ML18113A584

Steam Generator Repair Prog for Subj Facil.Rev Contains Supplemental Info Requested by NRC Staff

ML18113A584
Person / Time
Site:	Surry
Issue date:	10/25/1978
From:	VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
Shared Package
ML18113A583	List: ML18113A581 ML18113A584
References
NUDOCS 7810270223
Download: ML18113A584 (9)

Text

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• STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NOS. 1 AND 2 REVISION 7 INSERT Title Page/ I Page 9.A.4-:l THle Page~ Page 9.A;4-1 Page 9.A.4-2 Page 9.A.5-3\./

Page 9.A.5-5 Page 9.A.8-3 V Page, 9 .A. 9-2 /' Page 9.C.3-1 V .~ Page 9.A.5-3 ..___....-1 Page 9.A.5-5~ Page 9.A.8-3 Page 9.A.9-2 Page 9.A.3-1"'

P°c3e.. C\, C, '3~2 { I __J

• ** / STEAM GENERATOR REPAIR PROGRAM FOR THE SURRY POWER STATION UNIT NOS. 1 AND 2 Docket Nos. 50-280 Z 50-281 License Nos. DPR-32 I DPR-37 Is,ued August 17, 1977 R~vised December 2, 1977 R&vised April 21, 1978 I . Revised June 2, 1978 Revised June 13, 1978 Revised June 30, 1978 Revised September 1, 1978 VIRGINIA ELECTRIC AND POWER COMPANY

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.;;IVUI J .n.-Y I Ll -REV. 6 ~'1,A,,~\

-* ** A.4. Estimate the quantity of laundry and general decontamination wastes that will be generated during the repair program. Describe the sampling program for this waste. and identify which isotopes will be specifically assayed. If beta emitters such as Fe~55 and Ni-63 are not measured, provide justification for not analyzing for these and other beta emitters which could be present. RESPONSE:

An estimate of the quantity .of laundry waste water and other potential sources of contaminated 1 i quid waste is provided in the response to qu*estion A.5. The sampling program for this waste will be that which is required to implement the requirements of the Technical Specifications and 10 CFR 20. Regulatory Guide 1.21, 11 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 11 serves as a basic . guide for establishi_ng specific isotopes to be reported.

The sampling . gram will be the same as that which is presently in use at the stations.

This program and identification of the specific isotopes reported has been submitted in the Arinual Reports. It is presently not planned to measure such beta emitters as Fe-55 andl 6 Ni-63. The basis for not measuring these isotopes is that: .1. The gross beta activity is reported.

A breakdown by tope only further qualifies the data required . . 2. The techniques required to determine isotope composition beta emitters is complex and its benefit is not commensurate with its cost. 3. Existi_ng regulations can be satisfied by current practice.

-e ** SSGP 9.A.4-2 REV. 6 Sampling for Fe-55 has been addressed in the Standard Technical Specifications For the Implementation of Appendix I, NUREG 0472, May 1978. The Surry Standard Technical Specifications For the Implementation of Appendix I, are scheduled to be submitted on November 11, 1978. 6 e e e ** TABLE:A.5-1 SSGP 9.A.5-3 REV. 6 . 'ESTIMATED'QUANTITIES'AND'SPECIFIC'ACTIVITIES

.. OF 'LAUNDRY.

WASTE. WATER Specific Activity(l)

Tota1(2) *

• Isotope * (uCi/ct} * ** * * *Activity (Ci) Co-58

• 3. 2 X 10-6 2. 66 X l o-*2 Co-60 2.5 X ,a-6 2.085 X 10-2 Cs-137 7.79 X 10-7 6.65 X 10~3 Cs-134 3.65 X 10-7

• 3.04 X 10-3 Mn-54 2.28 X lQ-7 1.9 X 10-3 1.., 131 2.2 X ,a-7 1.84 X 10-3 Cr-51 1.4 X 10-6 1.16 X l o-2 . . . . . . . . . TOTAL 7.25 X 10-2 (1) Based on Surry Power Station data (2) 2,203,200 gallons of laundry water based ~n 12,240 gallons/day

• for 6 mon.ths * (3) All numbers are "per unit 11 6

• * ** TABLE A.5-3 TOTAL ESTIMATED LIQUID EFFLUENTS Source Laundry Wastes Steam Generator Secondary side water Local Decontamination Solutions TOTAL Total 1977 liquid Wastes Total Volume (Gallons) 2,203,200 80,400 18,000 2.3 x 106 gallons 1.4 x 108 gallons SSGP 9.A.5-5 Rev. 2 Total Activity (Ci) 6. 131 '.L 0.22 0.051 6.402 Ci 67.67 Ci

-.e b. **-SSGP 9.A.8-3 REV. 3 The contamination levels for the secondary system components should be less than 1 uCi/cm2 and would result in insignificant releases.

The ~irborne levels in occupied areas of the containment during the replacement activities are expected to be similar to those normally experienced during a refueling outage. Following the movement of the fuel, airborne levels are expected to decrease significantly.

Typical specific airborne activities for a ing outage are listed in Table A.8-1. c. The total effluents from a unit during the replacement activities are shown in table A.8-2. These effluents will be much less than that normally experienced during routine operation as can be seen in Table A.8-2. Therefore, the maximum individual doses are lation doses will be much less than those during routine operation.

The doses for routine operation have been presented in "Appendix I analysis, Surry Power Station Unit Nos. 1 and 2 11 , dated June 1977, submitted June 17, 1977. d. It is presently planned to install a temporary containment lation system that will be equipped with a HEPA and charcoal ter. The capacity of the ventilation system will be 30,000 CFM. The efficiency of the filter has been conservatively assumed to be at least 95 percent for the purpose of these evaluations, though they will be purchased to a specification which requires them to be 99.97 percent efficient.

.. e *-Description Feedwater pipe Main Steam Pipe Primary Moisture Separator Feedwater Ring Thermal Sleeve Telescoping Deck Plate Downcomer Guard Assem-bly Feedwater Nozzle 55.gal. drums (com~ pacted waste) Steam Generator In-sulation

• Concrete B1ocks(2)

Rebarred Concrete Upper Steam Gene-rator Support rings Support Ring Keys TOTAL TABLE.A.9-1 SOLID WASTE ESTIMATE {all values per unit) ¥Ws¥ Volume s {ft3) 540 37. 71 2,400 63.81 66,000 3,520.5 6,300 94.5 600 8.4 9,000 652.2 102,000 7, 182 2,100 19.2 416,000 7,644 14,900 966 193,050 1,350 14, 125 94.5 29,400 60 3,400 7.0 878,165 26,236 SSGP 9.A.9-2 Rev-. 2 Estimated Activitl {Ci) <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 <0.03 6.5 <0.03 <0.03 <0.01 <0.03 <0.03 6.9 ( 1 ) 1040 drums of compacted waste, includes trash, disposable protective equipment, rags, etc. (2) Biological shield wall

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-** ** ' .. REV. 6 SSGP C\,C:,'3-\ C.3. If decontamination is necessary, demonstrate that the methods and the decontamination solutions will not degrade or adversely affect the reactor coolant piping or components which are part of the primary system pressure boundary.

Further show that the nation solutions will not have deleterious latent effects in quent plant operations.

RESPONSE:

At the present time it is only *planned to decontaminate the removed tions of reactor coolant pipe for reuse. The method of decontamination*to be used will be electropolishing.

Electropolishi_ng has been widely used in the chemical industry to clean and prefinish chemical piping and process systems. The techniques for ing are over JO yeais old and have been tried and proven to be technically sound. The wastes created by this process consist of two (2) 55 gallon drums of solid wastes.and 300 gallons of water. The electrolyte or decontamination solution will be removed from the site by the decontamination contractor for reuse. 6