ML18143B519

From kanterella
Jump to navigation Jump to search
Semiannual Radioactive Effluent Release Rept, Jan-June 1985. W/850830 Ltr
ML18143B519
Person / Time
Site: Surry  Dominion icon.png
Issue date: 06/30/1985
From: Stewart W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To: Grace J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
85-627, POW-24, NUDOCS 8509190569
Download: ML18143B519 (23)
v • d • e


Text

POW 24 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION (January 1, 1985 Through June 30, 1985) 8509190569 855006003~0 PDR ADOCK O PDR R

J

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 6.6.3.C.

RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (January l, 1985 Through June 30, 1985)

Index Section No. Subject Purpose and Scope 4 2 Discussion 4&5 3 Supplemental Information 5 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

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 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 l, 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 explaination for the inoperability of radioactive liquid and/or gaseous effluent monitors is 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 l, 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 tri~ium, and for all radionuclides in particulate form with half lives greater thari 8 *.days shall be less than or equal to 1500 mRerrt/yr to the critical organ at or .~eyond the site boundary. The critical organ is the child 1s thyroid, inhalation path"way.

The basis for* the calculation of percent of technical specification for the total body and skin in Table IA of Attachment l, is Technical Specification 3.llB.l.a (i). Technical Specification 3.1 lB. l.a 1.0(i) 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 l, is Technical Specification 3.1 lA.l.a. Technical Specification 3.11 A. I.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 l o-4 microcuries/ml.

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

Page 2 of 2 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 6.6.3.C as those gaseous releases exceeding Technical Specification 3.11.B. l.a and those liquid releases exceeding Technical Specification 3.11.A. l.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 January l, 1985 through June 30, 1985.

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.

Attachment 1 EFFLUENT RELEASE DATA (January l, 1985 Through June 30, 1985}

,... L. L.acumen t 1 TABLE lA Page 1 of 6 EFFLUENT A.ND WA.STE DISPOSAL SEMIANNUAL REPORT PERIOD: 1/ 1/85 TO 6/30/85 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST QTR. SECOND QTR. .I' EST. ERROR A, FISSION & ACTIVATION GASES

1. TOTAL RELEASE CI 2.84E 02 6. 47E 02 2.508 01 2, AVG RELEASE RATE FOR PERIOD UCI/SEC 3. 65E 01 8.23E 01 B. IODINE
1. TOTAL I-131 CI 1.00E-02 7.898-03 2.50E 01
2. AVG RELEASE RATE FOR PERIOD UCI/SEC 1. 29E-03 J.OOE-03 C. PARTICULATE
1. HALF-LIVES >8 DAYS CI 2.65E-04 3.44E-04 2.508 01
2. AVG RELEASE RATE FOR PERIOD UCI/SEC 3.40E-05 4.388-05
3. GROSS ALPHA RADIOACTIVITY CI 4.13E-07 7. 48E-07 D. TRITIUM
1. TOTAL RELEASE CI 9.19E 00 8.29E 00 2.50E OJ
2. AVG RELEASE RATE FOR PERIOD UCI/SEC 1.18E 00 1.058 00 PERCENTAGE OF T. S. LIMITS CRITICAL ORGAN DOSE RATE 8.70E-02 6.23E-02 TOTAL BODY DOSE RATE J. 85E-01 1 .. 938-01 SKIN DOSE RATE 6. 58E-02 7.588-02

Attachment l TABLE lB Page 2 of 6 EFFLUENT A.ND WASTE DISPOSAL SENIA.NNCIA.L REPORT PERIOD: 1/ 1/85 TO 6/30/85 GASEOUS EFFLCIENTS-NIXED-NODE RELEASES CONTINCIOCIS NODE BATCH NODE SCIRRY POWER STATION CINITS 1&2 UNIT FIRST* SECOND FIRST SECOND QCIARTER QCIARTER QUARTER QCIARTER

1. FISSION & ACTIVATION GA.SES KR-85 CI O.OOE-01 O.OOE-01 O.OOE-01 3.928-02 XR-85N CI 1.296-03 O.OOE-01 O.OOE-01 O.OOE-01 KR-87 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XR-88 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE-133 CI 3.136 01 l.59B 02 4.616 00 9.188 01 XE-135 CI 8. 376-01 4.156-01 O.OOE-01 7.348-02 XE-135N CI O.OOE-01 O. OOE-01 O.OOE-01* O.OOE-01 XE-138 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 A.R-41 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE-13111 CI O.OOE-01 O.OOE-01 7.726-02 1.038 00 XE-13311 CI O.OOE-01 O.OOE-01 O.OOE-01 6.738-01 TOTA.L FOR PERIOD CI 3~21E 01 1.608 02 4.69E 00 9.368 01
2. IODINES I-131 CI 1.648-07 8.746-05 3.348-06 7.898-04 I-133 CI 2.508-07 O.OOE-01 4.426-08 1.636-05 I-135 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 I-132 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TOTA.L FOR PERIOD CI 4.14E-07 8.746-05 3.386-06 8.058-04
3. PARTICULATES SR-89 CI O. OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR-90 CI 1.0BE-09 O.OOE-01 O.OOE-01 O.OOE-01 CS-134 CI 7. 62B-07 5.808-07 3.00E-08 O.OOE-01 CS-137 CI 2.528-06 2.408-06 8.196-08 1.518-07 BA.-140 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 LA-140 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 TE-132 CI O.OOE-01 1.238-07 O.OOE-01 O.OOE-01 RB-88 CI O.OOE-01 O.OOE-01 O.OOE-01 6.lOE-05 CS-138 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 C0-60 CI 1.00E-05 4.596-06 O.OOE-01 7.996-08 C0-58 CI 1.848-08 4.396-07 4.628-09 2.136-09 MN-54 CI 2.266-07 O.OOE-01 O.OOE-01 O.OOE-01 C0-57 CI J.51E-08 O.OOE-01 O.OOE-01 O.OOE-01 SB-125 CI 5.846-08 O.OOE-01 O.OOE-01 O.OOE-01

Attachment 1 TABLE lC Page 3 of 6 EFFLUENT AND WASTE DISPOSAL SEN I ANNUAL REPORT PERIOD: .1/ 1/85 TO 6/30/85 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTI NUOUS NODE BATCH NODE SURRY POWER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND*

QUARTER QUARTER QUARTER QUARTER

1. FISSION & ACTIVATION GASES KR-85 CI O.OOE-01 0.008-01 O.OOE-01 O.OOE-01 KR-85N CI 0.008-01 O.OOE-01 O.OOE-01 2.386-03 KR-87 CI 1.848 00 O.OOE-01 O.OOE-01 4.618-04 KR-88 CI 0.008-01 0.008-01 0.008-01 2,698-03 XE-133 CI 2,398 02 2.398 02 O.OOE-01 1. 488 02 XE-135 CI 1,848 00 6.458 00 0.008-01 1. 618-02 XE-135N CI O.OOE-01 O.OOE-01 O.OOE-01 0. OOE-01 XE-138 CI 0.008-01 0.008-01 0.008-01 0.008-01 AR-41 CI 3.988 00 O.OOE-01 O.OOE-01 6.558-04 XE-131N CI O.OOE-01 0.008-01 O.OOE-01 4.918-01 XE-133N CI O.OOE-01 O.OOE-01 0.008-01 1. 898-03 TOTAL FOR PERIOD CI 2,478 02 2.458 02 O.OOE-01 1. 488 02
2. IODINES I-131 CI 9.958-03 5.488-03 7.038-05 *1. 548-03 I-133 CI 7.038-03 4,168-03 2.558-05 1.148-04 I-135 CI 1.558-03 2.498-03 O.OOE-01 0. OOE-01 I-132 CI 2.848-04 2.958-04 O.OOE-01 5.188-07 TOTAL FOR PERIOD CI 1.888-02 1.248-02 9.588-05 1.658-03
3. PART IC ULA TES SR-89 CI O.OOE-01 0.008-01 O.OOE-01 O.OOE-01 SR-90 CI 0.008-01 0.008-01 O.OOE-01 0.00E-01 CS-134 CI 3.0lE-05 2.168-05 3.358-06 .1.048-05 CS-137 CI 1.418-04 8.458-05 1.428-05 4.058-05 BA-140 CI O.OOE-01 0.008-01 O.OOE-01 O.OOE-01 LA-140 CI 0.008-01 O.OOE-01 0.008-01 0.008-01 TE-132 CI 2.098-05 O.OOE-01 O.OOE-01 0.008-01.

RB-88 CI 8.138-04 0.008-01 O.OOE-01 2,068-04 CS-138 CI 1.418-03 O.OOE-01 O.OOE-01 0.008-01 C0-60 CI 5.198-05 8.278-05 1.938-06 1. 948-05 C0-58 CI 7. 878-06 6.638-05 O.OOE-01 8. 488-06 NN-54 CI 0.008-01 2.098-06 O.OOE-01 0.008-01 C0-57 CI 0.008-01 0.008-01 0.008-01 0.008-01 SB-125 CI 0.008-01 0.008-01 0.008-01 0.008-01

Attachment 1 TABLE 2A. Page 4 of 6 EFFLUENT A.ND WA.STE DISPOSAL SE/r/IA.NNUA.L REPORT PERIOD: 1/ 1/85 TO 6/30/85 LIQ_c/ID EFFLUENTS-SU/r//r/A.TION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT FIRST QTR. SECOND QTR. -*" EST. ERROR A.. FISSION A.ND ACTIVATION PRODUCTS

1. TOTAL RELEASE (NOT. INCLUDING TRITIU/r/, GA.SES, ALPHA.) CI 2. 718 00 2.178 00 2.50E 01
2. AVG DIL. CONC. DURING PERIOD UCI//r/L 5.188-09 5.258-09
3. PERCENT OF APPLICABLE LI/r/IT J. 928-01 1.178-01 B, TRITIU/r/

J. TOTAL RELEASE CI 2.148 02 1.868 02 2. SOE 01

2. AVG DIL, CONC. DURING PERIOD UCI//r/L 4.098-0'l 4.508-07
3. PERCENT OF APPLICABLE LI/r/IT 1. 368-02 1.508-02
c. DISSOLVED ~ND ENTRAINED GA.SES J. TOTAL RELEASE CI 1.438 00 2.808-01 2.508 01
2. A. VG DIL. CONC. DURING PERIOD UCI//r/L 2. 748-09 6. 778-10
3. PERCENT OF APPLICABLE LI/r/IT J. 378-03 3.388-04 D. GROSS ALPHA RADIOACTIVITY
1. TOTAL RELEASE CI 2.238-04 3.408-12 2. 508 OJ E. VOLU/r/E OF WA.STE RELEASED (PRIOR TO DILUTION)
  • LITERS J.13E 08 9. 968 07 3.508 00 F. VOLU/r/E OF DILUTION lt'A.TER USED DURING PERIOD LITERS 5.24E 11 4.14E 11 3.508 00

l Attachment 1 TABLE 2B 5 of 6 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 1/ 1/85 TO 6/30/85 LIQUID EFFLUENTS CONTINUOUS NODE BATCH NODE SURRY PO/t'ER STATION UNITS 1&2 UNIT FIRST SECOND FIRST SECOND QUARTER QUARTER QUARTER QUARTER SR-89 CI O.OOE-01 O.OOE-01 1. 67E-03 8.33E-04 SR-90 CI O.OOE-01 O.OOE-01 O.OOE-01 8.92E-05 CS-134 CI 7. 23E-03 5.24E-03 3. lBE-01 7.lOE-02 CS-137 CI 2.89E-02 2.00E-02 8.41E-01 1. BlE-01 I-131 CI 9.61E-04 6.78E-05 2.48E-Ol 1.22E-01 C0-58 CI 1.38E-03 2. 74E-05 5.55E-Ol 7. 37E-Ol C0-60 CI 1. lOE-02 1.40E-04 3.0BE-01 4.73E-01 FE-59 CI O.OOE-01 O.OOE-01 l.62E-03 1. 90E-03 ZN-65 CI O.OOE-01 O.OOE-01 9.00E-05 3.38E-04 NN-54 CI 5. 71E-05 O.OOE-01 9.34E-03 3.72E-02 CR-51 CI O.OOE-01 O.OOE-01 J.32E-Ol 2. 57E-01 ZR-95 CI O.OOE-01 O.OOE-01 5.27E-03 6.56E-03 NB-95 CI O.OOE-01 O.OOE-01 1.14E-02 2.24E-02 N0-99 CI O.OOE-01 O.OOE-01 3.15E-03 3.92E-04 TC-99N CI 1.62E-04 O.OOE-01 3.83E-03 1.358-03 BA-140 CI O.OOE-01 O.OOE-01 3.79E-05 1. 97E-04 LA-140 CI O.OOE-01 O.OOE-01 5.12E-04 2.0BE-03 CE-141 CI l.40E-05 O.OOE-01 1.0?E-04 O.OOE-01 I-133 CI 4.00E-03 O.OOE-01 6.BBE-02 2.85E-02 RU-103 CI 3.76E-05 O.OOE-01 6.59E-0.4 7. B?E-05 CE-144 CI O.OOE-01 O.OOE-01 5.83E-03 1. O?E-03 SB-125 CI O.OOE-01 O.OOE-01 8.02E-03 5. 37E-02 AG-llON CI O.OOE-01 O.OOE-01 5.14E-04 3. 77E-02 SR-92 CI O.OOE-01 O.OOE-01 3.31E-04 1.l?E-02 C0-57 CI O.OOE-01 O.OOE-01 6.41E-04 1.64E-03 NA-24 CI 3.31E-04 O.OOE-01 8.15E-02 2.24E-04 SB-124 CI O.OOE-01 O.OOE-01 2.21E-03 1.llE-02 RB-88 CI O.OOE-01 O.OOE-01 2.76E-04 O.OOE-01 I-135 CI 1 .. 73E-03 O.OOE-01 8.05E-03 2.72E-03 I-132 CI 5.43E-05 O.OOE-01 1.19E-03 1.33E-04 lt'-187 CI O.OOE-01 O.OOE-01 1.06E-04 O.OOE-01 TE-132 CI O.OOE-01 O.OOE-01 J.30E-05 3. 87E-05 NA-22 CI O.OOE-01 O.OOE-01 4.27E-06 3.?0E-07 ND-147 CI O.OOE-01 O.OOE-01 6. 46E-05 2.58E-05 CS-136 CI O.OOE-01 O.OOE-01 2.44E-04 4.llE-04 I-134 CI O.OOE-01 O.OOE-01 3.52E-04 4.06E-05 CS-138 CI O.OOE-01 O.OOE-01 2.53E-04 O.OOE-01 FE-55 CI O.OOE-01 O.OOE-01 3.59E-02 8.33E-02 BI-207 CI O.OOE-01 O.OOE-01 1.97E-06 O.OOE-01 TOTAL FOR PERIOD CI 5.59E-02 2.55E-02 2.65E 00 2.15E 00 KE-133 CI 2.32E-04 3.738-02 9.99E-Ol 1. 54E-Ol KE-135 CI 1. JBE-03 J.24E-03 3.99E-01 8.12E-02 AR-41 CI O.OOE-01 O.OOE-01 2.47E-04 1.20E-04 KE-135N CI 5.43E-04 O.OOE-01 1.73E-02 3.BlE-03 KR-85N CI O.OOE-01 O.OOE-01 1.32E-03 5.31E-05 KR-88 CI O.OOE-01 O.OOE-01 6.68E-04

  • 1. 25E-04 XE-133N CI O.OOE-01 O.OOE-Oi 9.52E-03 7.21E-04 KR-87 CI O.OOE-01 O.OOE-01 1.20E-04 0. OOE-01 XE-131N CI O.OOE-01 O.OOE-01 3.84E-03 l.34E-03

ATTACHMENT l Page 6 of 6 TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD:01/01/85-06/30/85 SURRY POWER STATION A. SOLID WASTE SHIPPED OFF SITE. FOR BURIAL OR DISPOSAL (Not irradiated fuel) 1* Type of waste Unit 6-month Est. Total Period Error, ,c II. Spent resins, filler sludges, evaporator m3 4.67E+01 S.OOE+OO bottoms, etc. Ci 9.39E+02 3.00E+01

b. Dry compressible waste, conlllminaled m3 1.17E+03 S.OOE+OO equip., etc. Ci. 3.0SE+01 3.00E+Ol C. Irradiated components, control m3 O.OOE+OO O.OOE+OO rods, etc. Ci O.OOE+OO O.OOE+OO
d. Other (describe) m3 O.OOE+OO O.OOE+OO Ci O.OOE+OO O.OOE+OO
2. Estimate of major nuclide composition (by type of waste)
a. Co-60 3.B7E+01 Co-SB 3.32E+01.

Ni-63 7.74E+OO Fe-55 6.B2E+OO Te-125m 4.BOE+OO Mn-S4 2.31E+OO Cr-51 1.47E+OO

b. Fe-55 2.43E+01 Co-60 2.23E+01 Cs-137 2.1BE+01 H-3 1.09E+01 Cs-134 B.49E+OO Co-56 6.SOE+OO Ni-63 4.62E+OO C. 0.00E+OO
d. 0.00E+OO
3. Solid Waste Disposition Number of Shipments Mode of Transport,ation Destjnaljon 31 . Truck Barnwell, SC 19 Truck Richland, WA
8. IRRADIATED FUEL SHIPMENTS (Disposition)

Number or Shjomenls Mode or Icoosportatioo Oesliootioo 1 Truck E.G.!. G. Idaho

. (for U.S. Department of Energy)

Attachment 2 Page 1 of 1 ANNUAL AND QUARTERLY DOSES The Semi-Annual Radioactive Effluent Release Report submitted within 60 days after January 1 of each year, shall include 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.

L

Attachment 3 Page l of 4 REVISIONS TO OFFSITE DOSE CALCULATION MANUAL (ODCM)

1. A revision to the Offsite Dose Calculation Manual was approved by the Station Nuclear Safety and Operating Committee on January 10, 1985.
a. ODCM section 12 referenced an incorrect Technical Specification number when referring to Semi Annual Radioactive Effluent Report criteria listed in Surry Technical Specifications.
b. The following pages contain a copy of the changes to the ODCM and documentation that the change was reviewed by the Station Nuclear Safety Operating Committee.

No.111111,360 REQUEST TO CHANGE PROCEDURE. AD,,....

SURRY POWER STATION VIRGINIA ELECTRIC AND POWER COMPANY TO SUPERVISOR RESPONSIBLE FOR FO.LLOWING PROCEDURE:

D ABNORMAL D CURVE BOOK D OPERATING D WELDING D ADMINISTRATIVE D EMERGENCY D PERIODIC TEST [3": 00(:M D ANNUNCIATOR D IN-SERVICE INSPECTION .D HEALTH PHYSICS D---------

D CALIBRATION D MAINTENANCE .D SPECIAL TEST D---------

r** , CHEMISTRY* [ ] NON*DESTRUCTIVE TEST D START-UP TEST D----------

PROCEDURE NO: Z* UNIT NO: 3 REVISION DATE: 4

.? - 0 Dc.H - I 2. I (. Z. -11t> .,9FJ/

TITLE: 5 CHANGE REQUESTED: IGIVE STEP .NUMBER, EXACT SUGGEST~P WORDIN~ 1 .AND LIST REFERENCES, STAPLE COPY OF 6 PROCEDURE, WITH SUGGESTED CHAIIGES MARKED, TO "'tHIS FORM.I

REFERENCES:

Ave,,,. .s;e.t:., F~t:. ,y'1'IIA6 i' -,;-, ,.,-'"""r;-:-r, ----- .

. _. \.. ... '* . ~...... '.... :." ,* ,. *' ,. 7 REASON FOR CHANC,E:

'!\ .r:*~ (

rF: 1.

L--l-)--_ *---,~ ...-

, ~-

\..,..*,_I 8 DATE: - 9

.I -_s-tf !,

ACTION TAKEN: 10 DOES THIS CHANGE THE OPERATING METHODS AS DESCRIBED IN THE FSART DYES DOES THIS CHANGE INVOLVE A CHANGE TO THE TECH. SPECS.? DYES DOES THIS CHANGE INVOLVE A POSSIBLE UN REVIEWED SAFETY QUESTION? l.=J YES IF ALL "NO", NO "SAFETY ANALYSIS" IS REQUIRED, IF ANY "YES", A "SAFETY ANALYSIS" IS REQUIRED. l10CFRS0.59)

RECOMMENDED ACTION: II

[7') APPROVED r-i DISAPPROVED BY: 12 DATE: 13 I

REQUIREMENTS: 14 BY: JS 16

/-/0-'iS FETY ANO OPERATING COMMITTEE:

DISAPPROVED 0 APPROVED AS MODIFIED BY COMMITTEE 111 DATE: :18 JAN 1 o ACTION COMPLETED BY: 21 DATE: JAN 2 - 1985 22

Attachment 3 .

(1)

PROCEDURE SURRY POWER STATION NUMBER: HP-ODCM P~OCEDURE (2)

DATE: JAM ! '! 198S 3

TYPE PROCEDURE: UNIT IJ:

HEALTH PHYSICS PROCEDURE 1 &2 (5)

TITLE: OFFSITE DOSE CALCULATION MANUAL 6

LIST OF EFFECTIVE REVISIONS:

SECTION DATE l.* 06-28-84

2. 06-28-84
3. 06-28-84
4. 06-28-84
5. 06-28-84
6. 06-28-84
7. 06-28-84
8. 06-28-84
9. 06-28-84
10. 06-28-84
11. 06-28-84
12. JAN J " 1q95
13. 06-28-84
14. 06-28-84 Appendix A 06-28-84 Appendix B 06-28-84 THINK ALAR (7)

/,D las DATE: /

(9) (10)

DATE: {-\C>-&5" r SAFETY AND OPERATING COMMITTEE: (11) (12)

.DATE: JAN 1 0 1985 20DCMD

Attachment 3 HP-ODCM-12 Page 4 of 4 Page 2 of 2 JAN J O 19ar;

1. TECHNICAL SPECIFICATION REQUIREMENT Technical Specification 6.6.3.C requires that the Semiannual Radioactive Release Report submitted within 60 days after January 1 of each year include, in part, an assessment of the radiation doses to individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year, and an assessment of the radiation doses to the maximum exposed member of the public from reactor releases and radiation.
2. DOSE ASSESSMENT
1. The radiation doses to individuals due to the radioactive liquid and gaseous effluents from the station during the previous calendar year shall be calculated using the methodology presented in this Manual or in Regulatory Guide 1.109 (Revision 1), October 1977, "Calcula-tion of Annual Doses to Man from Routine Releases of Reactor Efflu-ents for the Purpose of Evaluating Compliance with 10CFR Part 50, Appendix I" (see Appendix B)
  • Population doses are not to be included in the dose assessment.
2. The dose to the maximum. exposed member of the public d~e to the radioactive liquid and gaseous effluents from the station shall be incorporated with the dose assessment performed above. If the dose to the maximum exposed member of the public exceeds twice the limits of Specifications 3.11.A.2, 3.11.B.2 or 3.11.B.3, the dose assessment shall include the contribution from direct radiation.

U.S. Nuclear Regulatory Commission NUREG-0543, February 1980, "Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40CFR Part 190)", states "There is reasonable assurance that sites with up to four operating reactors that have releases within Appendix I design objective values are also in conformance with the EPA Uranium Fuel Cycle Standard, 40CFR Part 190".

3. The meteorological conditions during *the previous calendar year or historical annual average atmospheric dispersion conditions shall be used for determining the gaseous pathway doses.

'*.~*,.

Attachment 4 Page 1 of 1 REVISIONS TO THE PROCESS CONTROL PROGRAM (PCP}

There were no licensee initiated changes made to the Process Control Program during the period January l, 1985 through June 30, 1985.

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 January 1, 1985 through June 30, 1985.

I Attachmen.t 6 Page l of 2 INOPERABIIJTY OF RADIOACTIVE LIQillD 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.

Three monitors require explanation under this criteria for the period of January l, 1985 through June 30, 1985. They are the Component Cooling Service Water Monitor, Unit

  1. 2 Discharge Tunnel Monitor and the Waste Gas Holdup System Explosive Gas Oxygen Monitor.
1. The Component Cooling Service Water Monitor (RM-SW-107) was inoperable .prior to this reporting period. The offline Radiation Monitor is operable but pumps bringing service water to the monitor failed. Repeated efforts to return the pumps to operable status failed and on June 4, 1984, a Design Change (84-25) was initiated to replace the monitoring system using an in-line gamma scintillation detector in each of the service water discharge lines from the Component Cooling Heat Exchanges.
  • Upon further review it was determined that such an installation was not feasible because of shielding requirements and physical configuration of the heat exchangers and the heat exchanger outlet piping. The Design Change is currently being rewritten to install a "Snow Plow" type monitor.

The rewritten Design Change is scheduled to be completed and submitted to SNSOC by December 31, 1985. Based on current equipment lead times, installation of the monitor(s) are scheduled for the summer of 1986.

Grab Sampling, 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 Design Change 84-25 is completed.

2. The Unit #2 Discharge Tunnel Monitor (RM-SW-220) was determined inoperable prior to this reporting period. The inline monitor housing experienced corrosion problems and requires redesign to provide stronger support. An Engineering Work Request (EWR 83-12) was initiated on*October 28, 1983.

Parts required for installation were received in July 1985. Installation of a stronger support and reinstallation of the monitor is currently in progress and is scheduled to be completed by September 30, 1985.

All Effluent Releases via this pathway have been diverted to the Unit # 1 Discharge Tunnel.

3. The Waste Gas Holdup System Explosive Gas Oxygen Monitor (GW-102A and GW-102B) was inoperable prior to this reporting period. Repeated attempts to return the monitor to service during the months of June, July and August of 1984 failed and an Engineering Work Request (EWR 84-266) was initiated on August 31, 1984 to correct the problem.

Attachment 6 Page 2 of 2 EWR-84-266 required both monitors to be replaced. The monitors specified by the EWR were received at the station but were returned to the vendor to correct deficiencies.

Installation will continue upon return of the repaired monitors. Scheduled completion date is December 31, 1985.

Grab Sampling, required by Technical Specification Table 3.7-5 (b) when the monitor is out of service, has been performed since the monitor became inoperable. The Grab Sampling will continue to satisfy the monitoring requirements until the installation of the new monitors.

Attachment 7 Page 1 of 1 UNPLANNED RELEASES There has been no Unplanned Liquid or Gaseous Releases that exceeded Technical Specific-ation 3.11.A.l.a or 3.U.B.1.a during the period of January 1, 1985 through June 30, 1985.

VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, V:rHOINIA 23261 W. L. STEWART VICE PBB8IDENT NuCLE_.,B OPERATIONS August 30, 1985 Dr. J. Nelson Grace Serial No. 85-62~

Regional Administrator NO/JBL:acm Region II Docket Nos. 50-280 .D U. S. Nuclear Regulatory Commission 50-281 101 Marietta Street, Suite 2900 License Nos. DPR-32 Atlanta, Georgia 30303 DPR-37 Gentlemen:

VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION, UNITS 1 AND 2 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Enclosed is the Surry Power Station Semi-Annual Radioactive Effluent Release Report for January 1, 1985 through June 30, 1985. The report, submitted pursuant to Surry Power Station Technical Specification 6.6.3.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, r

\ *.\(~*~,\

  • v1. ' ) ~ - * *.

W. L. Stewart Enclosure cc: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing Mr. D. J. Burke NRC Resident Inspector Surry Power Station

Retrieved from "https://kanterella.com/w/index.php?title=ML18143B519&oldid=2404267"