technical Specification 3.11.D.2.b 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 being calculated in Technical ication 4.9.C. No new sample location(s) that may yield a greater dose or dose commitment that are currently used in Technical Specification 4.9.C, 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 l, 1987 through December 31, 1987.
TABLE JA Attachment 1 * --Page 1 of 7 EFFLUENT ANO WASTE DISPOSAL SE/l'IIANNUAL REPORT PERIOD: 7/ 1/87 TO 12/31/87 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD QTR. FOURTH QTR. A. FISSION & ACTIVATION GASES 1. TOTAL RELEASE CI 8.47E 01 2. 07E 02 2. AVG RELEASE RATE FOR PERIOD UCI/SEC 1.06E 01 2.60E 01 B. IO.DINE 1. TOTAL I-131 CI 2.55E-03 J.46E-02 2.
- 1. HALF-LIVES
)8 .DAYS Ci 5.58E-04 4.41E-04 2. AVG RELEASE RATE FOR PERIOD UCI/SEC 7.02E-05 5.55E-05 3. GROSS ALPHA RADIOACTIVITY CI 8.91E-07 9. 70E-07 0. TRITIUM 1. TOTAL RELEASE CI 8.14E 00 6.58E 00 2. AVG RELEASE RATE FOR PERIOD UCI/SEC 1.02E 00 8.28E-01 PERCENTAGE OF T. S. LIMITS CRITICAL ORGAN .DOSE RATE >': 2.54E-02 1. 23E-01 TOTAL BO.DY .DOSE RATE % 3.24E-02 l. lOE-01 SKIN .DOSE RATE 0/ ,'O 1.28E-02 4.21E-02 ,'I,' EST. ERROR 2. 501!7 01 2.50E 01 2. 50E 01 2.50E 01
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---TABLE lB Attachment 1 e e Page 2 of 7 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/87 TO 12/31/87 GASEOUS EFFLUENTS-MIXED-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-85 CI N/D N/D 1. 88E-02 1.20E 00 KR-85M CI N/D N/D N/D 2.23E-03 KR-87 CI N/D N/D N/D 1.34E-03 KR-88 CI N/D N/D N/D 3.56E-03 XE-133 CI 1. 02E 01 1. 61E 01 4.21E 00 2. 73E 01 XE-135 CI 4.15E-01 1. 99E-01 5.51E-03 8.18E-03 XE-135M CI N/0 N/0 N/0 N/D XE-138 CI N/0 N/D N/D N/0 XE-131M CI N/D N/D 7. 40E-02 7. 62E-01 XE-133M CI N/D N/0 2.16E-02 6.64E-02 AR-41 CI N/0 N/0 N/D 1.43E-03 TOTAL FOR PERIOD CI 1. 07E 01 1. 63E 01 4.33E 00 2. 94E 01 2. IODINES I-131 CI 4.66E-07 2.03E-06 2.40E-06 3.17E-05 I-133 CI 8.65E-08 5. 71E-08 6. 73E-08 N/D I-135 CI N/D N/D N/D N/D I-132 CI N/D N/0 N/D N/D TOTAL FOR PERIOD CI 5.52E-07 2.09E-06 2.46E-06 3.17E-05 3. PARTICULATES SR-89 CI N/D N/0 N/D N/D SR-90 CI N/D N/D N/D N/D CS-134 CI 2.34E-08 8.56E-09 N/D N/0 CS-137 CI 2.52E-07 2.06E-07 2.61E-08 N/0 BA-140 CI N/D N/D N/D N/D LA-140 CI N/D N/D N/D N/D C0-60 CI 8.96E-07 7. 31E-07 N/0 N/D SE-75 CI 4.06E-08 J.OJE-08 N/D N/D C0-58 CI N/D 3.05E-09 N/D 1.85E-08 TC-99M CI N/0 7.93E-10 N/D N/D MN-54 CI N/0 N/D N/D N/D RU-103 CI N/0 2.20E-09 N/D N/0 RB-88 CI N/D N/D N/D N/D M0-99 CI N/D N/D N/D N/D CS-138 CI N/D N/D N/D N/D TABLE IC Attachment 1 * --Page 3 of 7 EFFLUE}{T AN.D WASTE .DISPOSAL SEMIANNUAL REPORT PERIO.D: 7/ 1/87 TO 12/31/87 GASEOUS EFFLUENTS-GROUN.D LEVEL RELEASES CONTINUOUS MO.DE BATCH MODE SURRY POWER STATION UNITS 1&2 J. FISSION & ACTIVATION GASES 'KR-85 l(R-85M J(R-87 KR-88 XE-133 XE-135 XE-135ft1 XE-138 XE-131ft1 XE-133M AR-41 TOTAL FOR PERIOD 2. IO.DINES 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 SE-75 C0-58 TC-99M MN-54 RU-103 RB-88 M0-99 CS-138 UNIT THIRD QUARTER CI N/.D CI N/.D CI N/.D CI N/.D CI 3.21E 01 CI N/D CI N/.D CI N/.D CI JV/.D CI N/.D CI N/.D CI 3.21E 01 CI 2.32E-03 CI 4.60E-03 CI 1. 93E-03 CI 1. OJE-03 CI 9.86E-03 CI JV/.D CI N/.D CI 4.29E-05 CI 2.94E-04 CI N/.D CI N/.D CI 1. 65E-04 CI N/D CI 2.43E-05 CI 8.41E-07 CI 3.93E-06 CI N/.D CI N/.D CI N/D CI JV/.D FOURTH QUARTER JV/.D N/.D JV/.D N/.D 8. 99E 01 1.54E 01 JV/.D JV/.D N/.D N/.D N/.D J.05E 02 J.04E-02 2.40E-03 2.83E-04 9.47E-05 J.31E-02 J .18E-06 N/.D 2.26E-05 1.18E-04 N/.D JV/.D 8.65E-05 JV/.D 1. 97E-04 N/.D J.OBE-06 N/.D 1.39E-04 J.53E-05 1.26E-05 THIR.D QUARTER N/.D N/.D N/.D N/.D 3. 70E OJ 6.21E-01 N/.D N/.D N/.D N/.D JV/JJ 3. 76E OJ 2.32E-04 3.03E-05 JV/JJ J.46E-07 2.62E-04 N/JJ N/.D 2.65E-06 1.76E-05 N/JJ N/.D 6.17E-06 N/JJ N/JJ N/.D N/.D N/JJ N/JJ N/.D N/.D FOURTH QUARTER JV/.D N/.D N/JJ N/.D 5. 48E 01 J. 27E 00 N/.D N/.D N/JJ N/.D N/JJ 5. 61E 01 ' 4. JBE-03 4.17E-04 N/JJ 2.14E-07 4.59E-03 JV/JJ N/.D JV/.D 1.03E-05 N/.D N/.D 2.50E-06 N/.D 9.17E-07 N/IJ N/.D JV/.D N/JJ N/.D N/IJ TABLE 2A Attachment 1 . e e Page 4 of 7 EFFLUENT AND WASTE .DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/87 TO 12/31/87 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD QTR. FOURTH QTR. .,i EST. ERROR A. FISSION AND ACTIVATION PRO.DUCTS
- 1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA) CI 1.45E 00 9.91E-01 2.50E 01 2. AVG .DIL. CONC. .DURING PERIOD UCI/ML 2.07E-09 1.64E-09 3. PERCENT OF APPLICABLE LIMIT o.,-'O 3.39E-02 1.39E-01 B. TRITIUM 1. TOTAL RELEASE CI 3.30E 02 1. 87E 02 2. SOE 01 2. AVG .DIL. CONC * .DURING PERIOD UCI/ML 4.73E-07 3.09E-07 3. PERCENT OF APPLICABLE LIMIT (I/ 1.58E-02 1.03E-02 '0 C. .DISSOL VE.D AND ENTRAINED GASES 1. TOTAL RELEASE CI 1.54E 00 8.42E-01 2.50E 01 2. A VG .DI.£. CONC. .DURING PERIOD UCI/ML ' 2.21E-09 1.39E-09 3. PERCENT OF APPLICABLE LIMIT o, .,i, 1.llE-03 6. 95E-04 '>>. GROSS ALPHA RADIOACTIVITY
- 1. TOTAL RELEASE CI 4.02E-06 O.OOE-01 2.50E 01 E. VOLUME OF WASTE RELEASED (PRIOR TO .DILUTION)
LITERS 5.62E 07 1.06E 08 3.50E 00 F. VOLUME OF .DILUTION WATER USED .DURING PERIOD LITERS 6.98E 11 6.06E 11 3.50E 00 TABLE 2B Attachment 1 . -e Page 5 of 7 EFFLUENT AN]} WASTE llISPOSAL SEMIANNUAL REPORT PERIOll: 7/ 1/87 TO 12/31/87 LIQUID EFFLUENTS CONTINUOUS MO]}E BATCH MOJJE SURRY POWER STATION UNITS 1&2 SR-89 UNIT THIRD QUARTER CI N/ll FOURTH QUARTER N/]} N/ll 6.64E-03 5.02E-02 N/ll THIRJJ QUARTER 6.80E-04 FOURTH QUARTER N/JJ N/JJ 7. 27E-02 2.38E-Ol 2.42E-Ol 8.83E-02 1.21E-Ol 4.17E-03 9.19E-06 2.88E-03 3.67E-02 7.67E-04 1.94E-03 1.02E-03 1. 26E-03 8.65E-04 1.52E-02 8.67E-06 SR-90 CS-134 CS-137 I-131 C0-58 C0-60 FE-59 ZN-65 MN-54 CR-51 ZR-95 NB-95 M0-99 TC-99Jl1 BA-140 LA-140 CE-141 SR-92 SB-125 AG-llOM I-133 SB-124 TE-132 NA-24 RU-103 I-132 I-135 C0-57 CE-144 Nll-147 FE-55 RB-88 NA-22 BI-207 CS-136 TOTAL FOR PERIO]} XE-133 XE-135 XE-135M AR-41 XE-133M KR-85M J{R-88 XE-131M ' L____ CI N/]} CI 1. 48E-02 CI 9.92E,-02 CI 2.06E-04 CI N/0 CI 8.69E-03 CI N/ll CI N/ll CI N/0 CI N/ll CI N/0 CI N/0 CI N/0 CI N/]} CI N/0 CI N/ll CI N/]} CI N/ll CI N/]} CI N/]} CI 1. 80E-04 CI N/ll CI N/]} CI N/]} CI N/ll CI N/]} CI N/]} CI N/D CI N/]} CI N/D CI N/ll CI N/D CI N/ll CI N/D CI N/]} CI 1. 23E-01 CI N/]} CI N/ll CI N/]} CI N/ll CI N/]} CI N/D CI N/ll CI N/ll N/D 6.68E-03 N/0 N/ll N/ll N/0 N/0 N/ll N/ll N/ll N/]} N/JJ N/JJ N/JJ N/0 N/JJ N/JJ N/lJ N/JJ N/JJ N/JJ N/lJ N/JJ N/JJ N/JJ N/JJ N/JJ N/JJ N/JJ N/JJ N/JJ 6.35E-02 1. 59E-03 N/JJ N/ll N/JJ N/JJ N/JJ N/JJ N/JJ N/JJ 5.50E-02 l.62E-01 5.52E-02 l.88E-01 3.24E-01 3.64E-03 3.15E-05 l.29E-02 1.53E-01 6.69E-03 9.82E-03 N/JJ 7.78E-04 l.41E-03 2.89E-02 5.68E-06 2.86E-03 l.86E-01 9. 49E-03 1. lBE-02 2.22E-02 3.55E-05 6.78E-04 4.50E-03 8.73E-05 1. l 7E-03 4.llE-04 7. 21E-04 2.65E-05 8. 37E-02 N/JJ N/0 N/JJ N/JJ l.32E 00 1.38E 00 1.45E-01 2.30E-03 5.91E-04 l.56E-02 l.13E-04 1. 87E-05 1.75E-03 N/JJ 3.24E-02 7.99E-04 3.09E-03 3.90E-03 N/1) 1.0lE-04 5.63E-04 N/JJ 1.64E-04 3.54E-05 l.20E-04 2.12E-05 5.81E-02 5.46E-05 2.46E-06 3.34E-06 l.38E-03 9. 27E-01 7. 71E-01 3.82E-02 2.31E-03 6.57E-05 1. 57E-03 1.09E-04 1. 82E-05 2.65E-02 e TABLE 3 -Attachment 1 Page 6 of 7 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 07/01/87-12/31/87 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 l.42E+Ol 5.00E+OO bottoms, etc. Ci 6.56E+O 1 3.00E+Ol b. Dry compressible waste, contaminated m3 1.60E+02*
5.00E+OO equip., etc. Ci 3.85E+OO 3.00E+Ol c. Irradiated components, control m3 6.SOE+OO 5.00E+OO rods, etc. Ci 2.88E+04 3.00E+O 1 d. Organic waste(i.e.
oil and scintillation m3 O.OOE+OO O.OOE+OO fluid) Ci O.OOE+OO O.OOE+OO 2. Estimate of major nuclide composition(by type of waste) a. Co-60 % 4.47E+Ol Ni-63 % l.29E+O 1 Cs-137 % 1.38E+O 1 Co-58 % 5.16E+OO Fe-55 % l.60E+O 1 Cs-134 % 4.92E+OO b. Co-60 % 4.31E+Ol Fe-55 % 2.09E+O 1 Cs-137 % l.37E+Ol Ni-63 % 1.81E+Ol Cs-134 % 2.74E+OO Co-58 % 1.16E+OO c. Mn-54 % l.51E+Ol Fe-55 % 4.67E+Ol Co-58 % l.04E+O 1 Co-60 % 2.34E+O 1 Ni-63 % 4.03E+OO d. % O.OOE+OO TABLE 3 (Cont} Attachment l Page 7 of 7 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 07/01/87-12/31/87
- 3. Solid Waste Disposition Number of Shipments 9 5 Mode of Transportation Truck Truck B. IRRADIATED FUEL SHIPMENT(Disposition}
Number of Shipments 0 Mode of Transportation Destination Barnwell, SC Oak Ridge, TN
- Destination
- 5 shipments of dry compressible waste were shipped from Surry to a licensed waste processor for volume reduction.
Therefore the volume as listed for this waste type is not representative of the actual volume buried. The total volume of dry compressible waste disposed of at Barnwell, SC for this reporting period was l.50E+2 m 3*
Total Body (mRem) 1st Quarter 1.22E-02 2nd Quarter 4.46E-03 3rd Quarter 3.44E-03 4th Quarter 3.66E-03 Annual 2.37E-02 e e ANNUAL AND QUARTERLY DOSES LIQUID GASEOUS Thyroid GI-LLI Gamma Beta (mRem) (mRem) (mRad) (mRad) 8.48E-04 6.16E-02 l.45E-04 2.44E-04 3.44E-03 5.63E-02 l.lOE-03 3.ZlE-03 4.18E-03 2.52E-02 4.88E-02 l.41E-01 2.23E-02 l.08E-02 l.58E-01 3.70E-O 1 3.07E-02.
l.54E-01 2.08E-01 5.14E-Ol Attachment 2 Page 1 of 1 Thyroid (mRem) 5.83E-03 l.ZSE-02 5.07E-02 2.91E-01 3.60E-01 e e Attachment 3 Page 1 of 1 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM) There were no changes to the Offsite Dose Calculation Manual during the period of July 1, 1987 through December 31, 1987.
e -Attachment 4 Page 1 of 1 REVISIONS TO THE PROCESS CONTROL PROGRAM (PCP) There were no changes to the Process Control Program during the period of July 1, 1987 through December 31, 1987.
e 4'ctachment 5 Page 1 of 1 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS There were no major changes to Surryls Radioactive Liquid, Gaseous or Solid Waste Treatment Systems during the period of July 1, 1987 through December 31, 1987.
e Attachment 6 Page 1 of 1 INOPERAJBILITY OF RADIOACTNE LIQUID AND GASEOUS EFFLUENT MONITORING INSTRUMENTATION Technical Specification 3.7.E.2 requires the Semi-Annual Report to include an explanation why monitors required by Technical Specification Tables 3. 7-S(a) and 3. 7-S(b) which were determined inoperable, were not returned to operable status within 30 days. Two monitors require explanation under this criteria for the period of July 1, 1987 through December 31, 1987. They are the Component Cooling Service Water Monitor and the Waste Gas Holdup System Explosive Gas Oxygen Monitor. 1. The Component Cooling Service Water Monitor (RM-SW-107) continues to be inoperable as described in the previous Semi-Annual Report. Two Engineering studies, suggesting alternate radiation monitoring systems have been completed.
A review of these studies indicates that monitoring the component cooling level and sampling of the service water may provide better sensitivity than the proposed systems. A Technical Specification Change will be proposed to eliminate the radiation monitoring requirement and replace it with service water grab sampling and/or component cooling level monitoring.
Grab sampling, as required by Table 3. 7-S(a) when the monitor is out of service, has been performed since the monitor became inoperable.
The grab sampling will continue until this matter is resolved.
- 2. Replacement of the Waste Gas Holdup System Oxygen Monitors and modification of the sample lines were completed in August of 1986. However, normal operation of the system caused alarm annunciations in the control room. Modification of the annunciator to prevent spurious alarms under normal station operations was completed in December 1987. Full operation of the monitors is expected in the first quarter of 1988. Grab sampling as required by Technical Specification Table 3. 7-S(b) when the monitor is out of service, has been performed since the monitor became inoperable.
Grab sa,mpling will continue to satisfy the monitoring requirements until the modification has been completed.
e UNPLANNED RELEASES Attachment 7 Page 1 of 1 There has been no Unplanned Liquid or Gaseous Releases that exceeded Technical Specification 3.11.A.1.a and 3.11.B.l.a during the period July 1, 1987 through December 31, 1987.
GASEOUS: LIQUID: e Attachment 8 Page 1 of 1 LOWER LEVEL OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS Isotope Required LLD Typical LLD (uCi/ml) (uCi/ml) Kr-87 1.00 E-4 4.88 E-7 -8.14E-7 Kr-88 1.00 E-4 4.71 E-7 -5.41 E-7 Xe-133 1.00 E-4 2.34 E-7 -2.93 E-7 Xe-133m 1.00 E-4 1.09 E-6 -1.51 E-6 Xe-135 1.00 E-4 1.44 E-7 -2.17E-7 Xe-135m 1.00 E-4 3.03 E-6 -4.99 E-6 Xe-138 1.00 E-4 8.17 E-6 -1.12 E-5 I-131 1.00 E-12 8.97 E-14 -1.20 E-13 Sr-89 1.00 E-11 9.00 E-15 -9.00 E-14 Sr-90 1.00 E-11 1. 0 0 E-16 -2. 0 0 E-14 Cs-134 1.00 E-11 4.99 E-14 -8.92 E-14 Cs-137 1.00 E-11 8.75 E-14 -1.58 E-13 Mn-54 1.00 E-11 5.62 E-14 -7.22 E-14 Fe-59 1.00 E-11 1.33 E-13 -1.87 E-13 Co-58 1.00 E-fl 5.44 E-14 -8.04 E-13 Co-60 1.00 E-11 1.06 E-13 -1.16 E-13 Zn-65 1.00E-11 1.36 E-13 -1.86 E-13 Mo-99 1.00 E-11 9.43 E-13 -1.38 E-12 Ce-141 1.00 E-11 3.47 E-14 -5.32 E-14 Ce-144 1.00 E-11 1.50 E-13 -1.92 E-13 Alpha 1.00 E-11 3.53 E-14 -3.97 E-14 Tritium 1.00 E-6 7.72 E-9 -9.03 E-9 Sr-'-89 5.00 E-8 4.00 E-8 -5.00 E-8 Sr-90 5.00 E-8 6.00 E-9 -2.00 E-8 Cs-134 5.00 E-7 5.10 E-8 -9.15 E-8 Cs-137 5.00 E-7 6.44 E-8 -1.05 E-7 I-131 1.00 E-6 3.68 E-8 -4.84 E-8 Co-58 5.00 E-7 3.47 E-8 -5.95 E-8 Co-60 5.00 E-7 6.90 E-8 -1.00 E-7 Fe-59 5.00 E-7 9.52 E-8 -1.21 E-7 Zn-65 5.00 E-7 1.10 E-7 -1.31 E-7 Mn-54 5.00 E-7 4.13 E-8 -5.29 E-8 Mo-99 5.00 E-7 2. 78 E-7 -3.68 E-7 Ce-141 5.00 E-7 4.41 E-8 -5. 77 E-8 Ce-144 5.00 E-7 1.78 E-7 -2.53 E-7 Fe-55 1.00 E-6 9.00 E-7 -1.00 E-6 Alpha 1.00 E-7 8.75 E-9 -9.83 E-9 Tritium 1.00 E-5 2.57 E-6 -3.01 E-6 Xe-133 1.00 E-5 7.09 E-8 -1.16 E-7 Xe-135 1.00 E-5 3.61 E-8 -4.81 E-8 Xe-133m 1.00 E-5 3.06 E-7 -3.48 E-7 Xe-135m 1.00 E-5 6.37 E-7 -8.65 E-7 Xe-138 1.00 E-5 2.05 E-6 -2.69 E-6 Kr-87 1.00 E-5 1.22 E-7 -1.42 E-7 Kr-88 1.00 E-5 1.02 E-7 -1.38 E-7 e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA.
23261 W. L, STEWART VxcE PRESIDENT NUCLEAR OPERATIONS February 29, 1988 U. S. Nuclear Regulatory Commission Attention:
Document Control Desk Washington, D. C. 20555 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNITS I AND 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Serial No. NO/JDH:vlh Docket Nos. License Nos.88-087 50-280 50-281 72-2 DPR-32 DPR-37 SNM-2501 Enclosed is the Surry Power Station Semi-Annual Radioactive Effluent Release Report for July 1, 1987 through December 31, 1987. 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, vfst.1 ~Jv~d_ f Enclosure cc: U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, N. W. Suite 2900 Atlanta, Georgia 30323 Mr. Hugh L. Thompson, Jr., Director Office of Nuclear Material Safety and Safeguards U. S. Nuclear Regulatory Commission Washington, D. C. 20555
- Mr. William E. Holland NRC Senior Resident Inspector Surry Power Station