ML18152A525

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Reissued Semiannual Radioactive Effluent Release Rept, Jul-Dec 1989
ML18152A525
Person / Time
Site: Surry  
Issue date: 12/31/1989
From: Barbara Blount
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18152A527 List:
References
NUDOCS 9006250074
Download: ML18152A525 (21)
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Text

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e ATTACHMENT SEMIANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURAT POWER STATION UNITS 1 AND 2 LICENSE NOS. DPR-32 AND DPR-37 INDEPENDENT SPENT FUEL STORAGE INSTALLATION LICENSE NO. SNM-2501

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SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION (July 1, 1989 Through D~cember 31, 1989)

Prepared By:

Supervisor Radiological Analysis Reviewed By: ~

4.4_._,L_

-~r iiealth Physi Technical Sen.,ices Approved By: ~ 7-- f ~

Superintendent Radiological Protection

I 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.

T Section No.

1 2

3 e

RADIOACTNE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (July 1. 1989 Through December 31. 1989)

Subject Purpose and Scope Discussion Index Supplemental Information Effluent Release Data Annual and Quarterly Doses Revisions to Offsite Dose Calculation Manual (ODCM) Revisions to Process Control Program (PCP) Major Changes to Radioactive Liquid, Gaseous and Solid Waste Treatment Systems Inoperability of Radioactive Liquid and Gaseous Effluent Instrumentation Unplanned Releases Lower Level of Detection (LLD) for Effluent Analysis Page 1

1&2 2

LO e

Page 1 of 2 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 Regulato-ry Guide L21, "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 l, 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 1 OCFR50.59 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. La (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 3.1 lB.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. La. Technical Specification 3.11 A. La 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 1 o-4 microcuries/ml.

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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 cf 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. l.a and those liquid releases exceeding Technical Specification 3.11.A. l.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. 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, 1989 through December 31, 1989.

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 July 1, 1989 through December 31, 1989.

.e e Attachment 1

,._j EFFLUENT RELEASE DATA (July 1, 1989 Through December 31, 1989)

TABLE lA Page 1 of 7 1 *,~

EFFLUENT ANO WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/89 TO 12/31/89 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRD QTR.

FOURTH QTR.

Jt. EST. ERROR A. FISSION & ACTIVATION GASES

1. TOTAL RELEASE CI 2.60E 01 1.llE 02 2.50E 01
2. AVG RELEASE RATE FOR PERIOD UCI/SEC 3.27E 00 1~39E 01 B, IODINE
1. TOTAL I-131 CI J.60E-04 2.29E-04 2.50E 01
2. A VG RELEASE RATE FOR PERIOD UCI/SEC 2.0JE-05 2.88E-05 C. PART IC ULA TE
1. HALF-LIVES >B DAYS CI 2.386-04 J.31E-04 2.50E 01
2. A VG RELEASE RATE FOR PERIOD UCI/SEC 2.99E-05
1. 64E-05
3. GROSS ALPHA RADIOACTIVITY CI
5. 78E-07 4.41E-07 D. TRITIUM
1. TOTAL RELEASE CI 5.40E 00 7.46E 00 2.50E 01
2. AVG RELEASE RATE FOR PERIOD UCI/SEC
6. 79E-01 9.39E-01 PERCENTAGE OF T. S. LIMITS CRITICAL ORGAN DOSE RATE

.I" 4.28E-03 5.90E-03 TOTAL BODY DOSE RATE

  • 1.17E-02 2.64E-02 SKIN DOSE RATE Jt;'

4.336-03 1.02E-02

TABLE lB Attachment I EFFLUENT..I WASTE DISPOSAL SEMIANNUAL REPORT Page 2 of 7

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PERIOD: 7/ 1/89 TO 12/31/89 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. 77E-01 6.06E 00 KR-85M CI N/D N/D 1.20E-03 2.56E-02 KR-87 CI N/D N/D
9. 77E-05 5.528-03 KR-88 CI N/D N/D 3.358-04 2.09E-02 XE-133 CI 1.13E 00 2.34E 00 4.608 00 5.968 01 XE-135 CI 5.948-02 3.098-01 5.798-02 6.14E-01 XE-135M CI N/D N/D N/D 4.258-05 XE-138 CI N/D N/D N/D N/D XE-133M CI N/D N/D 3.758-02
4. 798-01 XE-131M CI N/D N/D 6.088-02 1.238-01 AR-41 CI N/D N/D 8.208-04 5.088-02 TOTAL FOR PERIOD CI 1.19E 00 2.648 00 4.948 00 6.698 01
2. IODINES I-131 CI 6.578-07 2.328-06 1.498-06 5.178-06 I-133 CI 1.458-06 2.668-06 1.318-06 7.858-08 I-135 CI N/D 2.518-06 2. 428-07 N/D I-132 CI N/D 5.168-07 N/D N/D TOTAL FOR PERIOD CI
2. llE-06 8.018-06 3.04E-06 5.25E-06
3. PARTICULATES 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 5.968-09 6.658-09 N/D N/D CS-137 CI 1.368-07 2.50E-07 N/D N/D 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 1.608-07 5.33E-07 N/D N/D RB-88 CI N/D N/D

1. 878-05 N/D CS-138 CI N/D N/D N/D N/D MN-54 CI N/D N/D N/D N/D C0-58 CI N/D N/D N/D N/D

e TABLE JC Attachment I Page 3 of 7

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/89 TO 12/31/89 GASEOUS EFFLUENTS-GROUND LEVEL 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 N/D N/D KR-85M CI 3.78E-02 N/D N/D N/D KR-87 CI N/D N/D N/D N/D KR-88 CI 3.06E-02 N/D N/D N/D XE-133 CI
1. 91E 01
3. 38E 01 1.92E-05 4.23E 00 XE-135 CI 5.54E-Ol 3.28E 00 6.46E-06 N/D XE-135M CI N/D 8.02E-04 N/D N/D XE-138 CI N/D N/D N/D N/D XE-133M CI 7.92E-02 N/D N/D N/D XE-131M CI N/D N/D N/D 1.67E-04 AR-41 CI 7.14E-02 N/D N/D N/D TOTAL FOR PERIOD CI
1. 99E 01
3. 70E 01 2.56E-05 4.23E 00
2. IODINES I-131 CI
1. 58E-04 2.llE-04 N/D 1.05E-05 I-133 CI 5.54E-04 3.55E-04 N/D 8.20E-06 I-135 CI N/D N/D N/D N/D I-132 CI N/D N/D N/D N/D TOTAL FOR PERIOD CI 7.12E-04 5.66E-04 N/A
1. 87E-05
3. PARTICULATES 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 6.75E-06 2.57E-06 N/D N/D CS-137 CI 7.58E-05 6.43E-05 1.82E-08 6.34E-06 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 1.41E-04 4.92E-05 N/0
7. 27E-06 RB-88 CI 3.51E-05 N/D N/D N/D CS-138 CI 4.25E-05 5.97E-04 N/0 3.63E-05 MN-54 CI 3.02E-06 N/D N/D N/D C0-58 CI 9.79E-06 N/0 N/D N/D

e TABLE 2A EFFLUENT ANO WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/89 TO 12/31/89 LIQUID EFFLUENTS-SUMMATION OF ALL RELEASES Attachment I Page 4 of 7 SURRY POWER STATION UNITS 1&2 UNIT THIRO QTR.

FOURTH QTR.

.%" EST. ERROR A. FISSION ANO ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT INCLUDING TRITIUM, GASES, ALPHA)

CI 8.638-01 8.13E-01 2.50E 01

2. AVG OIL. CONC. DURING PERIOD UCI/ML 2.058-09 1.468-09
3. PERCENT OF APPLICABLE LIMIT

.t' 6.25E-03

1. lOE-02 B. TRITIUM
1. TOTAL RELEASE CI 1.008 02 2.14E 02 2.508 01
2. AVG OIL. CONC. DURING PERIOD UCI/ML 2.398-07 3.848-07
3. PERCENT OF APPLICABLE LIMIT k

7.95E-03 1.28E-02

c. OISSOL VEO ANO ENTRAINED GASES
1. TOTAL RELEASE CI 1.21E-01 3.89E-01 2.50E 01
2. AVG OIL. CONC. DURING PERIOD UCI/ML 2.88E-10 6.97E-10
3. PERCENT OF APPLICABLE LIMIT k

1.448-04 3.48E-04

n. GROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE CI O.OOE-01 O.OOE-01 2.50E 01 E.

VOLUME OF WASTE RELEASED (PRIOR TO DILUTION)

LITERS 1.llE 08 l.27E 08 3.50E 00 F.

VOLUME OF DILUTION WATER USEO.DURING PERIOD LITERS 4.218 11 5.58E 11 3.50E 00

TABLE 2B e

Attachment I Page.5 of 7

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EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/89 TO 12/31/89 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

6. 57E-03 2.14E-03 2.47E-02 5.37E-02 CS-137 CI 4.95E-02 2.96E-02
1. 76B-01 4.16E-Ol I-131 CI N/D N/D 7.13E-04 8.03E-03 C0-58 CI N/D N/D 9.51B-03 3.35E-03 C0-60 CI 4.02E-04 1.25E-04 1.98E-01 6.528-02 FE-59 CI N/D N/D N/D 3.0lE-04 ZN-65 CI N/D N/D 9.51B-06 5.93E-06 MN-54 CI N/0 N/D 4.30B-03 1.46E-03 CR-51 CI N/D N/0 4.02E-03 7.lOE-03 ZR-95 CI N/D N/D N/D 5.40E-05 NB-95 CI N/D N/D 8.87E-04
1. 68E-04 M0-99 CI N/D N/D N/D N/D TC-99M CI N/D N/D N/D 4.99E-05 BA-140 CI N/0 N/D N/D N/0 LA-140 CI N/D N/D N/D
1. 37E-04 CE-141 CI N/D N/D N/D N/D SB-125 CI N/D N/D
1. 79E-01
1. BOE-OJ AG-llOM CI N/D N/D 5.90E-03 4.46E-04 C0-57 CI N/D N/0 1.43E-04
1. 89E-06 SB-124 CI N/D N/D B.30B-04 8.llE-03 FE-55 CI N/D N/D.

2.03E-01 3.48E-02 I-133 CI N/D N/D 1.20B-04 1.40E-03 NA-22 CI N/D N/D 2.61E-06 3.34E-06 TE-132 CI N/D N/D 6.66B-06 9.58E-06 I-134 CI N/0 N/D N/D 4.638-06 NA-24 CI N/D N/D N/D 4.32E-05 I-135 CI N/D N/D N/D 1.40E-04 RU-103 CI N/0 N/D N/D 1.52E-04 TOTAL FOR PERIOD CI 5.64E-02 3.19E-02 8.068-01 7.BJE-01 XE-133 CI N/D

5. 798-02 1.02B-01 2.36E-01 XE-135 CI N/D 5.38E-04 1.858-02 9.23E-02 XE-135M CI N/D N/D
7. 48E-06 7.058-05 X8-133M CI N/D N/D 1.0JB-04 2.51E-03 AR-41 CI N/D N/D N/D 6.42E-05 KR-85M CI N/D N/D N/D 3.76E-05
  • \\I' Page 6 of 7 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 07/01/89-12/31/89 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 2.15E+Ol 5.00E+OO bottoms, etc.

Ci 3.79E+02 2.50E+Ol

b. Dry compressible waste, contaminated m3 2.68E+02*

5.00E+OO equip., etc.

Ci 3.38E+OO 2.50E+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+Ol

2. Estimate of major nuclide composition(by type of waste)
a. Ni-63 l.67E+Ol Co-60 5.0lE+Ol Fe-55 l.25E+Ol Co-58 5.72E+OO Cs-137 8.80E+OO Cs-134 3.64E+OO
b. Co-60 5.25E+Ol Fe-55 9.31E+OO Co-58 l.12E+Ol Cs-137 l.36E+Ol Ni-63 7.72E+OO Cs-134 3.34E+OO Mn-54 l.55E+OO
c.
d.

e TABLE 3 e

Attachment l Page 7 of 7 EFFLUENT AND WASTE DISPOSAL SEMI-ANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD 07/01/89-12/31/89

3. Solid Waste Disposition Number of Shipments 7

9 (continued)

Mode of Transportation Truck Truck B.

IRRADIATED FUEL SHIPMENT(Disposition)

Number of Shipments 0

Mode of Transportation Destination Barnwell, SC Oak Ridge, TN Destination

  • NOTE: 2.63E+02 m 3 (containing 2.67 Ci on 9 shipments) of this represents dry active waste shipped from Surry to a licensed waste processor for volume reduction.

Therefore, this portion of the total for this waste type is not representative of the actual volume buried. The total volume of dry active waste buried for the reporting period was l.77E+02 m 3.

  • t Total Body (mRem) 1st Quarter 1.83 E-01 2nd Quarter 3.64 E-02 3rd Quarter 5.34 E-03 4th Quarter 3.93 E-03 Annual 2.29 E-01 e

ANNUAL AND QUARTERLY DOSES LIQUID GASEOUS Thyroid GI-LLI Gamma Beta (mRem)

(mRem)

(mRad)

(mRad) 5.50 E-04 2.01 E-01 0.00 E+OO 0.00 E+OO 3.36 E-05 7.76 E-02 0.00 E+OO 0.00 E+OO 9.96 E-05 2.06 E-02 1.71 E-02 4.19 E-02 7.20 E-04 3.41 E-03 4.46 E-02 9.39 E-02 1.40 E-03 3.03 E-01 6.17 E-02 1.36 E-01 Page 1 of 1 Thyroid (mRem) 2.27 E-04 1.96 E-04 3.31 E-03 4.67 E-03 8.40 E-03

e Page 1 of 1 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

There were no changes to the Offsite Dose Calculation Manual (ODCM) during the period of July 1, 1989 through December 31, 1989.

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, 1989 through December 31, 1989.

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-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 Treatment Systems during the period of July l, 1989 through December 31, 1989.

4 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-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, 1989 through December 31, 1989. 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.

However, significant progress has been made on the design and procurement of a replacement monitoring system.

The new design will replace the single "offline" monitor and sample pump with four 11in-line 11 monitors mounted in a dry well in each heat exchanger. This concept is superior to the previous system in that (1) there is no piping to foul with service water, (2) there are no pumps to maintain, (3) each heat exchanger will be continuously monitored by its own detector, (4) the new system is more sensitive to activity.

Completion of the design change will be coordinated with replacement of the heat exchangers. The 1D1 Component Cooling Water Heat Exchanger and its associated radiation monitor have been replaced. The three remaining heat exchangers are scheduled to be replaced by the end of the next refueling outage on the applicable unit. RM-SW-107 A and B are scheduled to be installed during the Unit # 1 Refueling Outage in the fall of 1990. RM-SW-107 C is scheduled to be installed during Unit #2 Refueling Outage in the spring of 19 91.

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 and will continue until the new system is installed.

2. The Waste Gas Holdup System Oxygen Monitor continues to be inoperable as described in the previous Semi-Annual Report.

The design of the system was reviewed and it was decided to include hydrogen monitoring capability with the analyzer. Also, the sample flow path was altered to sample from and return to the Waste Gas Decay Tank, removing the Surge Drums from the path. This substantial design change delayed procurement of the analyzers and supporting equipment.

The analyzers have been reviewed and are on site, however, the supporting equipment has not been received to date. The modification will be implemented after receipt of remaining parts/equipment.

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 sampling will continue until the monitor is returned to service.

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',a UNPLANNED RELEASES Page 1 of 1 There have been no Unplanned Liquid or Gaseous Releases that exceeded Technical Specification 3.11.A.l.a and 3.11.B.l.a during the period July 1, 1989 through December 31, 1989.

GASEOUS:

LIQUID:

e 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-04 4.25 E 8.47 E-06 Kr-88 1.00 E-04 3.76 E 7.46 E-06 Xe-133 1.00 E-04 2.31 E 5.52 E-06 Xe-133m 1.00 E-04 9.64 E 2.90 E-05 Xe-135 1.00 E-04 1.19 E 3.74 E-06 Xe-135m 1.00 E-04 2.63 E 4.88 E-06 Xe-138 1.00 E-04 6.33 E 9.36 E-06 I-131 l.OOE-12 2.16 E 3.78 E-13 Sr-89 1.00 E-11 1.00 E 3.00 E-13 Sr-90 1.00 E-11 2.00 E 7.00 E-14 Cs-134 1.00 E-11 1.54 E 2.23 E-13 Cs-137 1.00 E-11 1.06 E 2.89 E-13 Mn-54 1.00 E-11 1.81 E 2.60 E-13 Fe-59 1.00 E-11 2.96 E 4.48 E-13 Co-58 1.00 E-11 1.71 E 2.55 E-13 Co-60 1.00 E-11 2.19 E 5.27 E-13 Zn-65 1.00 E-11 2.26 E 5.46 E-13 Mo-99 1.00 E-11 1.24 E 2.53 E-12 Ce-141 1.00 E-11 1.28 E 1.77 E-13 Ce-144 1.00 E-11 6.37 E 8.18 E-13 Alpha 1.00 E-11

1. 0 7 E 1. 7 8 E-14 Tritium 1.00 E-06 7.52 E 8.91 E-08 Sr-89 5.00 E-08 3.00 E 4.00 E-08 Sr-90 5.00 E-08 7.00 E 9.00 E-09 Cs-134 5.00 E-07 3.53 E 6.15 E-08 Cs-137 5.00 E-07 3.60 E 1.75 E-07 I-131 1.00 E-06 3.31 E 5.05 E-08 Co-58 5.00 E-07 2.79 E 4.09 E-08 Co-60 5.00 E-07 3.14 E 8.13 E-08 Fe-59 5.00 E-07 4.26 E 7.01 E-08 Zn-65 5.00 E-07 3.50 E 8.50 E-08 Mn-54 5.00 E-07 2.67 E 4.21 E-08 Mo-99 5.00 E-07 1.86 E 4.09 E-07 Ce-141 5.00 E-07 2.84 E 4.02 E-08 Ce-144 5.00 E-07 1.44 E 1.71 E-07 Fe-55 1.00 E-06 1.00 E 1.00 E-06 Alpha 1.00 E-07 6.19 E 1.03 E-08 Tritium 1.00 E-05 2.07 E 2.46 E-06 Xe-133 1.00 E-05 5.48 E 6.73 E-08 Xe-135 1.00 E-05 2.12 E 3.87 E-08 Xe-133m 1.00 E-05 1.74 E 2.84 E-07 Xe-135m 1.00 E-05 5.16 E 6.48 E-07 Xe-138 1.00 E-05 1.13 E 1.80 E-06 Kr-87 1.00 E-05 8.62 E 1.33 E-07 Kr-88 1.00 E-05 8.47 E 9.49 E-08
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