ML18151A037

Semiannual Radioactive Effluent Release Rept,Surry Power Station,Jan-June 1987. W/870831 Ltr

ML18151A037
Person / Time
Site:	Surry
Issue date:	06/30/1987
From:	Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
87-534, NUDOCS 8709080051
Download: ML18151A037 (20)

Text

POW 24 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION (January 1, 1987 Through June 30, 1987)

PREPARED BY

e FORHARD 1

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, 1

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.

e RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (January 1, 1987 Through June 30, 1987)

Index Section No. Subject ~

1 Purpose and Scope 1 2 Discussion 1&2 3 Supplemental Information 2 Attachment 1 Effluent Release Data Attachment 2 Annual and Quarterly Doses Attachment 3 Revisions to Offsite 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 Inoperability of Radioactive Liquid and Gaseous Effluent Instrumentation Attachment 7 Unplanned Releases Attachment 8 Lower Level of Detection (LLD) for Effluent Analysis

Page 1 of 2 1.0 Purpose and Scop,, e The Radioactive Effluent Release Report includes a summary of the quantities of radioactive liquid and gaseous effluents and solid waste as outlined in Regulato-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 3.11B.1.a (ii). Technical Specification 3.11B.1.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 3.11B.1.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.llA.1.a. Technical Specification 3.llA.1.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 microcuries/ml.

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 bounda-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 memb-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.1.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).

3.0 Supplemental Information Technical Specification 3.11.D.1.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 January 1, 1987 through June 30, 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 Specif-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 January 1, 1987 through June 30, 1987.

e Attachment 1 EFFLUENT RELEASE DATA (January 1, 1987 Through June 30, 1987)

TABLE lA Attachment 1 Page 1 of 6 EFFLUENT . D WASTE DISPOSAL SEMIANNU. REPORT PERIOD: 1/ 1/87 TO 6/30/87 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST QTR. SECOND QTR.  % EST. ERROR A. FISSION & ACTIVATION GASES

, 1. TOTAL RE.LEASE CI 5.44E 00 1.12E 01 2. SOE 01

2. AVG RELEASE RATE FOR PERIOD UCI/SEC 6. 99E-Ol l.42E 00 B. IODINE

1. TOTAL I-131 CI 3.0JE-04 6.31E-04 2.SOE 01

2. AVG RELEASE RATE FOR PERIOD UCI/SEC 3.87E-05 B.02E-OS C. PARTICULATE

1. HALF-LIVES >B DAYS CI 1.03E-03 8.lSE-04 2. 50E 01

2. A VG RELEASE RATE FOR PERIOD UCI/SEC 1.32E-04 1.04E-04

3. GROSS ALPHA RADIOACTIVITY CI 3.64E-07 6.19E-07 D. TRITIUM

1. TOTAL RELEASE CI 9.lOE 00 6.60E 00 2. SOE 01

2. AVG RELEASE RATE FOR PERIOD UCI/SEC 1.17E 00 8.39E-01 PERCENTAGE OF T. S. .LIMITS CRITICA.l ORGAN DOSE RATE 7.43E-03 8.33E-03 TOTAL BODY DOSE RATE l.06E-04 7.36E-04 SJ{IN DOSE RATE 3.50E-05 2.90E-04

TABLE lB Attachment 1 Page 2 of 6 EFFLUENT . D WASTE DISPOSAL SEMIANNUf/1 REPORT.

PERIOD: 1/ 1/87 TO 6/30/87 GASEOUS EFFLUENTS-MIXED-MODE RELEASES CONTINUOUS MODE BATCH MODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES J{R-85 CI N/D N/D N/D N/D KR-85M CI N/D N/D N/D N/D KR-87 CI N/D N/D N/D N/D KR-88 CI N/0 N/0 N/0 N/P XE-133 CI 1.19E 00 3. 64E-01 4.06E 00 8.43E 00 XE-135 CI 6.92E-02 2.35E-01 4.09E-02 4. 49E-01 XE-135M CI N/P N/0 N/P N/D XE-138 CI N/P N/D N/D N/P XE-131M CI N/P N/0 1.20E-02 1.39E-01 AR-41 CI N/P N/0 N/P N/P XE-133M CI N/P N/0 5. 27E-02 1.41E-01 TOTAL FOR PERIOD CI 1.26E 00 5.99E-01 4.17E 00 9.16E 00

2. IODINES I-131 CI 1.53E-07 6.69E-07 3.70E-05 1.20E-05 I-133 CI 2.69E-07 l.99E-07 1.05E-05 4.05E-06 I-135 CI N/P N/D 4.22E-07 4.04E-07 I-132 CI N/D N/D N/P N/0 TOTAL FOR PERIOD CI 4.22E_:_07 8.68E-07 4.79E-05 l.64E-05

3. PARTICULATES SR-89 CI N/P N/D N/P N/0 SR-90 CI N/P N/0 N/P N/P CS-134 CI 2.32E-08 6.02E-09 N/P N/D CS-137 CI 2.66E-07 1.05E-07 7. 56E-09 N/P BA-140 CI N/0 N/D N/0 N/0 LA-140 CI N/D N/D N/P N/0 C0-58 CI 6.20E-09 1.53E-08 N/0 4.75E-05 C0-60 CI 1.13E-06 2.85E-07 N/P 8.45E-06 CR-51 CI N/P N/D N/D N/0 NB-95 CI N/P N/P N/P N/P SE-75 CI N/0 1.61E-08 2.03E-08 N/P C0-57 CI N/D 1.29E-09 N/P 7.08E-08 TC-99M CI N/D N/D N/P N/D SB-125 CI N/D N/D N/D N/P MN-54 CI N/D N/D N/D N/D RB-88 CI N/P N/D N/D 3.91E-06 CE-144 CI N/D N/D N/D 2.03E-07

~--**

TABLE JC Attachment 1 Page 3 of 6 EFFLUENT .JJ WASTE JJISPOSAL SEMIANNU.REPORT PERIOJJ: 1/ 1/87 TO 6/30/87 GASEOUS EFFLUENTS-GROUNJJ LEVEL RELEASES CONTINUOUS MOPE BATCH /110.0E SURRY POWER STATION UNITS 1&2 UNIT FIRST SECONJJ FIRST SECONJJ QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES J{R-85 CI N/JJ N/JJ N/JJ N/JJ KR-85M CI N/JJ N/JJ 3.61E-04 N/JJ J{R-87 CI N/JJ N/JJ 2.12E-04 N/JJ KR-88 CI N/JJ N/JJ 7. 06E-04 N/JJ XE-133 CI N/JJ N/JJ 5.40E-03 1.42E 00 XE-135 CI N/JJ N/0 4.30E-03 N/0 XE-135M CI N/JJ N/0 4.38E-04 N/0 XE-138 CI N/0 N/0 1.70E-04 N/0 XE-131M CI N/0 N/0 2.12E-03 N/JJ AR-41 CI N/0 N/0 1.69E-03 N/JJ XE-133M CI N/JJ N/0 8.21E-05 JV/[)

TOTAL FOR PERIOO CI N/A N/A 1.55E-02 1.42E 00

2. IOJJIJVES I-131 CI 2.63E-04 5.67E-04 2.40E-08 5.13E-05 I-133 CI 8.40E-04 2.39E-03 N/0 2.14E-05 I-135 CI N/JJ 1.40E-03 N/JJ N/0 I-132 CI N/0 1. 69E-03 N/0 3.14E-07 TOTAL FOR PERIOJJ CI 1.JOE-03 6.05E-03 2.40E-08 7.31E-05

3. PART IC ULA TES SR-89 CI N/JJ N/0 N/JJ JV/[)

SR-90 CI N/0 N/0 N/D N/D CS-134 CI 7.81E-05 7.26E-05 J.05E-07 4. OOE-081 CS-137 CI 4.67E-04 3.95E-04 3. 27E-07 7.08E-06 BA-140 CI N/JJ N/0 N/D N/0 LA-140 CI N/0 N/D N/D N/0 C0-58 CI 1. 81E-04 7.12E-05 2.81E-08 5.90E-06 C0-60 CI 2.91E-04 2.00E-04 4.85E-08 3.03E-06 CR-51 CI 9.29E-06 N/D N/0 N/JJ NB-95 CI l .17E-06 N/0 N/D N/D SE-75 CI N/0 N/JJ 1.00E-10 N/JJ C0-57 CI N/D 8.14E-07 4.07E-11 N/0 TC-99M CI 7. 59E-07 N/D N/JJ N/D SB-125 CI N/JJ N/D 1.12E-09 N/D MN-54 CI N/JJ 1.95E-06 N/D N/D RB-88 CI N/D N/0 N/D N/D CE-144 CI N/D N/0 N/JJ N/D

TABLE 2A Attachment 1 Page 4 of 6 EFFLUENT * .D WASTE .DISPOSAL SEMIANNU,, REPORT PERIO.D: 1/ 1/87 TO 6/30/87 LIQUill EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST QTR. SECONll QTR.  % EST. ERROR A. FISSION AN.l) ACTIVATION PROllUCTS

1. TOTAL RELEASE (NOT INCLU.DING TRITIUM, GASES, ALPHA) CI 1.05E 00 l.68E 00 -2. 50E 01

2. AVG llIL. CONC. .DURING PERIO.D UCI/ML 4.00E-09 2.62E-09

3. PERCENT OF APPLICABLE LIMIT  % 2.53E-02 3.22E-02 B. TRITIUM

1. TOTAL RELEASE CI 5. 88E 01 2.39E 02 2.50E 01

2. A VG llIL. CONC. llURING PERIO.D UCI/ML 2.24E-07 3. 74E-07

3. PERCENT OF APPLICABLE LIMIT  % 7. 48E-03 1.25E-02 C. llISSOL VE.D AN.D ENTRAINE.D GASES

1. TOTAL RELEASE CI 8. 71E-02 1. 82E-01 2. 50E 01

2. A VG .DIL. CONC. llURING PERIO.D UCI/ML 3.32E-10 2.84E-10

3. PERCENT OF A.PPLICABLE LIMIT  % 1.66E-04 1.42E-04

.l). GROSS ALPHA RA.DIOACTIVITY

1. TOTAL RELEASE CI 4.52E-06 3. 06E-05 2.50E 01 E. VOLUME OF WASTE RELEASE.l)

(,PRIOR TO llILUTION) LITERS 7. 36E 07 6.06E 07 3.50E 00 F. VOLUME OF .DILUTION WATER USE.l) llURING PERIO.l) LITERS 2.62E 11 6. 41E 11 3.50E 00

TABLE 28 Attachment 1 Page 5 of 6 EFFLUENT * .D WASTE .DISPOSAL SEMIANNUA.REPORT PERIO.D: 1/ 1/87 TO 6/30/87 LIQUI.D EFFLUENTS CONTINUOUS MO.DE BATCH MO.DE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECON.D FIRST SECON.D QUARTER QUARTER QUARTER QUARTER SR-89 CI N/.D N/.D N/.D 2.80E-04 SR-90 CI N/.D N/.D N/.D N/.D CS-134 CI 3.92E-03 3.80E-03 5.67E-02 5.69E-02 CS-137 CI 1. 36E-02

• 2.75E-02 1. 98E-Ol 1.55E-Ol I-131 CI N/.D N/.D 8.36E-03 4.62E-02 C0-58 CI N/.D 3.30E-05 1. 48E-01 1. 80E-01 C0-60 CI N/.D 1.47E-03 3.64E-01 5.95E-Ol FE-59 CI N/.D N/.D 1. 37E-03 8. 26E-03 ZN-65 CI N/.D N/.D 9. 46E-05 1. 79E-04 MN-54 CI N/.D N/.D 6.26E-03 1.33E-02 CR-51 CI N/.D N/.D 3.38E-02 2. 30E-01 ZR-95 CI N/.D N/.D 4. 27E-03 6.28E-03 NB-95 CI N/.D N/.D 5.89E-03 1. 87E-02

.1110-99 CI N/.D N/.D N/.D 3.02E-05 TC-99M CI N/.D N/.D 1.30E-05 3. 79E-04 BA-140 CI N/.D N/.D N/.D 7.05E-05 LA-140 CI N/D N/D 2.41E-03 4.30E-02 CE-141 CI N/.D N/.D 1.13E-05 4. 71E-05 C0-57 CI N/.D N/D 5. 79E-04 9. 37E-04 SB-124 CI N/.D N/.D 1.35E-02 2.09E-02 SB-125 CI N/.D N/D 6.36E-02 9.66E-02 RU-103 CI N/.D N/.D 9.30E-04 5. 73E-03 AG-llOM CI N/.D N/.D 2.70E-03 2.99E-02 SR-92 CI N/.D N/D J.06E-03 9.69E-03 NA-24 CI N/D 2.52E-04 8.04E-04 3. 97E-04 CE-144 CI N/.D N/D J.66E-04 4.13E-03 FE-55 CI N/.D N/D 1.12E-01 1. JBE-01 TE-132 CI N/D N/.D 2.25E-05 3.02E-04 I-133 CI N/D N/D 5.35E-03 7.98E-03 NA-22 CI N/.D N/.D 3.92E-06 N/D I-135 CI N/.D N/D 2.84E-04 2. 56E-05 N.D-147 CI N/.D N/.D N/.D J.3.ZE-05 I-132 CI N/.D N/D N/11 2.85E-05 BI-207 CI N/.D N/D N/.D 1.22E-05 TOTAL FOR PERIOD CI 1. 75E-02 3.31E-02 l.03E 00 1.65E 00 XE-133 CI N/.D N/D 5.39E-02 9.66E-02 XE-135 CI N/D N/D 3.22E-02 8.0lE-02 XE-131M CI N/.D N/l) J.28E-04 1.llE-04 AR-41 CI N/D N/.D 4.45E-05 1.02E-05 KR-85M CI N/.D N/.D J. 07E-05 N/.D KR-87 CI N/.D N/D 7.15E-06 J.94E-05 XE-135M CI N/.D N/.D 4.44E-04 4.25E-03 XE-133.111 CI N/.D N/.D 3.91E-04 1.06E-03 J{R-88 CI N/.D N/JJ 4.95E-06 N/.D

Attachment 1 e TABLE 3 e Page 6 of 6 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND ffiRADIA TED FUEL SlllPMENTS PERIOD Ol/01/87-06/30/87 SURRY POWER STATION A. SOLID WASTE SIDPPED 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 4.98E+Ol 5.00E+OO bottoms, etc. Ci 5.11E+02 3.00E+Ol

b. Dry compressible waste, contaminated ma 4.54E+02* 5.00E+OO equip., etc. Ci 1.00E+Ol 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 fluid) Ci O.OOE+OO O.OOE+OO

2. Estimate of major nuclide composition(by type of waste)

a. Co-60  % 6.39E+Ol Ni-63  % 1.65E+Ol Cs-137  % 7.13E+OO Co-58  % 4.98E+OO Fe-55  % 4.42E+OO Cs-134  % 2.0lE+OO

b. Co-60  % 3.16E+Ol Fe-55  % 3.61E+Ol Cs-137  % 1. 77*E+Ol Ni-63  % 7.55E+OO Cs-134  % 4.43E+OO Co-58  % 2.59E+OO

c.  % O.OOE+OO d.

--  % O.OOE+OO

3. Solid Waste Disposition Number of Shipments Mode of Transportation Destination 13 Truck Barnwell, SC 14 Truck Oak Ridge, TN

• B. IRRADIATED FUEL SIDPMENT(Disposition)

Number of Shipments . Mode of Transportation Destination 0

• 14 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 3

waste disposed of at Barnwell, SC for this reporting period was 2.94 E+02 m

• Attachment 2 Page 1 of 1 ANNUAL AND QUARTERLY DOSES An assessment of the Annual and Quarterly Doses to the maximum exposed members of the public due to radioactive liquid and gaseous effluents released from the station during 1987 will be in the Semi.-Annual Radioactive Release Report submitted within 60 days after January 1, 1988 in accordance with Technical Specification 6.6.B.3.

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 January 1, 1987 through June 30, 1987.

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 January 1, 1987 through June 30, 1987.

e Attachment 5 Page 1 of 1 MAJOR CHANGES TO RADIOACTIVE LIQUID, GASEOUS AND SOLID WASTE TREATMENT SYSTEMS There were no major changes to Surry's Radioactive Liquid, Gaseous or Solid Waste Treat-ment Systems during the period of January 1, 1987 through June 30, 1987.

e Attachment 6 Page 1 of 1 INOPERABILITY OF RADIOACTIVE 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. 7-5(a) and 3. 7-5(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 January 1, 1987 through June 30, 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. 7-5(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 annunications in the control room. Station engineering has provided plans for modification of the annunicator to prevent alarm. Presently the modification is scheduled to be completed by 12/31/87.

Grab sampling as required by Technical Specification Table 3. 7-5(b) when the monitor is out of service, has been performed since the monitor became inoperable. Grab sampling will continue to satisfy the monitoring requirements until the modification has been completed.

Attachment 7 Page 1 of 1 UNPLANNED RELEASES There has been no Unplanned Liquid or Gaseous Releases that exceeded Technical Specification 3.11.A.1.a or 3.11.B.1.a during the period of January 1, 1987 through June 30, 1987.

- e LOWER LEVEL OF DETECTION FOR EFFLUENT SAMPLE ANALYSIS Attachment 8 Page 1 of 1 GASEOUS: Isotoee Reriuired LLD Tleical LLD uCi/ml) uCi/ml)

Kr-87 1.00 E-4 5.82 E 6.29 E-7 Kr-88 1.00 E-4 4.66 E 5.76 E-7 Xe-133 1.00 E-4 2.55 E 2.96 'E-7 Xe-133m 1.00 E-4 1.29 E 1.56 E-6 Xe-135 1.00 E-4 1.47 E 1.92 E-7 Xe-135m 1.00 E-4 3.34 E 6.28 E-6 Xe-138 1.00 E-4 1.24 E 9.62 E-6 I-131 1.00 E-12 9.35 E-14 -1.26 E-13 Sr-89 1.00 E-11 1.00 E 8.00 E-13 Sr-90 1.00 E-11 2.00 E 1.00 E-13 Cs-134 1.00 E-11 5.90 E 8.15 E-14 Cs-137 1.00 E-11 8.64 E 1.20 E-13 Mn-54 1.00 E-11 5.28 E 7.61 E-14 Fe-59 1.00 E-11 1.36 E 1.99 E-13 Co-58 1.00 E-11 5.54 E 7.71 E-14 Co-60 1.00 E-11 8.07 E 1.39 E-13 Zn-65 1.00 E-11 1.45 E 2.18 E-13 Mo-99 1.00 E-11 1.01 E 1.35 E-12 Ce-141 1.00 E-11 3.92 E 4.57 E-14 Ce-144 1.00 E-11 1.45 E-13 -1.73 E-13 Alpha 1.00 E-11 3.56 E 5.88 E-14 Tritium 1.00 E-6 7. 72 E 9.03 E-9 LIQUID: Sr-89 5.00 E-8 4.00 E-8 - 5.00 E-8 Sr-90 5.00 E-8 9.00 E-9 - 1.00 E-8 Cs-134 5.00 E-7 6.64 E-8 - 7.74 E-8 Cs-137 5.00 E-7 8.18 E-8 - 1.03 E-7 I-131 1.00 E-6 4.20 E-8 - 4.84 E-8 Co-58 5.00 E-7 4.51 E-8 - 5.57 E-8 Co-60 5.00 E-7 7.06 E-8 - 8.72 E-8 Fe-59 5.00 E-7 9.39 E-8 - 1.27 E-7 Zri-65 5.00 E-7 1.13 E-7 - 1.43 E-7 Mn-54 5.00 E-7 5.20 E-8 - 5.48 E-8 Mo-99 5.00 E-7 3.04 E-7 - 3.55 E-7 Ce-141 5.00 E-7 4.00 E-8 - 5.39 E-8 Ce-144 5.00 E-7 1.80 E-7 - 2.47 E-7 Fe-55 1.00 E-6 9.00 E-7 - 1.00 E-6 Alpha 1.00 E-7 8.82 E-9 - 1.46 E-8 Tritium 1.00 E-5 2.57 E-6 - 3.01 E-6 Xe-133 1.00 E-5 7.17 E-8 - 1.10 E-7 Xe-135 1.00 E-5 3.97 E-8 - 4.87 E-8 Xe-133m 1.00 E-5 2.97 E-7 - 4.04 E-7 Xe-135m 1.00 E-5 7.76 E-7 - 9.03 E-7 Xe-138 1.00 E-5 2.23 E-6 - 2.62 E-6 Kr-87 1.00 E-5 1.21 E-7 - 1.53 E-7 Kr-88 1.00 E-5 1.34 E-7 - 1.53 E-7 f *~. I ,- **

~,.,,~; .*: t

e VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 W. L. STEWART August 31, 1987 VICE PRES1:DENT NUCLEAR OPERATIONS U. S. Nuclear Regulatory Commission Serial No.87-534 Attn: Document Control Desk NO/DAS:vlh 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, 1987 through June 30, 1987. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.B.3, includes a surnmary 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. As discussed in our letter (Serial No.87-069) of February 27, 1987, the report is also being sent to NRC Region II.

pursuant to ISFSI Technical Specification 1.4.1 of Appendix C.

(".Very tr~~ yours,

~L~W. L. Stewart Enclosure cc: U. S. Nuclear Regulatory Cornmission Region II 101 Marietta Street, N. W.

Suite 2900 Atlanta, GA 30323 Mr. W. E. Holland NRC Senior Resident Inspector Surry Power Station