ML18149A389
| ML18149A389 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 12/31/1985 |
| From: | Stewart W VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | Grace J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| 86-122, NUDOCS 8610280102 | |
| Download: ML18149A389 (45) | |
Text
VV 24 SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT SURRY POWER STATION (July l, 1985 Through December 31, 1985)
J
FORWARD This report is submitted as required by Appendix A to Operating License No. 1s DPR-32 and DPR-37, Technical Specifications for Surry Power Station, Uri.its 1 and 2, Virginia Electric and Power Company, Docket No. 1s 50-280, 50-281, Section 6.6.B.3.
RADIOACTIVE EFFLUENT RELEASE REPORT FOR THE SURRY POWER STATION (July 1, 1985 Through December 31, 1985)
Index Section No. Subject 1 Purpose and Scope 2 Discussion 1&2 3 Supplemental Information 2 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
Page 1 of
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 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 gaseo~s 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.BB, changes to the ODCM for the time period _covered by this report are included. Information is provided to $Upport 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.BA.
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 monito_rs 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 l, is Technical Specification 3.llB.1.a (ii). Technical Specification 3.11 B.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 l, is Technical Specification 3.llB.1.a (i). This Technic_al 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.l.a. Technical Specification 3.11 A.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 10-4 microcuries/ml.
Page 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 befog 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.
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, 1985 through December 31, 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 (July 1, 1985 Through December 31, 1985)
TABLE lA achment 1 h 1 of 6 EFFLUENT ._~,o WASTE OISPOSAL SEMIANNUAL REPORT PERIOO: 7/ 1/85 TO 12/31/85 GASEOUS EFFLUENT-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2
- 1. TOTAL RELEASE CI 5.55E 02 5.81E 02 2.50E OJ
- 2. AVG RELEASE RATE FOR PERIOO UCI/SEC 6. 98E 01 7. 31E 01 B. IOOINE
- 1. TOTAL I-131 CI 5.53E-03 2.lOE-03 2. 50E 01
- 2. AVG RELEASE RATE FOR PERIOO l!CI/SEC 6.95E-04 2.64E-04 C. PARTICULATE
- 1. HALF~LIVES. >8 OAYS CI 4.18E-04 1.99E-04 2. 50E 01
- 2. AVG RELEASE RATE FOR PERIOO UCI/SEC 5.26E-05 2.50E-05
- 1. TOTAL RELEASE CI 7 .. 31E 00 7.91E 00 2.50E 01
- 2. AVG RELEASE RATE FOR PERIOO UCI/SEC 9.19E-01 9.95E-01 PERCENTAGE OF T. S. LIMITS CRITICAL ORGAN OOSE ,RATE' 4.83E-'-02 2.llE-02 TOTAL BOOY OOSE RATE 2.04E-01 1. 70E-01 SKIN OOSE RATE. 8.14E-02. 6.94E-02
TABLE JB f ~hrnent 1 12 of 6 EFFLUENT ._.,.l) WASTE .l)ISPOSAL SEMIANNUAL REPORT PERIO.l): 7/ 1/85 TO 12/31/85 GASEOUS EFFLUENTS-MIXE.l)-MO.l)E RELEASES CONTINUOUS MO.l)E BATCH MO.l)E SURRY POWER STATION UNITS 1&2 UNIT THIR.l) FOURTH THIR.l) FOURTH QUARTER QUARTER QUARTER QUARTER
- 1. FISSION & ACTIVATION GASES K~-85 CI 0. OOE-01 O.OOE-01 O.OOE-01 8.60E 00 KR-85M CI O.OOE-01 1.82E-02 1.49E-:Ol O.OOE-01 KR-87 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR-88 CI O.OOE-01 O.OOE-01 1. 07E-01 O.OOE-01 XE-133 CI 1. BOE 01 3. 56E 01 9. BOE 01 1.50E 02 KE-135 CI 2.41E-01 1.40E 00 3.55E 00 1.15E-Ol XE-135M CT 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 XE-133M CI 7.BBE-02 O.OOE-01 9. 42E-01 8.22E-01 XE-131M CI 2.26E-08 O.OOE-01 1.43E 00 2. 71E 00 TOTAL FOR PERIO.l) . CI 1. 83E 01 3. 71E 01 l.04E 02 1. 62E 02
- 2. IO.l)INES I-131 CI 1.44E-06 l.40E-06 1.06E-04 1.0JE-05 I-133 CI 7;28E-09 1.40E-06 4.06E-06 l.15E-06 I-135 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE'-01 I-132 CI O.OOE-01 0. OOE-01 . O.OOE-01 O.OOE-01 TOTAL FOR PERIO.l) CI 1.45E-06
- 2. 80E--06 1.lOE-04 1.13.E-05
- 3. PARTICULATES SR-89 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SR-90 CI 3. 49E-09 7.87E-10 O.OOE-01 O.OOE-01 CS-134 CI 3. 74E-:-06 5.23E-07 O.OOE-01 0. OOE-01 CS-137 CI 1. 49E-05 2.16E-06 1.68E-09 1. 99E-09 BA-140 CI 0.00.E-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 C0-60 CI 6.34E-05 1.04E-05 O.OOE-01 O.OOE-01 C0-58 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 SB-125 CI 6.83E-07 6.43E-08 O.OOE-01 O.OOE-01 MN-54 CI 1.12E-06 9.70E-08 O.OOE-01 . 0. OOE-01 C0-57 CI 6.39E-09 O.OOE-01 O.OOE-01 O.OOE-01 RB-88 CI O.OOE-01 O.OOE-01 1. 61E-03 1.99E-05 CS-138 CI. O.OOE-01 O.OOE-01
- 0. OOE-01 *o. OOE-01 SR-92 CI O.OOE-01 *o. OOE-01 O.OOE-01 O.OOE-01 N.l)-14i CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 NA-24 CI O.OOE-01 1.83E-09 O.OOE-01 O.OOE-01
TABLE JC At t- ::i.chrnen t 1 T t 3 Of 6 EFFLlfENT -* _,O WASTE DISPOSAL SEMIANNUAL REPORT PERIOD: 7/ 1/85 TO 12/31/85 GASEOUS EFFLUENTS-GROUND LEVEL RELEASES CONTINUOUS MOOE BATCH MOOE SURRY POWER S-TATION UNITS 1&2 UNIT THIRD FOlfRTH THIRD FOURTH QUARTER QUARTER QUARTER QUARTER
- 1. FISSION & ACTIVATION GASES KR-85 CI O.OOE-01 O.OOE-01 2.94E-01 O.OOE-01 KR-85/tf CI O.OOE-c--01 O.OOE-01 O.OOE-01 O.OOE-01 KR-87 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 KR-88 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01 XE-133 CI 2.40E 02 3.69E 02 1.78E 02 1. 27E 01 XE-135 CI 6.04E 00 O.OOE-01 1.16E-02 O.OOE-01 XE-135M 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 XE-133M CI O.OOE-01 O.OOE-01 5. 49E-01 0. OOE-01 XE-131/tf CI O.OOE-01 O.OOE-01 7. 30E 00 O.OOE-01 TOTAL FOR PERIOD CI 2. 46E 02 3. 69E 02 1. 87E
- 02 . J. 27E 01
- 2. 09E-03 3.37E-05 9.09E-05 I-135 CI 1.22E-03 l.33E-03 O.OOE-01 1.93E-05 I-132 CI 5.38E-04 2. 77E-04 O.OOE-01 3. 97E-0(i TOTAL FOR PERIOD CI 8.87E-03 5.66E-03 1.20E-03 2.32£-04
- 3. PARTICULATES .J SR-89 CI O.OOE-01 O.OOE-01 O.OOE-01 0. OOE-01 SR-90 .CI O.OOE-01 O.OOE-01 0. OOE-01 O.OOE-01 CS-134 CI 3.93E-05 l.31E-05 3.86E-06 O.OOE-01 CS-137 CI 1. 59E-04 6.57E-05 2.59E-05 5. 89.E-06 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 C0-60 CI 7. 09E-05 4. 47E-05 1.06E-05 6.77E-06
.C0-58 CI 2.14E-05 4.28E-05 1.22E-06 5.60E-06 SB-125 CI O.OOE-01 O.OOE-01 O.OOE-01 0. OOE-01
- MN-54 CI 7.63E-07 5.91E-07 6. 49E-07 O.OOE._01 C0-57 CI O.OOE-01 O.OOE-01 O.OOE-01 0. OOE-01 RB-88 CI 3.39E-05 O.OOE-01 O.OOE-01 O.OOE-01 CS-138 CI O.OOE-01 O.OOE-01 O.OOE-01 1. 47E-05 SR-92 CI O.OOE-01 O.OOE-Ol* O.OOE-01 6.03E-08 N0-147 CI O.OOE-01 O.OOE-01 O.OOE-01 2. 94E-08 .
NA-24 CI O.OOE-01 O.OOE-01 O.OOE-01 O.OOE-01
TABLE 2A Atr::ichment 1 r .4 of 6 EFFLUENT . .JJ WASTE llISPOSAL SEMIANNUAL REPORT PERIOll: 7/ 1/85 TO 12/31/85
- LIQUill EFFLUENTS-SUMMATION OF ALL RELEASES SURRY POWER STATION UNITS 1&2 UNIT THIRll QTR. FOURTH QTR. .t* E,5T. ERROR A. FISSION ANO. ACTIVATION PRODUCTS
- 2. AVG OIL. CONC. llURING PER IOll UCI/ML 2.69E-09 3.34E-09
- 3. PERCENT OF APPLICABLE LIMIT % 6.29E-02 3.08E-02 B. TRITIUM*
- 1. TOTAL RELEASE C1 3.50E 02 3. 40E 02 2.50E 01
- 2. AVG OIL. CONC. DURING PERIOll .UCI/ML 5.83E-07 5.SOE-07
- 3. PERCENT OF APPLICABLE LIMIT % 1. 94E-02 l.83E-02
- c. DISSOLVED ANO ENTRAINED GASES
- 1. TOTAL RELEASE CI 3.39E-01 6.61E 00 2. SOE 01
- 2. A VG OIL. CONC. DURING PERIOD l!CI/ML 5.65E-10 l.07E-08
- 3. PERCENT OF APPLICABLE LIMIT o.*
,o 2.82E-04 5.35E-03 JJ. GROSS ALPHA RAllIOACTIVITY *
- 1. TOTAL RELEASE CI 1.64E-05 1.26E-05 2. 50E OJ E. VOLUME OF WASTE RELEASED (PRIOR TO DILUTION) LITERS 1.45E 08 6.39E 07 3.50E 00 F.
- VOLUME OF- DILUTION WATER USED DURING PERIOll LITERS 6.00E 11 6. lBE 11 3.50E 00
TABLE 2B . Ar' ~chment 1
\5 of 6 EFFLUENT _ .. u WASTE .DISPOSAL SEMIANNUAL REPORT PERIO.O: 7/ 1/85 TO 12/31/85 LIQUI.O EFFLUENTS CONTINUOUS MO.OE BATCH MO.OE -
- SURRY POWER STATION UNITS 1&2 UNIT THIR.O FOURTH _THIR.O FOURTH
. QUARTER QUARTER QUARTER QUARTER SR-89 CI O.OOE-01 O.OOE-01 6. 31E-04. 4.30E-04 SR-90 CI O.OOE O.OOE-01 2.87E-05 O.OOE-01 CS-134 CI 1.0lE-02 5.52E-03 1.16E-01. 9.81E-02 CS-137 CI 4.50E-02 2.45E-02 3.29E-01 2.21E-01 I-131 CI 1.38E-06 6.64E-05 9.53E-02 3. 77E-02 C0-58 CI 6. 67E-04 3.52E-.05. 3.42E-Ol 5. 36E-01 C0-60 CI 7.05E-03 3.60E-04 4. 47E-Ol 5, 76E-01 FE-59 CI O.OOE-01 O.OOE 3.68E-04 8.96E-03 ZN-65 C_I O.OOE-01 O.OOE-01 5.45E-04 4. 71E-04 MN-54 CI O.OOE-01 O.OOE-_01 1. 71E-02 2.0lE-02 CR-51 CI 2. 73E-04 1.19E-04 3.0lE-02 1. 59E-Ol ZR-95 CI O.OOE-01 O.OOE-01 2.16E-03 9.02E-03 NB-_95 CI O.OOE-01 O.OOE-01 9.28E-_03 1.69E-02 M0-99 CI O.OOE-:01 O.OOE-01 J .17E-03 9.JJE-05 TC-99M CI O.OOE-01 O.OOE-01 1.99E-03 3.39E-04 BA-140 CI O.OOE-01 O.OOE-01 2.88E-05 O.OOE-01 LA-140 CI O.OOE-01 0. OOE-.01 2.85E-03 2.70E-03 CE-141 CI J.38E-05 O.OOE-01 8. 71E-06 5. 73E-06 I-133 CI O.OOE-01 O.OOE-01 6.60E-03 1.06E-02 NA-24 CI O.OOE-01 O.OOE-01 4.91E-()5 J.20E-03 SB-124 CI O.OOE-01 O.OOE-01 1 ~ 57E-03 1.99E-02 SB-125 CI 6.63E-05 O.OOE-01 1. 76E-02 J. 52E-Ol AG-llOM CI O.OOE-01 O.OOE-01 5.42E-03 7. 59E-03 SR-92 CI O.OOE-01 O.OOE-01 2.20E-03 2.92E-03 C0-57 CI O.OOE-01 O.OOE-01 1.llE-03 1. 87E-0~1 CS-136 CI O.OOE-01 O.OOE-01 2.46E-03 3. 69E-04 *
- CE-14_4 CI O.OOE-01 O.OOE-01 2.09E-03 4.53E-03 N.0-147 CI O.OOE'-01 O.OOE-01 7. 47E-06 O.OOE-01 Rl!-103 CI, O.OOE-01 O.OOE-01 3.18E-04 6;03E-04 NA-22 CI O.OOE'-01 O.OOE-01 2. 67E-06 6. 71E-06 TE-132 CI O,.OOE-01 O.OOE-01 3.85E-05 2. 47E-05 I-135 CI O.OOE-01 O.OOE-01 8.29E-05 6.99E-04 FE-55 CI O.OOE-01 O.OOE-01 J .15E-01 J. 45E-01 I-134 CI O.OOE-01 O.OOE-01 O.OOE-01 8.95E-05 MN-:56 CI O.OOE-01 O.OOE-01 O.OOE-01 1. 94E-04 W-187 CI O.OOE-01 O.OOE-01 O.OOE-01 1. 89E-04 I-132 CI O.OOE-01 O.OOE-01 O.OOE-01 1.55E-05 TOTAL FOB PERIO.O CI 6. 31E-*02 3.06E-02 1.55E 00 2.03E 00 XE-133 CI J. 61E-02 2.24E-03 2.42E-01 6.16E 00 XE-135 CI O.OOE-01 O. OOE-01
- 7.74E-02 3.63E-01 XE-135M CI O.OOE-01 O.OOE-01 6.92E-04 8.60E-03 XE-133M CI O.OOE-01 O.OOE-01 J. 75E-:03 2.63E-02 KR-85M CI *o.OOE-:01 O.OOE-01 4.13E-05 1.25E-04 AR-41 CI O.OOE-01 O.OOE-01 5. 27E-06 2.07E-04 KR-88 CI O.OOE-01 O.. OOE-01 J.45E-04 1.40E-04 XE-131M CI O.OOE-01 O.OOE-01 8.66E-04 4.87E-02
Atta,* *nt 1 Page ls TABLE 3 EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT SOLID WASTE AND IRRADIATED FUEL SHIPMENTS PERIOD:07/01/85-12/31/85 SURRY POWER STATION A. SOLID WASTE SHIPPED OFFSITE FOR BURIAL OR DISPOSAL (Nol irradiated fuel)
I. Type of waste Unit 6-month Est. Total Period Error. X
- a. Spent resins, filler sludges, evaporator m3 2.44E+01 5.00E+OO bottoms, etc. Ci 2.02E+02 3.00E+01
- b. Dry compressible waste, contaminated m3 7.11E+02 5.00E+OO equip., etc. Ci 3.0SE+01 3.00E+01 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 fluid) m3 7.26E+01 5.00E+OO Ci 4.41E+OO 3.00E+OO
- 2. Estimate of major nuclide composition (by type of waste)
- a. Co-60 X 3.63E+01 Co-58 2.44E+01 Cs-137 "X 1.29E+01 Fe-55 1.08E+01 Ni-63 "X 7.91E+OO Cs-134 4.19E+oo*
H-3 "X 1.44E+OO
- b. H-3 2.92E+01 Co-60 "X 1.66E+01 Fe-S5 X 1.64E+01 Cs-137 X 1.56E+01 C-14 X 5.63E+OO Cs-134 X 5.60E+OO Co-58 X 4.55E+OO C. X O.OOE+OO
- d. Ni-63 Fe-55 "X 7.68E+01 1.41E+01 C-14 ~ :5.76E+OO Pu-241 X 1.SOE+OO Co-60 X 1.SOE+OO J. Solid Waste Disposition Number of Shipments Mode of Iraosportatioo Deslioalioo 29 Truck Barnwell, SC 05 Truck Richland, WA B. IRRADIATED FUEL SHIPMENTS ( Disposition)
- Number of Shipments Mode of Transporlat;on Destination 10 Truck E.G. & G. Idaho (for U. S. Department of Energy)
ichment 2 r'age 1 of 1 ANNUAL AND QUARTERLY DOSES LIQUID GASEOUS Total Body Thyroid GI-LLI Gamma Beta Thyroid (mRem) (mRem) (mRem) (mRad) (mRad) (mRem) 1st Quarter 1.14 E-2 2.27 E-2 3.14 E-2 2.60 E-1 5.49 E-1 1.99 E-1 2nd Quarter 6.83 E-3 1.59 E-2 9.09 E-2 2.86 E-1 8.13E-l 1.50 E-2 3rd Quarter 6.27 E-3 8. 78 E-3 3.17 E-2 3.07 E-1 8.86 E-1 1.11 E-2 4th Quarter 6.01 E-3 2.89 E-3 4.91 E-2 2.58 E-1 7.70 E-1 4.37 E-3 Annual 3.05 E-2 5.03 E-2 2.03 E-1 1.11 E+O 3.02 E+O 2.30 E-1
Attachmen*
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 November 5, 1985.
- a. Surry Station radioiodine and particulate sample location has been moved from its onsite protected area location to a site boundary location of highest annual average D/Q. The new location provides redundant monitoring for near site boundary sampling of radioiodines and particulates as required by Surry Technical Specification Table 4.9-3.
- b. The location of the North North East(06) environmental TLD location, as indicated by degrees from true north, has been changed to reflect proper direction.
- c. 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. 888.360 REQUEST TO CHANGE PROCEDURE 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 ~ e:,cc:H D ANNUNCIATOR D IN-SERVICE INSPECTION _d HEALTH PHYSICS D---------
D
[I CALIBRATION D CJ MAI NT.ENANCE *O SPECIAL TEST D---------
o _________
CHEMISTRY NON-DESTRUCTIVE TEST D START.-UP TEST PROCEDURE NO: 2 UNIT NO: 3 REVISION DA TE: 4 I .Jue.
TITLE: s CHANGE REQUESTED: (GIVE ST~E' ..NUMBER, EXACT SUGGEST!=:D WORDING, AND LIST REFERENCES. STAPLE COPY OF 6 PROCEDURE, WITH SUGGESTED CHAIIGES MARKEO,-TO-tHIS FORM.I
REFERENCES:
~,o.a.
. R.EASON FOR CHANGE: 7 e.ttAPU0--"--6:.A.u.*& ... o.l!"' ... ~ Lcc.AT* *-~-.M(AIJC 0 0
- r ta 1T.&..-4AJ.9.'Y..A..&1..c..T. t8M..,,,.N&w_
Irr S.1°"1'.liie :1l,..c,42&)A"4' Lot,.&TU>C, 4'~ H1°,.tt:ti-zr -P/9, 'Su...,_,'f 6us,1T<<
9 ACTION TAKEN: 10
-* . \',t *: * .. *-.: ; ...: .--. : .
uov f 3'ms*
DOES THIS CHANGE THE OPERATING METHODS AS De5f~l~9'~N THE "FSAR?
1 DYES c:r;.o DOES THIS CHANGE INVOLVE A CHANGE TO THE TE'e'1UM~~" RECORDS DYES [B"No DOES THIS CHANGE INVOLVE A POSSIBLE UNREVIEWED SAFETY QUESTION? l~ YES [;.,t"NO
- IF ALL "NO", NO "SAFETY ANALYSIS" IS REQUIRED, IF ANY "YES", A "SAFETY ANA.LYS1s* IS REQlJIRED. (IOCFRS0,591 II
[J DISAPPROVED BY: 12 DATE: 13 14 BV: 15 l:.i.1!TE: 16 3p,,_~-
DISAPPROVED 0 APPROVED AS MODIFIED BY COMMITTEE 18 DATE: 19 NOV 5 1985 ACTION COMPLETED BY: 21 . DATE: 22
'E.. ~~ ~ \\-\~-i~
(1)
PROCEDURE HP-ODCM SURRY POWER STATION NUMBER:
PROCEDURE (2)
DATE: NOV CJ 5 19t3~
HEALTH PHYSICS PROCEDURE (3) l & 2 (4)
TYPE PROCEDURE: UNIT:
OFFSITE DOSE CALCULATION MANUAL (5)
TITLE:
(6)
CONTENTS SECTION
- 1. 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. 01-10-85
- 13. NOV O5 1985
- 14. 07-18-85 Appendix A 06-28-84 Appendix B 06-28-84 ALARA (7 (8)
DATE: /C, 7
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(9) (10)
DATE: / 0-3iJ-
~ NUCLEAR SAFETY AND OPERA.TING COMMITTEE: (11 l
. f?-' .
DATE: NOV 5 1985
HP-01 3 Pagel of 14 NOV O 5 1985 SURRY POWER STATION OFFSITE DOSE CALCULATION MA1'UAL SECTION 13 Radiological Environmental Monitoring Locations Part Subject l Land Based Samples 2 2 River Based Samples 8 3 Figures
HP-OL J Page 2 of 14 1.0 LAND BASED SAMPLES D NOV IJ 5 1985 Particulate and Charcoal Air Samples Hog Island Reserve (HIR) - Route 650 to Hog Island Reserve, end of dirt road of reserve. On Virginia Power pole on right side of road.
Bacon's Castle (BC) - 50 yards back on Rt. 617 from intersection ot Rt. 617 and Rt. 10 on Virginia Power pole near Addison's Grocery #2.
Alliance (ALL) - Route 10 to Route 634 north; 1. 4 miles on Virginia Power pole on right side of road.
Colonial Parkway (CP) - Take Route 31 from James River Ferry, Jamestown, to Route 359. Take Colonial Parkway for approx. 2. 9 miles; sampler on right side of road on Virginia Power pole.
Dow Chemical - Route 60 east to Dow Chemical Road at Badische Corp. sign. Follow road parallel to railroad tracks. At first curve in road, turn left at substation. Air sampler inside substation.
/
( Fort Eustis (FE) - Route 60 east to Fort Eustis entrance road.
Straight to circle, first right out of circle onto Lee Blvd. Left on Harrison Road to stop sign; .continue on Harrison Road to small railroad house on left.
Virginia Power pole by this house on left.
Newport News (N.N.) - Route 60 east (Warwick Blvd.) to 34th Street. Left on 34th Street, one block to Jefferson Avenue, left on Jefferson Avenue.
Sampler inside Virginia Power substation.
Surry Station (SS) - Sampler located at . site boundary between TLD iocation 04 and 05.
Environmental TLD' s 6 Control= (00) Control TLD located in shield in count room.
Surry Station - (01) See air sample location Surry Power Station West North West - (02) Located on the center, rear fence of the sewage treatment plant.
Station Discharge - (03) End of discharge structure.
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HP-t 13 Page HI of 14 RADIOLOGICAL SAMPLING STATIONS DISTANCES AND DIRECTION FROM UNIT fll .
CONTAINMENT NO\I O ~ \9SS SAMPLE DISTANCE MEDIA LOCATION (MILES) DIRECTION DEGREES REMARKS Air Charcoal Surry Station .37 NNE 15° Site Boundary and Particulate Location at Sector with Highest D/Q Hog Island Reserve (HIR) 2.0 NNE 26° Bacons Castle (BC) *4.5 SSW 202° Alliance (ALL) 5.1 WSW 248° Colonial Parkway (CP) 3.7 NNW. 330° Dow Chemical (DOW) 5.1 ENE 70° Fort Eustis (fE) 4.8 ESE 107° .
Newport News (NN) 16.5 ESE 122° Control Location Environmental Control (00) Onsite **
c** TLD's West North West (02) 0.17 . WNW 292° Site Boundary- I Surry Station Discharge(03) 0.6 NW 309° Site Boundary I I
North North West* (04) 0.4 NNW 330° Site Boundary North (05) 0.33 N 357° Site Boundary North North East North East (06)
(07) 0.28 0.31 NNE NE 22° 45° Site Boundary Site Boundary I
East North East (08) 0.43 ENE 68° Site Boundary East (Exclusion) (09) 0.31 E 90° Onsite West (10) 0.40 w 270° Site Boundary West ~outh West. (11) 0.45 WSW 250° Site Boundary South West (12) 0.30 SW 225° Site Boundary South South West (13) 0.43 SSW 203° Site Boundary
HP-L Page 14 of 14 RADIOLOGICAL SAMPLING STATIONS DISTANCES AND DIRECTION FROM UNIT #1 ~ov o s \98:i CONTAINMENT SAMPLE DISTANCE MEDIA LOCATION (MILES) DIRECTION DEGREES REMARKS Clams Hog Island Point 2.4 NE 52° Jamestown 5.1 WNW 300" Lawnes Creek 2.4 SE 131° Oysters Deep Water Shoals 3.9 ESE 105° Point of Shoals 6.4 SSE 157° Newport News 12.0 SE 140° Crabs Surry Station Discharge 0.6 . NW 312° Fish Surry Station Discharge 0.6 NW 312° Shoreline Hog Island Reserve 0.8 N . 50 Sediment Burwell's Bay
- 7. 76 SSE 167°
- Onsite Location - in Lead Shield.
- Onsite sample of Well Water - taken from tapwater at Surry Environmental Building.
(
Attachment 4 REVISIONS TO THE PROCESS. CONTROL PROGRAM (PCP)
- 1. A revision to the Process Control Program was approved by the Station Nuclear Safety and Operating Committee on October 29, 1985.
- a. The processing of wet wastes to eleminate the presence of free standing liquids has been changed to include the use of approved absorbent materials. Changes also include the definition and description of the absorption process, surveillance requirements and processed waste acceptability requirements.
- b. The stabilization of spent mechanical filter elements by encapsulation process has been deleted. Spent filter elements will be encapsulated in cement to eliminate free standing liquids, then placed into high integrity containers for stabilization and shipment, as required by 10CFR61.56 and burial site criteria.
- c. References to criteria used to determine waste classification have been changed to reference 10CFR61.55 waste classification.
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No. BBB.36D REQUEST TO CHANGE PROCEDURE SURRY POWE_R STATION VI_RGINIA ELECTRIC AND POWER COMPANY TO SUPERVISOR RESPONSIBLE FOR FOLLOWING PROCEDURE:
D ABNORMAL D CURVE BOOK D OPERATING D)"'.ELDING D ADMINISTRATIVE D EMERGENCY D PERIODIC TEST ~.PveCE$$ CASna,, P~,1Nl D ANNUNCIATOR D IN-SERVICE INSPECTION 0 HEALTH PHYSIC!'.
D----------
D CALIBRATION D MAINT*ENANCE - D SPECIAL TEST D - - - - - - - - -_-
D CHEMISTRY D NON-DESTRUCTIVE TEST D START-UP TEST
- o ______
PROCEDURE NO: 2 UNIT NO: REVISION DA TE: 4
//- z.
TITLE*
CHANGE REQUESTED:
1,J~ wA-:s-n;- 7?e~cess (GIVE STEP NUMBER, EXACT SUGGESTED WORDING, AND LIST REFERENCES. STAPLE COPY OF 5
6
- PROCEDURE, WITH SUGGESTED CHANGES MARKED, TO THIS FORM.I RECEIVED
REFERENCES:
,~ov o5 1985
.STATION. RECORDS 7
CHANGE REQUESTED BY: B 9 ACTION TAKEN: 10 DOES THIS CHANGE THE OPERATING METHODS AS DESCRIBED IN THE FSAR? YES DOES THIS CHANGE INVOLVE A CHANGE TO THE TECH. SPECS.? YES DOES THIS CHANGE INVOLVE A POSSIBLE UN REVIEWED SAFETY QUESTION? YES IF ALL "NO", NO "SAFETY ANALYSIS" IS REQUIRED. IF ANY "YES", A "SAFETY ANALYSIS" IS REQUIRED. (10CFRS0.S9l.
RECOMMENCED ACTION: 11 D DISAPPROVED BY: 12 ,.- 13 s
REVIEWED 14 BV:
D J.5 o.~.TE:
APPROVED AS MODIFIED BY COMMITTEE 16 Jo?
CHAIRMAN SIGNATURE: 18 CATE: 19 OCT 2 9 1985 NEW PROCED.URE REVISION CATE:
ACTION COMPLETED BY: 21 .. CATE: 22
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(l)
PROCEDURE Process SURRY POWER STATION NUMBER: Contr. Prog.
PROCEDURE (2)
DA.Tr.: . OCT 2 9 1985 (3) (~)
lTP:E PROCEDURE: PROCESS CONTROL PROGRAM 1 & 2*
(5) nn.r.: RADIOACTIVE WASTE PROCESS CONTROL PROGRAM (6)
CON'!ENTS SECTION
- 1. Scope and Purpose
- 2. Definitions
- 3. System and Process Descriptions
- 4. Waste Sources and Characteristics
- 5. Sampling, Analysis and Process Surveillance
\
- 6. Contractor Services/Station Interface and Requirements
- 7. Station Records
- 8. References FOR Think ALARA (8)
DATE: t.tJL~
7 l
/t.r (9) (lO) v._j DATE: "fic:q'i:S:
(11) l OCT 2 9 19~:.
DATE:
PCP-1, OCT 2 9 \98.S Surry Power Station Radioactive Waste Process Control Program Table of Contents
'\
1.0 Scope and Purpose 2.0 Definitions 3.0 System and Process Descriptions 4.0 Waste Sources and Characteristics 5.0 Sampling, Analysis and Process Surveillance 6.0 Contractor Services/Station Interface and Requirements 7.0 Station Records 8.0 References DNl'
PCP-2.(
OCT 2 9 1985 SURRY PO~TER STATION RADIOACTIVE WASTE i PROCESS CONTROL PROGRAM I 1,0 Scope and Purpose The Process Control Program (PCP) for Surry Power Station provides the minimum requirements and guidelines to be followed to assure that "wet" radioactive wastes are processed and packaged in accordance with all Federal and State regulations.
The program encompasses those forms of radioactive wastes as defined in section 2.0 and establishes the processing parameters through sampling, testing and determinations, to ensure an acceptable product for trans-portation and burial.
Methods will be provided to assure that waste solidification/dewatering systems are operating properly and to substantiate an acceptable solidi-fied/dewatered and/or absorption process product.
The Process Control Program shall be implemented by all personnel who operate dewatering and solidification equipment and/or control absorp-tion processing, collect and process samples used to establish process para.meters and those who prepare documentation for shipping of radioac~
tive wastes.
PCP-3.
OCl 2 9 95 2.0 Definitions 2.1 Batch - A discrete quantity of waste material exhibiting certain chemical and physical properties which may be considered a homogeneous mixture for the purposes of sampling, testing and processing.
2.2 Sample - A. reasonably representative aliquot of a batch, as defined above, to be obtained for the purpose of deter-mining/verifying solidification parameters, absorption processing or radioactive constituents.
2.3 Direct Measurements/Analysis - The methodology used to quantify the radioactive concentrations
- existing in the waste.
Direct gamma spectroscopy measurements/ analysis of the waste form itself and/or the acquisition of samples for subsequent measurement/ analysis, constitutes an accept-able means of quantifying the radioactive content of the waste.
2.4 Indirect Measurements/Analysis - The methodo.logy used to estimate I
the radioactive concentrations existing in the radioac-tive waste. A representative composite of the waste stream influent and effluent concentrations may be considered a reasonably representative sample for the purpose of performing radiological analysis. For radio-isotopes not readily measured, the establishment of an inferential measurement program to allow the ratios of readily measurable isotopes to those not easily*measured, may also constitute an acceptable means of performing rad~ol~gical content analysis.
PCP-4.
OCi f. 9 \98S 2.0 Definitions [continuedj 2.5 Wet Wastes - Those forms of radioactive materials normally gener-ated as by-products from* the liquid waste processing systems, including spent bead resins and filter elements which contain greater than one half percent by volume of liquids per container.
In addition, wet wastes will also inclu_de radioactively contaminated oily wastes that require disposal at a licensed facility.*
- 2. 6 Solidification - Solidification is the conversion of radioactive wet waste to a homogeneous, monolithic, immobilized free standing solid, with a detinite volume and shape.
2.7 Absorption process - The use of absorbent material to eliminate the presence of free standing liquid in wet wastes.
2.8 High Integrity Container - A container that has been certified to meet the requirements of burial site criteria tor waste form stabilization, which may be used in lieu of solidi-fication.
ONL,1
PCP-5.
OCi ~~ \9SS 3.0 System and Process Descriptions Burial ground requirements for waste stabilization, and elimination of free standing liquids are complied with by processing the wet wastes via the following systems and/or methods:
3.1 Dewatering System
- The Dewateririg System consists of a dewatering container (usually a shipping container), a dewatering pump and associated hose and piping. Station personnel use the foll~ng procedures, approv~d by the Station Nuclear Safety Operating Committee, to transfer and dewater spent resins in preparation for shipment or solidifica-tion:
Station Procedure OP-20 ._1.1, Resin Was_te System - Transfer-ring spent resin from primary demineralizer to shipping
) . container I
(. - Station Procedure OP-22.9.5, Liquid Waste receiving, filling and dewatering a spent media receiving container The above procedures specify (or reference) the minimum time periods for dewatering pump operation, settling* time and subse-quent verification that the waste contains "no detectable free standing liquids" as required by *applicable radioactive waste burial ground license conditions.
These procedures also require .that each step be initialed, . thus insuring that the operating personnel comply with the dewatering procedures and document their completion.
ONLY
PCP-6 .l 3.0 Svstem Description [continued]
3.2 Solidification System
.Wet wastes, as defined in Section 2.0, which are classified, pur-suant to 10CFR61.55, as Clas~ B or Class C wastes, shall be solidified prior to burial or disposed of in approved high inte-grity containers.
- Surry Power Station currently has no installed solidification system onsite to process wet wastes. In the event that such processing is required, an outside contractor will provide a solidification system to the Station. The contractor shall also furnish to the Station a system description, system operating procedures that specify the process control parameters, and a copy of the *topical report or equivalent documentation indicating compliance with 10CFR Part 61 and burial site requirements.
Solidification parameters may include but are not limited to waste pH, waste/liquid/solidification agent/catalyst. ratios,. waste oil content, and mixing and curing _times. Once established, the process control parameters will provide boundary conditions which assure solidification will be complete and that the requirements for waste form stability and for no detectable free standing liquids are met.
PCP-7.
3.0 System Description [continued]
3.2 Solidification System [continued]
The system operating procedures for solidification and a copy of the topical report or equivalent documentation will be submitted to the Station for determination of compliance with the Process Control Program. Upon approval by the Station Nuclear Safety and Operating Committee, the procedures will be incorporated into the appropriate Operations and/or Health Physics Procedures as an
, attachment or by reference *.
The solidification system will not be considered operable until the operating procedures are approved by the Station.
The topical report or equivalent document must be reviewed by the Station prior to the performance of any solidification processing.
3.3 Absorption Processing Wet wastes, including oily wastes, as defined in Section 2. 0, meeting the criteria for Class A wastes, as per 10CFR 61.55, may be processed by absorption to eliminate free standing liquids.
Sufficient absorbent shall be . used to ensure that the waste contains "no detectable free standing liquids" prior to sealing the container.
Processing of such wastes with absorbents shall be performed in compliance with procedures approved by the Station Nuclear Safety Operating Committee" and only with materials approved by the burial site.
PCP-8.
4.0 Waste Sources and Characteristics 4.1 Bead Resin Four (4) systems currently exist at Surry Power Station for processing radioactive liquids.
4 .1.1 The Liquid Waste Processing System processes radioactive liquids normally associated with primary and secondary leakage which are collected from various sumps/tanks and transferred to the high and low level waste tanks for processing. Liquids collected in these waste tanks are pumped through one or more trains of filters and/ or ion exchange resins and transferred to the liquid waste test tank. The liquid waste tank is isolated, recirculated, sampled and analyzed for radioactive content. 'l'he tank may then be released to the discharge canal provided the radioactivity is within the release limits.
4.1.2 The Primary Coolant System is purified by processing the letdown flow through the letdown filters and one of two mixed bed demineralizers. 'l'he mixed bed is a combination of anion and cation bead resin, used for removal of fission and corrosion products. A cation bed is used intermittently to adjust primary coolant pH by removal of L.i-7 and a deborating demineralizer (anion resin) used to reduce boron concentrations. Primary coolant is passed through a post resin filter, then returned to the system through the volume control tank.
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PCP-9.
4.0 Waste Sources and Characteristics [continued]
4 .1 Bead Resin [continued]
4.1.3 The Boron Recovery System processes primary vents and drains for the purpose of recycling or disposal of boric acid and removal of gaseous products. Liquids are pumped from the primary drains tanks to the Gas Stripper System, through the Cesium Removal Ion Exchangers (cation resin),
the Boron Recovery Filters and finally to the Boron Recovery Tanks.
4.1.4 The Spent Fuel Pit Purification System provides a means to cool the Spent Fuel Pit water. The purification system is a closed system, circulating spent fuel pit water through a heat exchanger, a filter element and ion exchanger (anion/cation resin), and discharging back into the fuel pit *
.Resins from theeie various systems are considered "spent" when decontamination factors indicate a significant decrease or when a~tiv:Lty levels reach a pre-determined level. Spent resins are transferred to shipping contain-ers using primary grade water.
Resins will remain in the shipping container while the sluice water passes through a retaining element, dis- .
charging into the liquid waste system.
Bead resins are normally processed by solidification or dewatering. When solidified, the normal solidification agent is cement. When alternate solidification
- agents are used, the description shall be provided in the contractors solidification system operating procedures.
PCP-10 oci is -
4.0 \llaste Sources and Characteristics [continued) 4.2 Filter Elements Mechanical filters with wound fiber cartridges are used for removing particulate matter from liquid systems. Spent filter elements are removed from systems and placed in storage bunkers to await processing and shipment. The filter elements are encapsu-lated in cement to eliminate free standing liquid prior to place-ment in high integrity containers for stabilization and shipment, as required by 10CFR part 61 and burial site criteria.
4.3 Organic Waste Oil used in systems for cooling and lubrication which comes into contact with radioactive contamination, must be processed to ensure compliance with Burial site requirements. Oily waste is generated by system leakage or from normal system replacement and stored until the waste can be processed. Contaminated oily waste shall meet the criteria for Class A, as per 10CFR 61.55 and may be processed, using approved procedures, by
- absorption or solid if i-cation and sealed in a container meeting burial site requirements.
Solidification equipment, materials and procedures will normally be supplied by a contractor.
PCP-11 OCi t9 '98:i 5.0. Sampling, Analysis, and Process Surveillance 5 .1 Collection of Samples At least one representative sample from at least every tenth batch of wet radioactive waste, shall be tested to verify solidification and/or absorption.
For collection and handling of high activity wastes, where han-dling of samples
- could result in personnel radiation exposures inconsistent with AI.ARA practices, representative nonradioactive samples may be used for solidification testing. Nonradioactive samples shall be as representative as possible to the actual waste with regard to chemical properties.
Samples of actual waste are also used for direct radiological analysis to determine waste classification .in accordance with 10CFR 61.55. Samples should be drawn reasonably close to date of shipment or date of processing
- 5.2 .Analysis
.Analysis shall be performed on radioactive waste to define process.
control parameters, prior to waste solidification. The type of analysis to be performed on waste samples will be dependent on the specific solidification operation procedures submitted by contrac-tor services. Results of analysis will be recorded. on 'Waste Solidification Data Sheets, contained in solidification operating procedures.
Samples of wet waste, taken to determine isotopic content, shall be analyzed for major gamma emmitters by radioassay techniques in accordance with approved Health Physics Procedures.
PCP-I:..
OCi t9 \9!S 5.0 Sampling, Analysis, and Process Surveillance [continued]
5.3 Process Surveillance 5.3.l _ If any sample, taken to verify solidification, fails to solidify* the solidification batch under test shall be suspended until such time as additional samples can be obtained, alternative solidification parameters can be determined in accordance with the Process Control Program or its supporting procedures. and
- a subsequent test verifies solidification. Solidification of the batch may then be resumed using the alternative solidification parameters determined.
If the initial sample from a batch of waste fails to verify solidification, then representative samples shall be collected from each consecutive batch of the same type
. of wastes until three consecutive initial test specimens demonstrate solidification. The Process Control Program and/ or its supporting procedures shall be modified as required to ensure solidification* of subsequent batches of waste.
5.3.2 If the waste is
- processed by absorption. a test sample shall be obtained from at least one of every ten batches to verify ratios of absorbent to wet waste volumes are adequate to ensure complete elimination of free liquids.
If a test sample used to verify absorption shows free standing liquid. then the batch under test
- shall be suspended until such time that the procedures can be modified to ensure sufficient absorption to eliminate any free standing liquids.
PCP-13.
OCi t 9 '9SS 5.0 Sampling, Analysis, and Process Surveillance [continued]
5.4 Acceptance Criteria 5.4.1 Solidification.Acceptability The following criteria define an acceptable solidification process and process parameters:
Sample
- solidifications used to verify batch solidifica-tion will be considered acceptable if there are no visible or drainable free liquids.
Sample solidifications are considered acceptable if upon inspection the waste will retain its shape when removed from the test container.
Solidified containers of actual waste shall be inspected to ensure proper curing (i.e.hardness) prior to closing.
5.4.2 Radioassay Acceptability - The results of the -radioassay
- are considered acceptable. when it has been verified and documented that the waste material is packaged in a container which is acceptable for transportation and burial. considering the radioactivity concentrations which exist in the waste,. Strong-tight containers are acceptable for waste meeting Class A criteria of 10CFR. 61.55 with no free standing liquid. High integrity containers or solidification is required for Class Band Class C wastes.
PCP-14 OCT t 9 ~S 5.0 Sampling, Analysis, and Process Surveillance [continued]
5.4 Acceptance Criteria lcontinued]
5.4.3. Dewatering Acceptability Procedures for dewatering containers are specified in Section 3 .1. These proce-dures specify the minimum time periods for dewatering pump operation,. settling time and subsequent verification that the waste contains ":No detectable free standing liquids" (less than 1% by waste volume).
5.4.4 Absorption Acceptability - S~les used to verify proper absorption will be considered , acceptable if there are no visible or drainable free liquids.
I L_
PCP-15 OCi t9 -SSS 6.0 Contractor Services/Station Interface and Requirements Currently there is no installed solidification system onsite to process wastes that require solidification. In the event such services* are required, a contractor will be requested to submit, for. approval, solidification system operating procedures, a list of physical inter-faces, materials required, and a list of expected utility/contractor responsibilities.
The solidification system operating procedures will be reviewed in accordance with the Process Control Program to determine adequate station control and Quality Assurance criteria are met. Once approved by the Station Nuclear Safety Operating Committee, the system operating procedures will be incorporated into, or referenced by existing Health Physics and/or Operations Controlling Procedures.
A copy of the topical report or equivalent documentation indicating compliance with 10CFR Part 61 and burial site requirements must be reviewed prior to performing solidification processing.
PCP-16 OCi 2 9 19BS 7.0 Station Records 7.1 Process Documentation Station records shall.be maintained, to document that the dewater-ing and solidification process was carried out in accordance with the Process Control Program. Applicable procedures specified in Section 3.0 1 a copy of the topical report or equivalent documenta-tion provided by the contractor, and the contractor.'.s operating procedures utilized during solidification, will be retained.
Data sheets shall be used to record test sample solidification data. The data sheets may include but are not limited to, type of waste to be solidified, major const; ..:uents, pH, waste/liquid/so-lidification agent/catalyst ratios, waste oil content, mixing and curing times.
Data sheets should also include batch number, batch volume, and date processed for each ba.tcb solidificatiotl and/or absorption.
Station records shall be maintained for any Direct or Indirect Measurements/Analysis performed on the waste material.
PCP-17 OC1 2 9 1985 7.0 Station Records [continued}
7.2 Changes to Process Control Program Changes to the Process Control Program shall.be submitted in the Semi-annual Radioactive Effluent Report. The report shall include detailed information that totally supports the rationale for the change, determination that the change did not reduce the overall conformance of the solidified waste product to the existing criteria for solid wastes,
- and documentation that it has been reviewed by the Station Nuclear Safety Operating Committee.
Changes to the Process Control Program _shall become effective upon review and acceptance by the Station Nuclear Safety Operating Committee.
PCP-18 .l OC'I' t 9 198S 8.0 References 8.1
- Surry Power Station Technical Specifications 8.2 State of South Carolina Radioactive Materials License No. 097. and
('
amendments 8.3 Surry Power Station Operating Procedures 8.4 Branch Technical Position - ETSB 11-3 8.5 State of Washington Radioactive MateTials License No. WN-1019-2, and amendments 8.6 10CFR Part 20, Paragraph 311 8.7 10CFR Part 61, Paragraphs 55 and 56 ONL~
Att, ~nt 5 Pagl:. i l 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 July l, 1985 through December 31, 1985.
Attachment f 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 Table.s 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 July 1, 1985 through December 31, 1985. They are the Component Cooling Service Water Monitor, Unit #2 Discharge Tunnel 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. Design Change 84-25, which was to install 11 Snow-Plow 11 type radiation monitors on the exterior of each of the four Heat Exchanger Service Water outlets is currently being re-evaluated. 11 Snow-Plow 11 type monitors have been found to be insufficiently sensitive for this type of application.
Engineering is reviewing alternate radiation monitoring schemes and/or the feasibility of proposing Tech Spec changes to require periodic Service Water sampling in lieu of a revised Radiation Monitoring scheme.
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 this matter is resolved.
- 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 required 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 was completed on September 11, 1985. The monitor was returned to service on September 16, 1985.
All Effluent Releases via this pathway were diverted to the Unit # 1 Discharge Tunnel during the period when Unit #2 Discharge Monitor was out of service.
- 3. Replacement of the Waste Gas Holdup System Oxygen Monitors as per EWR 84-266 was completed on February 14, 1986, however difficulties have been encountered with the calibration of these monitors. Engineering is working to resolve the calibration difficulties with the Instrument Department.
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. Grab sampling will continue to satisfy the monitoring requirements until the calibration problems have been resolved.
Attach.me
, Page l of UNPLANNED RELEASES There has been no Unplanned Liquid or Gaseous Releases that exceeded Technical Specific-ation 3.11.A.l.a or 3.11.B.l.a during the period of July 1, 1985 through December 31, 1985.
VIRGINIA ELECTRIC AND POWER COMPANY RICHMOND, VIRGINIA 23261 i'
1 1U "
. - il J W. L. STEWART VICE PRESIDENT NUCLEAR OPERATIONS February 28, 1986 Dr. J. Nelson Grace Serial No.86-122 Regional Administrator NO/ETS/acm Region II Docket Nos. ~@:_01.C U.S. Nuclear Regulatory Commission 50-281 Suite 2900 License Nos. DPR-32 101 Marietta St., N.W. DPR-37 Atlanta, Georgia 30323 Gentlemen:
VIRGINIA ELECTRIC AND POWER COMPANY SURRY POWER STATION UNIT NOS. 1* AND 2
{SEMI;;ANNUAL']W>lOACTIVE :EFFLUENT .RELEASE*. REPORT-Enclosed is the Surry Power Station Semi-Annual Radioactive Effluent Release Report for July. 1, 1985 through December 31, 1985. The report, submitted pursuant to Surry Power Station Technical Specification.
6.6.B.3, 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, 0l~
W. L. Stewart Q>>.._~Ls/r )-8~ .
Enclosure fV_fWur ,1'Y0~j/)1i cc: Mr. -Roger D. Walker, Director 5c-d-F0 ~-,vt(
Division of Reactor Projects NRC Region II fu;,Jtw~
Mr. Lester S. Rubenstein, Director PWR Project Directorate #2 Division of P~ Licensing-A Mr. Donald J. Burke NRC Senior Resident Inspector Surry Power Station Mr. Terence L. Chan NRC Surry Project Manager PWR Project Directorate #2 Division of PWR Licensing-A