Text

Semiannual Effluent Release Rept for Yankee Atomic Electric Co,For First & Second Quarters 1989
	ML20246H651
Person / Time
Site:	Yankee Rowe
Issue date:	06/30/1989
From:	Papanic G; YANKEE ATOMIC ELECTRIC CO.
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	BYR-89-131, NUDOCS 8909010327
	Download: ML20246H651 (61)
	v • d • e

{{#Wiki_filter:.. Is i YANKEEATOMICELECTRlCCOMPANY 'fl "yo'"gio','*;"l" j i 580 Main Street, Bolton, Massachusetts 01740-1398 l '. v.E E K 1 August 29, 1989 BYR 89-101-j 1 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555'

Reference:

(a) License No. DPR-3 (Docket No. 50-29)

Subject:

Semiannual Effluent Release Report

Dear Sir:

Enclosed are the tables summt.rizing the quantities of radioactive liquid and: gaseous effluents, and solid waste released from Yankee Nuclear Power-Station at Rowe, Massachusetts for the first and second quarters of 1989. This information is submitted in accordance with Technical Specification 6.9.6.b. We trust that this information is satisfactory; however, should you have any questions,.please contact us. Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY Georg'Papanic,Jr! Senior Project Engineer - Licensing GP/gbc cc: USNRC Region I USNRC Resident Inspector, YNPS 8 I 8909010327 090630 PDR ADOCK 05000029 R PNV t _ - _ ________ __ _ _ _ _ ______ _ _______ __ _ a

r- .. g, A g.. .s i EFFLUENT AND WASTE DISPOSAL SEMIANNUAL REPORT FOR FIRST AND SECOND QUARTERS, 1989 Yankee Atomic Electric Company Rowe, Massachusetts 7986R

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.n:. - TABLE 1A 1 .x Yankee Atomic Electric Company. Rowe. Massachusetts ~ Effluent and Waste Disposal Semiannual Rengri First and Second'Ouarlers. 1981 Gaseous Effluents - Summation of All' Releases Unit Quarter. -Quarter; .Est. Total _. l' '2 Error. % 'A. Fission and Activation Gases-

1. Total release ci 1.02E+01 1.98E+01 5.50E+01

2. Averare release rate for'oeriod-uCi/sec 1.30E+00 2.52E+00 3.-Percent of Tech. Spec. limit (1)(4) %

1.50E-0) 2.50E-01 B. Iodines

1. Total Iodine-131 Ci

<8.89E-07 4.17E-07 2.50E+01

2. Average release rate for period' uci/see~<1.13E-07 5.30E-08

3. Percent of Tech._ Spec. limit (2)(4) %

3.57E-01 5.29E-Oi C. Particulate

1. Particulate with T-1/2 > 8 days ci 3.66E-05 4.97E-06~

' 3.00E+01

2. Average release rate for period uCi/sec 4.66E-06 6.32E-07

3. Percent of Tech. Spec. limit (3)-

(3)

4. Gross alpha radioactivity Ci (7.62E-08 8.02E-09 D. Tritium-

1. Total release ci 2.51E+00 1.22E+00 3.00E+01 2.'Averare release rate for period uCi/sec 3.19E 1.55E-01

3. Percent of Tech._ Spec. limit (3)

(3) '(1) Technical Specification 3.11.2.2.a for gamma air dose. Percent values for Technical Specification 3.11.2.2.b for beta air dose are approximately the same. (2) Technical Specification 3.11.2.3.a for dose from I-131, Tritium, and radionuclides in particulate form. (3)~ Per Technical Specification 3.11.2.3, dose contribution from Tritium and particulate are included with I-131 above in Part B. (4)' The first and second quarter percent of Technical Specification limits are based on' conservative plant quarterly dose determinations. 7986R i _-_____-___-____________a

46 '^ 6 n-TABLE IB +. Xankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste Disposal Semiannual Report First and Second Ouarters. 1981' Gaseous Effluents - Elevated Release Continuous Mode Batch Made Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 1 2 =

1. Fission Cases Krypton-85 Ci 3.36E-03 4.22E-03 Krypton-85m C1 1.02E-01 2.19E-01 Krypton-87 Ci 1.27E-01 2.50E-01 Krypton-88 Ci 2.14E-01 4.24E-01 Xenon-133 Ci 2.00E+00 5.52E+00 Xenon-135 Ci 2.86E+00 5.20E+00 Xenon-135m Ci-4.59E+00 7.58E+00 Xenon-138' Ci 5.42E-02

-1.67E-01 Xenon-133m Ci 3.92E-Q2 1.08E-01 _. Argon-37 C1 1.28E-02 3.17E-02 Argon-41 Ci 2.49E-01 3.24E-01 ' Carbon-14 Ci 6.72E-04 8.44E-04 Xenon-131m Ci 6.30E-03 1.74E-02 Unidentified Ci Total for' period C1 1.02E+01 1.98E+01

2. Iodines Ic' ge-131-C1

<8.89E-67 4.17E-07 Iodine-133 Ci (1.03E-06 <8.59E-07 ' Iodine-135 01 ' <2.31E-07 <3.87E-07' Total for. period C1 <2.15E-06 4.17E-07

3. Paffi,ulates

__ b_.,ntium-89 C1 5.06E-07 <2.15E-07 Strontium-90 C1 2,86E-09 (4.20E-08 Cesium-134 Ci 6.1BE-07 <3.04E-07 Cesium-137 C1 1.10E-06 6.81E-07 Barium-Lan thanum-140 Ci <1.34E-06 <1.12E-06 -l Zinc-65 Ci <1.04E-06 <7.46E-06 Cobalt-58 Ci 3.37E-06 3.25E-08 ) Cobalt-60 01 1.66E-05 4.20E-06 ) Iron-59 C1 1.15E-06 <6.35E-07 Chromium-51 Ci 3 49E-06 <1.86E-06 Zirconium-Niobium-95' Ci 3.64E-06 <5.50E-07 Cerium-141 Ci 8.21E-07 <2.56E-07 Cerium-144 C1 1.40E-06 <1.11E-06 Antimony-124 C1 (4.29E-07 (2.85E-07 ... Manganese-54 Ci 3.38E-06 5.50E-08 i Silver-110M Ci (4.18E-07 <2.87E-07 Molybdenum-99 Ci <2.77E-06 <2.11E-06 Rathenium-103 Ci 5.34E-07 <2.60E-07 Total for period Ci 3.66E-05 4.97E-06 7986R.

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.r ,w M - Ya'kee Atomic Electric Comoany.-Rowe. Massachusetts n p q Effluent and Waste Disposal'Samiannual Report.. Fihst and Second Ouarters.'1989 ~" Gaseous Effluents - G$ound Level Releases .i ~ There were' no routine' measured ground level' continuous' or batch mode gaseous .} releases during the.first or second quarters of'1989. ? t -) I l 1 7986R + 4- ..________m.m_ .-.-m_. _ _ _ _. _ _ -. _. ___ ___.._.___._ _ _. _ _ _ _ __. _.

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1 s Y 4. TABLE 2A I i Yankee Atomic Electric Company. Rowe. Massachusetts Effluent and Waste Disqngal Semiannuni Report a first and Second Ouarters. 1989-Liould Effluents - Summation of All Releases 1 Unit Quarter Quarter. Est. Total-5 1 2' Error. % ' A. Fission and Activation Products ? i

1. Total release (not including tritian. 2Ases. alphal Ci 9.33E-03 1.56E-02 2.00E+01

2. Average diluted concentration j

durine oeriod uCi/ml 8.26E-11 1.26E-10

3. Percent of apolicable limit (1) 9.10E-05 7.82E-05 i

B. Tritium 5.Totalrelease Ci 1.99E+01 4.59E+01 1.00L+01

2. Average diluted concentration during period uCi/ml 1.76E-07 3.70E-07 1

3. Percent of applicable limit (1) 5.87E-03 1.23E-02_

1 C. Dissolved and Entrained Gases _j

1. Total relsase ci 1.23E-02 1.30E 42 2.00E+01

2. Average diluted concentration during period uCi/ml

'1.09E-10 1.05E-10 i ~3. Percent of apolicable limit (2) 5.44E-05 5.25E-05 l 1 D.' Gross Alpha Radioactivity

1. Total release C1 2.47E-06 4.53E-07 3.50E+01-E. Volume of waste released (prior to I

dilution) liters 5.43E+06 6.51E+06 3.00E+01 j F. Volume of dilution water used during period liters 1.13E+11 1.24E+11 5.00E+00 (1); Concentration limits specified in 10CFR, Part 20. Appendix B, Table II, Column 2 (Technical Specification 3.11.1.1). The percent of applicable j limit reported is based on the average diluted concentration during the l period. ' At no time did any release exceed the concentration limit. j . (2) Concentration limits for dissolved and entrained noble gases is 2E-04 microcuries/ml (Technical Specification 3.11.1). The percent of applicable limit reported is based on the average diluted concentration during the period. At no time did any release exceed the concen'. ration limit. 7986R

I TABLE 2B Yankee Atomic Electric Company. Rowe. Massachusetts Efiluent and Waste Disposal Semiannual Report First and Second Ouarters. 1989 Liquid Effluents Continuous Mode Batch Mode l Nuclides Released Unit Quarter Quarter Quarter Quarter 1 2 1 2 S tr ont ium-89 Ci 1.09E-04 <2.05E-04 <1.68E-05 (2.76E-05 Strontium-90 Ci <1.51E-04 <1.08E-04 <7.89E-06 <7.16E-06 _Cealum-134 Ci 3.67E-05 1 29E-05 1.14E-04 8.44.E-05 _ Cesium-137 Ci 1296E-04 2.87E-05 1.41E-04 1.17E-04 _lndjne-131 Ci (1.46E-05 7.60E-06 6.10E-06 9.94E-06 _fRhall-18 Ci <1 3DE-05 <2.25E-05 4.99E-07 <6.17E-06 _.Cabalt-60 Ci 6.49E-06 4.62E-06 4.00E-05 2.55E-05 _]ron-59 Ci <3.09E-05 <4.59E-05 <1.11E-05 <1.31E-05 Zine-65 Ci <3.28E-05 <4.66E-05 <1.27E-05 <1.4DE-05 _MangannEc:54 Ci (1.53E-05 _12.27E-05 4.07E-06 3.71E-06 _Chrnmium-51 Ci <1.lbE-04 <1.68E-04 <5.84E-05 <5.78E-05 ._7,irconium-Niobium-95 Ci <2.58E-05 <3.76E-05 <1.02E-05 <1.10E-05 _Malybdenum-99 Ci <1.13E-04 <1.62E-04 <4.32E-05 <4.53E-05 _Inchnetium-99m Ci 5.58E-06 2.17E-06 <6.00E-06 <6 83E-06 ,Jarium-Laatltanuni-l_40 Ci <5.22E-05 (7.18E-05 (2.56E-05 <2.55E-05 _ Cerium-141 Ci <2.07E-05 <2.95E-05 <9.70E-06 <1.08E-05 _ Ruthenium-103 Ci <1.48E-05 (2.13E-05 <7.25E-06 <7.49E-06 _ Cerium-144 Ci (9.43E-05 <1.33E-04 <4.41E-05 <5.03E-05 Iodine-133 Ci <1.49E-05 <2.13E-05 <7.42E-06 3.01E-07 _S.elenium-75 Ci <1.66E-05 <2.35E-05 <7.85E-06 <8.55E-06 l Silver-11Ds Ci <1.54E-05 <2.09E-05 (7.29E-06 <7.40E-06 l _Anlimony-124 Ci <1.43E-05 (2.10E-05 <9.55E-06 2.57E-06 _ Carbon-14 Ci 8.53E-03 1.21E-02 _1.ron-55 Ci 7.83E-05 5 20E-04 6.61E-05 2 64E-03 2 _ Cesium-136 Ci <1.46E-05 <2.13E-05 <5 86E-06 (6.34E-06 _ Antimony-125 Ci <4.15E-05 <5.56E-05 <2.14E-05 (2 30E-05 _Unident111gd C1 _In_tal for period (above) C1 4.32E-04 5.76E-04 8.90E-03 1.50E-02 __ Xenon-133 Ci 1.53E-06 <6.30E-05 4.08E-03 5.28E-03 Xenon-135 Ci <1.21E-05 <1.71E-05 1.60E-05 2.27E-05_ __ Xenon-131m Ci <5.18E-04 <7.43E-04 <2.50E-04 7.02E-05 i I l Xenon-133m Ci <1.01E-04 <1.41E-04 2.92E-05 2.11E-05 [ Krypton +85 Ci <5.00E-03 <7.16E-03 8.18E-03 7.58E-03 l l 7986R

l c V [ TABLE 3 Yankee Atomic Electric Company. Rowe. Massachusetts p Effluent and Waste Disposal Semiannual Report 1 First and Second Ouarters. 1989 l Solid Waste and Irradiated Fuel ShlomRDin .A. Solid Waste Shipped Off-Site for Burial or Disposal (Not Irradiated Fuel)* Unit Six Month Est. Total Period Error. %

1. Type of Waste

a. Spent resins, filter sludges, evaporator m3 8.49E+01 bottoms. etc. - LSA container **.+

Ci 1.0hE+01 3.00E+01 3 1.33E+02

b. Dry compressible waste, contaminated m

eauipment. etc. - LSA container ++ Ci 5.19E+00 1.00E102

c. Irradiated components, control rods, m3

~ e t.c. C d. m C1 m3 e. I Ci

2. Estimate of Major Nuclide Composition (By Type of Waste)***

a. Tritium 3.69E+01%

Ni_ckel-63 211EtQQ% Cesium-137 2.41E+01% Niobium-95 1.80E+00% Cesi um-134 1. 71 E+01% Manganese-54 1.05E+00% Iron-55 1.71E+01% Cobalt-60 2.92E+00% Nickel-63 1 10E+00%

b. Cesium-137 3.33E+01%

Scainm. -134 3.00E+01% Iron-55 2.68E+01% Cobalt-10 4.01E+00%

3. Solid Waste Disposition Humb_er_nL_ Shipments tiode of Transportation Destination 14 Truck Barnwell, SC B. Irradiated Fuel Shipments (Disposition): None

+ Container volume equal to 55 gallons (drums). ++ container volume equal to 105 ft3 (boxes).

Solid waste is Class A, as defined in 10CFR61.55.
- Solidification agent is cement.

C** Excluding nuclides with half-lives less than 12.8 days. 7986R

~. s e 4-APPENDIX A Radioactive Liquid Effluent Monitoring Instrumentation Requirement: Radioactive liquid effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.6. With less than the minimum number of channels operabic and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful. Technical Specification 3.3.3.6.b requires an explanation for the delay in correcting the inoperability in the next Semiannual Effluent Release Report. RespRnse: Since the requirements of Technical Specification 3.3.3.6 governing the operability of radioactive liquid effluent monitoring instrumentation were met for this reporting period, no response is required. l A-1 7986R

AFPENDIX B Endinacilv.e Gasanus Effluent Monitoring Instrumentation . Requirement: Radioactive gaseous effluent monitoring instrumentation channels are required to be operable in accordance with Technical Specification 3.3.3.7. With less than the minimum number of channels operable and reasonable efforts to return the instrument (s) to operable status within 30 days being unsuccessful. Technical Specification 3.3.3.7.b requires an 1 explanation for the delay in correcting the inoperability in the I next Semiannual Effluent Release Report. Ecursnne: Since the requirements of Technical Specification 3.3.3.7 governing the operability of radioactive gaseous effluent monitoring instrumentation were met for this reporting period, no response is required. l l l B-1 7986R

APPENDIX C Liould Holdup Tanks Requirement: Technical Specification 3.11.1.4 limits the quantity of radioactive material contained in any outside temporary tank. With the quantity of radioactive material in any outside temporary tank exceeding the limits of Technical Specification 3.11.1.4, a description of the events leading to this condition is required in the next Semiannual Effluent Release Report. fiemmnae: The limits of Technical Specification 3.11.1.4 were not exceeded during this reporting period. l l l l C-1 .7986R I l 1

L l.i L 1 APPENDIX D a. Endiological EnviroomaniallDnitoring Program l Egguirement: The radiological environmental monitoring program is. conducted 1 in accordance with Technical Specification 3.4.12.1. With milk or fresh leafy vegetation samples.no longer available from one or more of the required sample locations, Technical Specification 3.4.12.1.c requires the identification of the new location (s) for obtaining replacement sample (s) in the next Semiannual Effluent Release Report and inclusion of revised l Off-Site Dose Calculation Manual Figure (s) and Table (s) reflecting the new location (s). EcEPonte: No new sampling locations were needed to be identified in accordance with the above requirement. l l l l l 1 1 i l l D-1 i 7986R' j

r + .s APPENDIX E Land Use Census Requirement: A land use census is conducted in accordance with Technical Specification 3.12.2. With a land use census identifying a location (s) which yields at least a 20 percent greater dose or dose commitment than the values currently being calculated in Technical Specification 4.11.2.3, Technical Specification 3.12.2.a requires ~the identi..eation of the new location (s) in the next Semiannual Effluent Release Report.

Response

The annual land Use Census was not completed during this reporting period. Requirement: With a land use census identifying a location (s) which yields a calculated dose or dose commitment (via the same exposure pathway) at least 20 percent greater than at a location from ' which samples are currently being obtained in accordance with Technical Specification 3.12.1, Technical Specification 3.12.2.b requires the identification of the new location (s) in the next Semiannual Effluent Release Report. Reannnas: The annual Land Use Census was not completed during this reporting period. l E-1 7986R L

I. t e APPENDIX F l-Process Control Program' Requirement: Technical Specification 6.14.1 requires that licensee initiated changes to the Process Control Program be submitted to the Commission in the Semiannual Radioactive Effluent Release Repsrt for the period in which the change (s) was made. l Bas.psnsa: Revision 4 of the Process Control Program was developed to incorporate the addition of a new liquid waste cement l solidification drumming system (refer to Appendix H). The PORC review (Meeting No. 89 -25) took place on January 25, 1989. Revision 4 of the Process Control Program is found on the following pages. 1 F-1 7986R i

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01/11/89 Rev. 4 de WlEE NUCLEAR POWER STATION l PF0 CESS CONTROL PROGRAM I k-i g a m. - 1 / l I 7- .-zi j j

[; c '- 1 --.l 01/11/89 Rev. 4 d TABLE OF CONTENTS Page Rev. j l

1.0 INTRODUCTION

1 4 1 a 2.0 SOLIDIFICATION PROCESS DESCRIPTION.................. 4' 4 i ~l 3.0 CONTROL OF THE FACTORS WHICH AFFECT SOLIDIFICATION.. 8 4 4.0 ADMINISTRATIVE CONTROLS............................. 10 4 ,x-5.0 SURVEILLANCE AND TEST PROGRAM...................... 11 4 6.0 SPECIFICATIONS...................................... 13 i 7.0 FO RMU LAT I ON BAS E S................................... 16 4 .lL l' " 8.0 APPENDICES APPENDIX A Figures Used in PCP Implementation..... 18 4 APPENDIX B' Station Procedures Which Implement the PCP............................... 19 4 ATTACHMENTS YAEC to NRC: Request for Review of Solid Waste Process Control Program September 30, 1983 NRC to YAEC: Solid Waste Process Control ; rogram November 2,1983 l bh ' -i-h ..u____-.--.-

01/11/89 Rev. 4 Page 1 o )

1.0 INTRODUCTION

The Yankee Atomic Electric Company Process Control Progiam (henceforth' abbreviated as PCP) describes the administrative and technical controls on the liquid radioactive waste solidification system to provide assurance that solidified waste is produced that meets shipping and burial ground requirements, and~ that the operations are carried out in a controlled manner per plant procedure to. keep personnel exposure "as low as reasonably achievable." The PCP describes process parameters, controls, sampling, and formulas to assure: athe ~ solidification of liquid waste maximum practical volume reduction a ' h' SOLIDIFICATION, as defined in the Technical Specifications (Definition 1.35), shall be the conversion of wet waste into a form that meets shipning i and burial ground requirements.. Disposable waste containers, shipping casks, and methods of packaging shall meet all applicable Federal Regu-lations; e.g., 10 CFR Part 71, and all radioactive waste will be shipped to licensed burial sites in accordance with applicable State, NRC, and 007 regulations, including burial site regulatory requirements. L This PCP addresses the solidification of liquid waste (evaporator concentrates, decontamination solutions, and spent cartridge filter ele-ments) with Portland cement to produce solidified waste classified in 10 CFR 61.55 as Class A waste. Solidification of bead resins, oily waste, or any Class B or C liquid waste is not specifically described in the PCP, but treated as special cases on an individual basis by the PCP. The disposal of bead resins occurs on an infrequent basis of approxi-mately once per year. There are no cross connections between the resin h.3dling system and the radwaste solidification system which preclude the .___.m-

3- . q.m m OD11/89' l

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.Rev. 4' Page 2-pJ g' l7 use.of 'in plant solidification equipment for. the immobilization' of spent 4 resinst Due to thel infrequent nature of. spent resin shipments, the. most - efficient method of handling is by contract with a waste disposal.' vendor and : a mobile dewatering sys;em for the sluicing of* spent' resins int'o : a l. disposable liner ' contained within a shipping-cask and..the subsequent-l' dewatering < A11 spent resin dewatering' operations are carried-out under the vendor's PCP.and/or procedures'which have been. reviewed.and approved by p the plant's radwaste coordinator.and the Plant Operation Review Committee (PORC) ' prior to implementation. This review is' to identify that there. is sufficient supporting documentation of the vendor's PCP and/or procedures to give assurance that the final dewatered resin will meetLall requirements for transport and burial, and that sufficient procedural controls exist to assure safe dewatering operations with resultant doses to personnel kept as low as reasonably achievable" in all phases of the process handling. If solidification of spent resins is required, a vendor will be utilized and the vendor's PCP will be reviewed as above. 1 .~4 i-Oily waste above trace and incidental amounts- (greater than 1% by volume) are to be treated as special situations. Waste streams containing greater than trace amounts are to be > segrerated and held until proper solidification parameters are determined via laboratory analysis for each l batch of waste, or until an approved outside vendor's mobile solidification equipment and PCP can ' be available ~ for the handling of oily waste to produce waste forms which meet all appropriate burial ground critaria. This method of segregating and handling oily waste on a case-by-case sr. sis is possible since the volume of. waste in this category has historically 11 been smw11. Class B and C liquid waste per 10 CFR 61.55 are not normally encoun-tered as a result of plant operations, and, as such, are to' be treated as a special situation on a case-by-case basis. Normal liquid waste streams are processed via a forced circulation evaporator to a concentration of between 20 w/o to 30 w/o solids, which is mostly boric acid cv borate compounds (there is no boron recovery in the plant design). The vast ccjority of waste concentrates from the liquid systems are expected to exhibit specific 4*'

t 01/11/89 Rev. 4 Page 3 h activities less than 0.1 times the concentrations in Table ] cf 10 CFR 61.55 and less than the specific ~ activities of Column 1 of Table 2, and are therefore Class A waste. Normally wastes are concentrated so as not to exceed Class A unstable limits (81 pCi/cc). If liquid waste ' would be expected to exceed Class-A waste-specific activities due to the normal degree of. evaporation processing, plant procedures will direct that the waste not be concentrated tt a point such that Class A waste criteria would be exceeded prior to solidifh stion. Alternately, lanoratory analysis on batch liquids will be performed prior to. any solidification procedure to identify all criteria necessary to properly solidify the waste and meet 10 CFR 61 stability criteria on the final waste form as well as all cther required waste form criteria. High integrity containers may be substituted for standard steel drums in order to meet criteria on waste form stability. G l 9 1 ) 4 i t 3 _1_____.1._.____.__.__._

01/11/89 Rev. 4-Page 4 2.0 SOLIDIFICATION PROCESS DESCRIPTION 2.1 Liquid Waste Evaporator Concentrate liquid wastes containing significant radioactivity are routinely processed through a single radioactive liquid waste evaporator. The liquid waste feed streams ~to the evaporator have sufficiently consistent chemistry-such that the waste to be solidified (the evaporator bottoms liquid) has, in over +.wenty-eight years of plant operation, demonstrated a reasonably uniform chemical makeup. Accordingly, this section of the Process Control Program addresses a single liquid waste stream, the radioactive waste evaporator concentrate, as the normal or typical operating case. An overview of the general process is depicted in Figure PCP-1. Radioactive liquids processed by the evaporator on a batch basis will normally be liquids described as hydrogenated or aerated. Hydrogenated liquids are primary coolant that is collected as primary coolant dilution water, purification system rinse water and primary coolant valve stem lea'kage water. Hydrogenated liquid waste is collected in a non-isolable 7500 lallon tank and stored in two isolable 75,000 gallon tanks. Aerated liquids are pump leakage, sample sink drains, floor drains, ) ) laboratory waste, shower waste, rinse and wash water, reactor containment building sump drains, and some steam generator blowdown water. Aerated liquids are collected in one, non-isolable 5000 gallon tank. Waste liquids from any of the four collection and storage tanks are 1 fed to a permanently installed, indir< ctly steam-heated evaporator. \\ l

01/11/89 ~ ' Rev. 4 Page 5 hk} Averaged over a fuel cycle, liquid waste accumulates at about one gallon per minute. The evaporator operates intermittently with a liquid feed of four gallons per minute. A typical evaporator " batch" or "run" would consist of 12,000 gallons of liquid waste feed, both hydrogenated and aerated, processed intermit-tently over a one-week period. The batch is, terminated when either the boric acid concentration in the evaporator bottoms approaches a saturated

soletion, i.e.,

the soh:bility limit is approached, or the radioactivity concentration limits are approached. A typical evaporator bottoms, at solidification concentration, would have characteristics similar to: 1) Temperature 200 F 2) Boric Acid 27 w/o l {g 3) Dissolved Electrolytes

0. 5's 4) 011 No measurable 1

i 5) Total Radioactivity 0.01 - 0.1 microcuries per grim 6) Bottom Batch Volume 265 gal. (2400 lbs) l The hot concentrated evaporated bottoms liquid.is recirculated through insulated and heat traced piping to an adjoining drumming station. There are two different drumming stations available. The primary drumming station involves having a drum placed in a position on the load cell. Based on the Chemistry analysis, the load cell system is set to receive a predetermined weight (typically 330 lbs) of liquid waste. When the correct amount of waste has been added to the drum, the transfer will be automatically stopped.

01/11/89 Rev. 4 page 6 h A mixer is started. The load cell system is now set for a predetermined weight of cement / lime mixture. The cement / lime is added until the proper amount is

received, then the transfer will be automatically. stopped.

Mixing continues until a homogeneous mixture has been achieved. The mixer is then stoppped and the barrel removed. The secondary drumming system has approximately 220 pounds of the liquici afspensed by weight into an empty 55 gallon drum, ' subsequent dispent,ng of the remaining bottoms liquid into empty 55 gallon drums is accomplished by weight or volume approximately equal to the first drum. A measured quantity of slaked lime is added to each drum based on content of boric acid. When the liquid is cooled, a measured amount of Portland I/II l cement is added to each drum. It is capped, mixed by rotating the drum axially at approximately 20 rpm for 10-20 minutes, opened, and inspected. Drums of liquid waste are solidified one at a time. The solidification process produces drums half filled with paste. Before hydration and setup, one half-filled crum of cement paste is decanted into another to produce 2;, filled drums of solidifie3 waste. Filled drums, with lids removed, are set aside for at least five days to allow for cement hydration and set. Each drum of solidified waste is visually inspected for setup and no free water before the drum is capped. Over the last several years, about 250 drums of solidified evaporator bottoms liquid are produced per year by the drumming process. Normally a thimble (e.g. metal rod, pipe, or wooden dowel) is inserted down the axial center of selected drums of wet cement. When the cement has set, but not hardened, the rod is removed. The axial hole thus produced facilitates inspection of solidified waste. If necessary, drums without axial holes formed by use of a thimble may be inspected full length by drilling a minimum 5/8 inch diameter hole fr am the top to within 5 inches of the bottom. The acceptability of the solidified mix may be determined by inspection of the drill tailings for dryness and/or by ,,h inserting a small diameter rod into the hole to judge hardness.

g 01/11/89 Rev. 4 Page 7 2.2 Decontamination Solutions, Miscellaneous Liquids Other liquids including decontamination solutions may be solidified using formulas whose parameters are bounded by the limits shown on Graphs PCP-4, PCP-5, and PCP-6 as appropriate. Liquids must meet the specifications for pH, t'otal solids, chelates, oil, hazardous chemicals -and radionuclides content. Solidified decontamination solutions.will meet the criteria for Class A waste. A solidification test will be performed on each batch of miscellaneous liquid solidified. 2.3 Cartridge Filter Elements Spent cartridge filter elements which are Class A are encapsulated in non-radioactive cement in 55 gallon drums. The filters are centered axially in the drums and all remaining space filled with cement paste. The final solidified product is about 96 volume percent cement, 4 volume yh percent filter cartridges. The radioactivity content of the filter cartridges is determined and/or estimated to assure that the solidified product meets the criteria for Class A waste. E,* h

b l i j l 01/11/89 l Rev. 4 I Page 8 l ih 3.0 CONTROL OF THE FACTORS WHICH. AFFECT SOLIDIFICATION ) Sampling and Analysis l 1 Each batch of evaporator bottoms liquid is sampled and analyzed prior ] to solidification for boric acid content, electrolyte content, radionuclides I content, pH and oil. Evaporator bottoms are concentrated to the practical maximum boric acid concentration, or radioactivity concentration limit. Liquid Waste pH: A pH of evaporator liquid waste between 5.5 and 8.5 l assures efficient volume reduction. A pH between 3 and 11 assures solidi- .fication and that the resulting solid will not be corrosive to the contain-er. Solidification Formula: The proportion of liquid waste to hydrated lime and cement is specified for each batch of evaporator bottoms based on actual analyses o.' the bottoms liquid (see Section 7.0). Presence of 011: YAEC does not expect oil contamination in liquid waste to exceed 1% by volume. Liquid Waste Temperature: Liquid waste concentrate piping will be 1 heat traced to 200 F. j i Drum Mixing Time: For the primary drumming system a mixing time of 5-10 minutes per drum is necessary to properly blend the ingredients. For i the secondary drumming system sufficient energy. must be imparted to the mixture to properly blend the ingredients. A mixing time of 10-20 minutes per drum on the axial drum roller has been shown to produce satisfactory mixing. I Solidification (Hydration and Set) Time: Drums of blended waste set for a minimum of 5 days at a minimum temperature of 50 F, with covers removed, to assure set up of borated waste. Db i I a

01/1'1/89 Rev. 4 2 Page 9 }h Cement and Lime Quality: Commercial grades of Portland I/II cement and hydrated' lime are sufficiently consist'ent in quality. For the secondary drumming-Lsystem cement and lime are purchased and dispensed in 94 and 50 pound bags, respectively. For the primary drumming system a cement / lime mixture will be used. This mixture will be delivered premixed. f hI m i i hb. ____mm._ .m_________

e:

01/11/89 Rev. 4 Page 10 4'. 0 ADMI' ISTRATIVE CONTROLS N Written procedures are used to implement the YAEC PCP. The station procedures address the following areas of implementation: a. Step-by-step operation of'the liquid radwaste evaporator b. Sampling and analysis of liquid waste streams c. Solidification formulas d. Solidification process e. Inspection of solidified waste containers f. Laboratory Test Program Gi g. Quality Assurance Station procedures which implement the YAEC PCP are listed in Appendix B.

01/11/89 y L Rev. 4 0 Page 11 h 5.0 SURVEILLANCE AND TEST PROGRAM l Each drum of solidified waste is uncapped immediately after mixing, and remains uncapped for about a week (minimum of 5. days) during the hydration and set process. Thus, the principal method to verify. SOLIDI-l FICATION and NO FREE LIQUID is visual inspection of each drum of solidified waste. If free liquid above the criteria set forth in 10 CFR 61 is detect-ed in any waste container, that container shall be set aside, drained of all excess liquid, and be reprocessed based on laboratory determination of acceptable process control parameters to assure that solidification with no unacceptable free liquid is obtained. At least one representative test specimen from at least every tenth batch of. evaporator bottoms liquid or every batch of decontamination solution, that meets the appropriate chemistry criteria for pH, oil, and boric acid content shall be tested for solidification according to a laboratory test program. The laboratory procedure duplicates the solidification procedure on a small scale. The solidified test specimens are kept in the laboratory for reference. For evaporator bottoms liquids that meet the chemistry criteria of the PCP, the solidification test may be performed concurrently with the solidi-fication of the evaporator bottoms. If the evaporator bottoms liquid does not meet the chemistry criteria of the PCP, the bottoms will be adjusted to meet the criteria; otherwise solidification of a test specimen must be demonstrated before the bottoms liquid can be mixed with cement binder. If any test specimen used as a basis for solidification formulation fails to verify solidification in the laboratory, the solidification of the batch under test may be su2 pended until such time as additional test specimens can be obtained, alternate solidification parameters can be determined, and a subsequent test verifies that acceptable solidification can be accomplished with the alternate solidification parameters. ~.. -_.m_-_..___-.m._

01/11/89 Rev. 4 Page 12 . 5 If the initial test specimen from a batch of waste fails to verify solidification, representative test specimens shall be collected from each consecutive batch 'of the same type of wet waste until at least three consecutive ' initial test specimens demonstrate acceptable solidification. The PCP shall then be modified as required (in accordance with Technical Specification 6.14) to assure proper solidification of subsequent batches of waste. ~ l ) l l es

4 - 01/11/89-Rev. 4 Page 13 6.0 SPECIFICATIONS 1. Liquid waste, after processing through. the evaporator, prior to solidification, will meet the following specifications: - Parameter Specification Test Method pH 5.5 to 8.5(a) Lab' analysis on 1:9 diluted Sample Insoluble Oil Less than 1% Visual on sample by volume l Boric Acid Practical maximum Lab analysis of batch sample concentration at the temperature of the solution. See h Graphs.PCP-2, PCP-3, PCP-4 Temperature. Greater than 200 F In evaporator 170 F to 200 F When blended with cement for the primary drumming system. ' 160 F Primary secondary drunming system Radionuclides As described below - Laboratory assay, estimation, Content values expressed in source terms, or ratio to microcuries per gram measured nuclides i Gamma Emitters t1/2 less than 5 years j 700 ] All Isotopes t1/2 greater than 5 years j ,g3 .s 3 bE

Includes H-3, C-14, Co-60, Ni-63, Sr-90, Tc-99, I-129, Cs-137, Pu-241, transuranic, any other identified isotopes.

l

= h.' ' 01/11/89 Retf. 4 Page 14 .hh Parameter Specification Test Method Solids a) No hazardous chemicals b) Less than 0.1% chelating agents c) No scintillation Administrative controls, liquids laboratory analysis, prior knowledge of liquid waste d) Less than 10% total chemistry 7 di ssolved ' electrolytes (excludes boric acid) 2. Cement Portland cement type I/II. Meets ASTM C-206-49. hib 3. Lime Type S hydrated lime. Meets ASTM C-150-77. 4. Premixed Cement / Lime Mixture The components will meet the criteria of 2 and 3 above. 5. Additives Silica containing natural or synthetic materials to improve cement hydration, set, and leach resistance. No specifications for various volcanic pozzolanas, burnt clay pozzolanas, or pulverized fly ash. Yr

i 01/11/89-Rev. 4' Page 15 - k 6.- Containers Type 17H 55 gallon drums with lids and. bolted lid clamp. Drums will have a smooth sealing surface, free of rust and cement. -Footnote: (a) A pH of 5.5 to 8.5 insures the radwaste system operates to effect maximum volume reduction. A pH of 3-11 insures solidification. l. E 0 ') 4 i

I 01/11/89 Rev. 4 i Page 16 { lhhh - I 7.0 FORMULATION BASES The solubility of boric acid in water is a complex function of temper-ature, pH, and alkali metal concentrations. Figures PCP-2 and PCP-3 show i the solubility of boric acid-in water as a function of temperature and i l volume reduction curves for evaporator operation respectively. The figures are used by plant chemists to determine the practical maximum concentration of boric acid in evaporator bottoms liquid. The ability of boric acid to strongly inhibit the hydration and set of Portland cement is well known. Calcium hydroxide (slaked lime) is an additive which reacts with, and reduces, the hydration inhibiting property of boric acid. Any amount of slaked lime may be cdded to the solidifica-tion mixture; but excess beyond the molar requirement to react with the boric acid present reduces waste loading efficiency. The ratio of Portland I/II cement to liquid waste depends on the water content of the waste..The higher the boric acid content, the less the water content, and the less cement is required. The basis of the liquid waste / lime / cement formulation is: Time-is added according to the boric acid content, and cement is added according to the water content. Certain materials with a high silica content may be substituted for a portion of the lime and cement in the solidification formula in order to improve product strength and waste volume efficiency. Some such materials are: clays, pulverized fly ash, pozzolanas, and burnt clay pozzolanas. Solidification Formulas: For the primary drumming system the ratio of cement / lime has been determined to be satisfactory for the entire range of expected boric acid concentrations. l

6 01/11/89 Rev. 4 Page 17 l!(T For the secondary drumming system the solidification formula for each batch of' concentrated liquid waste is based on the boric acid and solids content of the batch. sample. Appendix. A illustrates graphs (Figures.PCP-4 and PCP-5) which give boundary limits for acceptable solidification. Specific l - solidification formulas are based on experience from previous batches. Plant chemists issue the solidification formula, in writing, for each batch of evaporator bottoms to be solidified. New solidification formulas may be developed and employed in station operating procedures to accommodate improved binders, to optimize radiation levels on solidified waste, or fr; sued waste processing techniques. For new formulas, the blended waste will be frequently inspected for solidi-fication ud no free liquid. .h$ t I ---a--_----,.-a_.--,--___-.--_____--------._.---.------------.-----_.____..--_---.a-

} ,i 01/11/89 Rev. 4 i l Page 18 1 l YAEC PCP APPENDIX A Figures Used for PCP Implementation Figure PCP-1 is a block diagram of the normal liquid radwaste effluent pathways. Figures PCP-2 and PCP-3 are used by the plant chemists to determine the extent that the evaporator can concentrate boric acid containing liquid waste to achieve-a practical maximum volume reduction. Figures. PCP-4 and PCP-5 are used by the plant chemists to determine that the solidification formulas are within acceptable boundary limits for secondary drumming system. l Figure PCP-6 is used by the plant chemists to determine that the I solidification formulas are within acceptable boundary limits for the primary drumming system. 1 I bh' i 1

k 01/11/89-Rev. 4 j'; Page 19 J L2, YAEC PCP 1 APPENDIX B j. Station Procedures Which Implement the PCP i l 1. OP-2380 Operation of the Waste Disposal Evaporator System 2. OP-2381 Batch' Record for Concentrating and Drumming Evaporator Bottoms Batch 3. OP-2388 Solidification of Miscellaneous Radioactive Liquid Waste 4. OP-2175 Changing Filter Capsule Cartridges in the Purification System. 5. OP-8310 Preparation and Inspection of Dry, Drummed Evaporator /;g Bottoms. 6. OP-9406 Primary Plant Liquid. Sample Points. 7. OP-9416 themistry Control of the Primary Auxiliary System and the Radioactive Waste Disposal Systems kO'

? q. . })/[. i*..- n ,e o '~ Telephone t617) B77B100 e l - TWK 1103807619 l y- - YANKEE ATOMIC ELECTRIC COMPANYx. A-t.Aw...' rYRe3-ss .n cu sn i2.C2.1 W/ x y ex*- 1671 Worcester Road. Framongham. Massachusetts 01701 TAN KEE we,- September 30, 1983 United States Nuclear Regulatory Ccrnmission Washington. D. C. 20555 Attention: M r. Dennis M. Crutchfield, Chief Operating Reactors Branch No. 5 Division of Licensing Referc6ces: (a) License No. DPR-3 (Docket No. 50-29) (b) USNRC Letter to YAEC, dated February 16, 1983

g S ubj ec t :

Request f or Review of Solid Waste Process Control Progra:n 9 '

Dear Sir:

Yankee Atcxnf c Electric Company herewith subnits its solid radioactive vaste Process Control Progra= (PCP) for review and approval in response to the require:nents of Section 3/4.21.3 of the recently accepted changes to our Technical Specifications (Reference b). Long-tenn operating history indicates that solidified liquid wastes have not exceeded the concentration limits listed in 10CFR61.55 for Class A vastes. With the use of this PCP, it is expected that processed waste forms will continue to meet the necessary requirements to be classified as Class A vaste when 10CFR61 becomes ef fective on December 27, 1983, in addition, it should be noted that it is our position that Class A wastes which are sufficiently stable such that they do not affect overall disposal site stability through.sltumping, collapse, or other f ailure of the disposal unit, need not be segregated upon disposal. By placing additional specifications on the final vaste product, Yankee intends to meet the stability requirements of 10CFR61.56(5), prior to its effective date. These specifications vill include the follot.ing: 1) minintan product density of 100 lbs/f t3; and 2) minimum container fill of 9M. s As long as the final disposal unit rmains intact, reasonable assurance '.k, is given that water will not infiltrate the vaste and result in radionuclides h m ovm ent. By specifying a minimu:n product density of 100 lb/f t3, which is representative of the soils in a burial site, further ecunpaction of the waste i ___m___m

.e m ' M.. United States Nuclear Regulatory Canaission-Septem ber 30, 1983 it.~ Attention: Mr. Dennis M._ Crutchfield Page 2' is not possible. Specifying a minimum container fill of 95% vill assure only minimum slumping at the point in time when the container rusts away. As long as the container is full, and the density of the contents is similar to that of the burial site backfill, burial site subsidence vill not occur as a result - of the waste material -buried therein. Implementation of these additional specifications should provide sufficient assurance that the vaste form being pro,duced under this PCP meets ' the intent of the. stability requirmente: of 10CFR61.56(b) and will not require segregation upon disposal. We trust this information is satisf actory; however, if you have any questions, please contact us. Very truly yours, YANKEE ATQi1C ELECTRIC CCMPANY-J. A. Kay Senior Engineer - Licensing kb JAK/dsm p 4 l I l dpc m..._..

l W.J.neg. RECENED -j. MEE ATODC 1 ../ 1, UNITED STATES <-A; .[ 7g j L*, g a NUCLEAR REGULATORY COMMISSION { wAssiuctoN. o. c. 20sss s. i Jh t ' %j *...

j, N OV.

4 3 1983 ] November 2, 1983 i NYR 83-202 . Docket No. 50-29 LS05-83-11-007 ' Mr. James A. Kay Sen~ior Engineer - Licensing . Yankee Atomic.. Electric Company - 1671 Worcester Street Framingham, Massachusetts 01701

Dear Mr. Kay:

4

SUBJECT:

SOLID' WASTE PROCESS CONTROL PROGRAM Re: . Yankee Nuclear Power Station By letter dated February 16,.1983, we transmitted to you our Amendment No. 80 to Facility-Operating License No. OPR-3 for the Yankee Nuclear Power Station (Yankee).. The amendment approved the radiological environmental Technical Specifications and among(PCP) for Yankee.other things, referenced the use of an process control program ' On September 30, 1983, Yankee Atomic Electric Company submitted the PCP and requested our approval.

pj We have reviewed your PCP and find that it uses documented and approved

~ methods that are consistent with NRC guidelines and, therefore, is acceptable for-use as required by Technical Specification 6.14. We recommend however, ,j3 g,,the process control systems.that in'your next revision of the PCP, you add a sketch o .j l-If you have any questions on this matter, please let us know. Since rely, ' 9g,y) ~7f, f i 7 Dennis M. Crutchfield, Chief Operating Reactors Br nch #5 Division of Licensing cc: See next page d /? 'Q. w - L______m ._.__.___._____..m _.m._.

i ..y 3 j ,1...1 ~ .p t q s,- .h ; s ) '. _: q x ;" W., Mr. James A.' Kay' 2. November 2,.1983.- , o CC . Mr. James E. Tribble,' President. Yankee Atomic Electric Company 1671 Worcester Road' Framingham, Massachusetts 01701 Chairman Board of Selectmen Town of Rowe Rowe,: Massachusetts '01367 U. S. Environmental Protection Agency Region 1 Office- . AT.TN:. Regional Radiation. Representative - 'JFK Federal Building. Boston, Massachusetts 02203~ . Resident Inspector Yankee Rowe Nuclear Power Station Jc/o U.S.-'NRC ' Post Office Box 28-Monroe Briage,' Massachusetts 01350 t ~. $8.[ Dr. Thomas E. Murley, Regional Administrator t ~ Nuclear Regulatory Comission, Region 1 -s -631 Park Avenue King of-Prussia, Pennsylvania 19406 Robert M. Hallisey, Director Radiation Control Program L . Massachusetts Department of Public Health 600 Washington Street, Room 770 Boston. Massachusetts 02111. D4D G e M9 SA $ } J

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APPENDIX G Off-Site Dose Calculation Manual Requirement:. Technical Specification 6.15.2 requires that licensee initiated changes ' to the Off-Site Dose Calculation Manual be submitted to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the change (s) was made effective. i ReapDnag: There were no licensee initiated changes to the Off-Site Dose Calculation Manual during this reporting period. l ( l l i 1 l l l I c-1 7986R I 1 l L_____

1 i j AETENDIX H I l \\ Radioac.tive Liquid. Gaseous and solid Waste Treatment systems i i Requirement: Technical Specification 6.16.1 requires that licensee initiated major changes to the radioactive waste systems (liquid, gaseous, and solid) be reported to the Commission in the Semiannual Radioactive Effluent Release Report for the period in which the evaluation was reviewed by the Plant Operation Review Committee.

Response

During this period, a new liquid waste cement solidification drumming system was installed. The PORC review which approved the system (Meating No. 88-31), took place on March 29, 1988. The following pages include excerpts from Plant Design Change Request No. 87-012, which address the fulfillment of Technical Specification 6.16 requirements. H-1 I 7986R l

- _ = - - _ _ + 3.0 LICENSING Technical Specification 6.16, " Major Changes'to the Radioactive Liquid, Gaseous, and Solid Waste Treatment Systems" .This Technical Specification states that major changes to the Radioac-tive. Waste Systems must be reported to the~ Commission in the Semiannu- ~ lal Radioactive Effluent Release Report for the period in which the change was reviewed by PORC. It also lists the following topics which _must.be addressed in.the report: - A detailed description of the equipment, components, and processes involved and the interfaces with other plant sys-tems. This topic is addressed in Section 1.0 of this PDCR entitled " Description of Change."

1.0 DESCRIPTION

OF CHANGE 1.1 General System Description The proposed ATCOR Solidification System is designed to receive sepa-rate feeds of liquid. waste and dry binder material for mixing in a standard 17H DOT SS gallon drum for subsequent solidification and dis-posal. The. ratio of waste liquid to binder material-(cement and lime) ~ will be determined in accordance with the Process Control Program (PCP) which will be instituted for each batch. 'New solidification formulas, which may be required as a result of this change, must still meet'the chemistry and radioactivity parameters specified in the PCP. The proposed system consists of a mixing unit assembly, a cement stor-age and feed assembly, a S5 gallon drum conveyor / lift system, and con-- trol consoles. The equipment will be locat'ed in the radwaste process-ing-area-and the adjacent warehouse. A process flow diagram and proposed equipment layout are shown on Drawings 8129-D-01 and 8129-D-06 (Enclosure (F)).

1. 2 System Operation The following is a brief desc5ption of the steps involved in opera-tion of the Waste Liquid Drumming System.

1. A drum is manually loaded and positioned below the mixing unit on the conveyor / lift platform. 2. The platfarm is raised, pressing the drum against the mixing head gasket to provide and ensure a. tight seal. 3. Based on the PCP results,,the weighing system indicator and cut-off is' set to receive the determined weight of liquid waste. 4. The waste inlet valve is then opened by pressing the control pushbutton at the operator's station to begin waste tra,nsfer. l H-2

o, -5. When the correct amount of waste has-been received, a signal from

g u

the Load Cell System will automatically close the waste inlet 4 valve to stop waste transfer. l~ ~6. The mixer is started. ~ '7. The Load Cell. System is set to rec < the predetermined amount-of'solidificati,on binder. 8. The cement feeder is started to begin the transfer of cement. 9. A signal from the Load Cell System will automatically: stop the feeder _when the correct amount of cement has been: received. 1-

10. Mixing will continue for a-short time to ensure a homogeneous waste / cement mixture and will-then be secured.

11. The ' conveyor / lift platform is lowered and the drip shield extend-ed below the mixing blades to contain-drippage.

12. The drum:is:then manually moved on the conveyor / lift platform to the monorail pick-up point, capped, and removed to 'the drum stor-age area.

The system design' enables the operator to perform all' waste transfer, cement transfer, and mixing operations from-the remotely-located ' con-trol' panel. Only the capping and conveyor operations must be per-formed manually,. significantly reducing the operator's exposure time from the solidification process currently in use. Reference 11,~ con-tained'in Enclosure (I), details the expected man-rem savings for the new system. Cement / lime loading operations are performe.d: prior to beginning any batch processing. The cement / lime mixture kill'be delivered in 25-cu-bic: foot bulk bags for easy loading. Using a fork lift, the operator will' lift the bag above the batch bin,. connect and clamp the outlet' sock to the bin inlet, and pull >the control cord to gravity fill the batch bin..The bin is specifically sized to handle a full. day's batch processing without' refilling. 1.3 System Components 1.3.1-Mixing Unit Skid Assembly The mixer and waste / cement inlets will be installed on a steel structure designed to straddle the conveyor scissor lift platform. The structure legs will be attached to the ficor grating for stability. The mixing unit will be a fixed mount, three-bladed agitator mounted directly to the support structure. The mixing blades will be located at the top and bottom of-the shaft and near the drum midpoint to provide, efficient mixing action. The mixing unit will be driven by a 3-hotsepower 460-volt motor. The mixing head will also include a waste inlet valve, a ,.T drum overfill level element to stop waste liquid and ce-H-3

a: l0 _Of 7.f' i ment / lime. addition before the ' drum overflows;in the event' of' m

9. -.

,1 a Load Cell. System failure, and a drip shield l assembly: to' prevent the spread of contamination when h drum is not. " located below the mixing blades. The drip'. shield is mounted-

on rails that' extend beneath the mixing blades to contain g~

,N 'any drippt by catching it on..a pla~stic sheet. The: sheet -may be'dit ed of and replaced with a clean sheet,as neces- ,,7 sary. 1.? 2-Cement Storage and Transfer System The Cement Storage and' Transfer System _ consists of a 60-cu-= bic foot storage hopper and mechanical screw feeder. The hopper is loaded manually using premixed,' prefilled bulk. bags. The bags are fitted with loops designed to' enable them to be lifted over the hopper with a ' standard forklift.- This eliminates the need for an additional ~ hoist system. The hopper inlet is connected to the bulk bag discharge nozzle' and clamped for dust-free gravity transfer. The hopper is vented through a cloth filter to minimize dust. The cemen_t feeder is.a flexible mechanical screw type which takes feed from the hopper discharge ~and lifts it to the' mixing head cement inlet connection..The flex drive motor ~ is supplied with 460.V, 3 phase, 60 Hz service. 1.3.3 Conveyor / Lift System The Conveyor / Lift System consists of a roller conveyor mounted on a hydraulic scissor lift platform. The scissor. lift platform is used to lift empty. drums for nrocessing-tc mate with the mixing equipment. The platform o *e is 24" x 66" with a 2,000 pound capacity and vertical l u of.48". The' platform has a self-contained Hydraulic Systen ytilizing a 3.2 Sp hydraulic pump requirint, 460 volt, 3 phase, 60-hertz service. The platform :an.be elevated to full height in nine secon.ds. During all elevated operations, the drum is clamped in place with an attached-drem clamp. One 1 part of the conveyor will extend below' the existing monorail to facilitate drum pick up and remoul to the. storage area. The scissor lift platform is mounted on load cells for drum weight measurement and system process control. 1.3.4 Control Panels The control panels consist of two wall-mounted NEMA 12 en-closures containing all necessary control buttons, indicator = lights, selector switches, relays, breakers, starters, and necessary instrumentation to enable system operation from a-remote location away from the actual process. Drum place - ment and removal will be the -only activities requiring oper-ator contact with the drummed was'e. The system operating logic will be entirely based-on manual actuation.- The only automatic' functions associated with the process'will be the . interlocking between the Load Cell Weighing System'and the waste inlet valve and cement feeder. This interlock will de-energize the waste inlet valve or cement / lime feeder based on predetermined weights and the operation in pro-gress. 1 H-4 j s

n. k 15.[ h '1.41 System Requirements: f Ths 'ATCOR System is designed to be freestanding and. requires 'the fol-lowing connections'to existing systems: 1r 1.4.1 -Electrical.- Power will be supplied to the' motors an'd con-trol. equipment.from MCC 5 located in the Waste Disposal. Building. 1.4.2 Compressed Air - Service air will be supplied to the ' sole-- noid-operated valve,s.and to the drip shield actuators from the Service Air System in the Waste Disposal Building. i 1.4.3' Waste Liquid Piping - The wasteL11guid inlet'on the mixing -head will be connected-to the evaporator-recirculation'11ne'- upstream of the tap currently'used.for drumming. A manual isolation valve will be installed between the evaporator.- 2 - recirculation line and the ATCOR System. Also, a valved tap will be installed immediately downstream from this isolation valve to permit flushing the isolated piping with servirc water after drumming has been completed.

1. !r Electrical-h Nonsafety-related 480 V, 3 phase, 60 Hz electric power will be provid-l ed to the system.fr.om a new 40 amp breaker to be mounted in MCC 5, Bus 1 adjacent to the.PCA Storagi Building feeder breaker. A single feed

-will be-run from the MCC to the radwaste solidification. control panel and-will branch out to the various system components from there. Each I., control panel is protect'ed by a dedicated 30 amp breaker and will con-l tain a 480/120 V control transformer to supply the 120 V control power-required for system control. "A loc 21.30 amp disconnect switch is

provided on the flex conveyor motor for personnel protection. The new system will add an additional load of 30 amps to the MCC. which is

. sized to handle this additional capacity. >1.5.1 Grounding Grounding of various equipment will be done in accordance with the vendor drawings using #10 bare copper wire. 1.5.2 Breaker Coordination. Each control panel is protected by a 30 amp breaker. Break-er coordination between the MCC and the control panel is achieved by replacing the existing 100 amp breaker in the MCC with a new 40 amp breaker..This is,iustified since the two panels will operate together during system operation. Also, the existing coordination for the MCC feeder. breaker - is unaffec,ted by this modification since the new breaker is small and the existing coordination is based on the largest breaker in the MCC. 1.6 Compressed Air ' ) Operation of the Waste Liquid Drumming System requires compressed air be supplied to the drip shield pneumatic actuators and to the sole-l l -noid-operated valve on the waste inlet line. A tee will be installed j l H-5 1 ,i ima__ii___ ______._________.._i..___.___

p ( in' Service Air Line 3/4" ASC-151-9 and' 1/2" Schedule 80 pipe wi1'1 be i run from the tee-to the connection on the mixing head. An isolation valve will be installed in the line near the mixing head. This line is shown on Figure 1, " Waste Liquid Drumming System Service Con-nections," which is ' included in Enclosure (B).. E 1.7 Ventilation System During operation of the Waste Liquid Drumming System, the drum will seal against the mixing head to prevent the release of dust and air-borne contamination resulting from material addition or mixing. In order to facilitate unrestricted flow of materials into the drum, a 2-1/2" vent connection is provided on the mixing head. A high effi-ciency, low pressure drop filter will be attached to this vent to min-imize dusting. A -description of this filter can be found in Enclosure (D). 1.8 Waste Liquid piping The existing evaporator bottom pump recirculation line (1"-ERB-152-2, Drawing 9699-FM-41C) will be cut to allow a loop of pipe to be in-stalled extending up the wall, across the' ceiling above the system, and back to the extsting pipe. The reason for doing this is to maintain as much of the new piping in the recirculation stream as possible. From this loop, a short section of pipe, containing a manual isolation valve, will be routed down to the system.. This section will be the only dead leg of the new piping run. The heat tracing and insulation will be extended to include the new section of pipe up to the isolation valvd'to preclude boron precipitation. 1.9 Heat Tracing Baron solidification in the stripper " bottoms" pump recirculation line has been a problem. To remedy this situation, the existing 6STV1 Chemelex Auto-Trace will be replaced with 15XTICT Chemelex Auto-Trace. The new heat tracing is designed to maintain the recirculation piping at 200 F (controlled by a thermostat) as compared to the existing i 110 F-130'F. The new calcium silicate insulation to be installed over the heat tracing will be 1" thick on the 1" NPS pump discharge piping, and 1-1/2" thick on the 1-1/2" NPS pump suction piping. To allow op-erators to read the heat tracing load when required, a thermostat by-pass switch will be installed next to the existing test switch and upgraded (0-25 amp vs 0-15 amp) ammeter. The existing 20 amp elec-trical supply, Circuit No. 16 of Lighting Cabinet 0, located in the Waste Disposal Building; is adequate to supply and protect the expect-ed heat trace load of 9-16 amp. 1.10 Mechanical Supports j The mounting details for the new radwaste drumming equipment, as well as the supports for new radwaste piping and service air piping, are I included in Enclosure (B). The mounting details for the mixing head I stand and the scissor lif t/ load cell are shown on Sketch YR-590-1. The cement hopp'er is to be mounted on the plant warehouse floor using i two (2) 1/2" diameter Hilti Kwik bolts with 2-1/2" minimum embednent i for each b'aseplate. A Bill of Materials for mounting the above l equipment is contained on Sheet 2 of Sketch YR-590-1. j To allow additional height for the fork lift when loading the cement hopper, the bridging between one pair of roof joists in the plant i H-6

q i

warehouse will be removed. 2x2 angle will.be added to the adjacent joists for support. See Sketch YR-590-2 for details, a The new 1" waste disposal piping should be. supported using the j blockwall mounted supports (Sketch YR-590-3a) and the beam' mounted i supports (Sketch YR-590-3b). This piping should be supported at 8'-0" maximum lengths. The new service air piping should be supported at 8'-0" or less in-tervals using the support shown in Sketch YR-590-3c. 4'i The designs of the equipment mountings and. pipe supports were per-i formed in accordance with the AISC manual of Steel Construction, 8th l Edition, ACI 318-83, building code requirements for reinforced con-crete, and manufacturer's recommendations. 3 - The removal of the. plant warehouse roof jois1 bridging was evaluated in accordance with the Steel Joist Institute Standard Specifications and the AISC Manual, 8th Edition. All designs and evaluations are contained in Calculation N'o. YRC-590, , to be kept on file in DCC. 1.11 Qualification Requirements This system is classified as non-nuclear safety and contains no equip-ment necessary to safely shut down the plant or to mitigate the ef-fects of an accident. As such, no seismic or environmental qualifica-tions are' required. 1.12 Fire Hazard Considerations The addition of this system will introduce two new fire loads to the area. The first of these are the electrical panels and associtted wiring. The cables between MCC 5, the panels, and the various system components are run in conduits. Therefore, because of the relatively small' amount of cabling involved, and because the wires are. enclosed within conduits and control panels, the fire load addition is minimal and assumed to be zero. The other load addition is due to the hydrau-lic fluid in the scissor lift. The fluid is Texaco Rando 011 HD32 and has a value of 141,000 Btu / gallon. The lift contains two gallons of oil, so the total additional load would bo ?32,000 Btu. This is not enough to change the area fire load designation (Reference 2). 1.13 System Testing In order to ensure that the system will operate as designed, a pre-shipment test was conducted at ATCOR's test facility. The system was set up with water and cement used to simulate the waste liquid and cement / lime inputs. The system was stopped after each major step to evaluate system performance. The~ system was also run uninterrupted to judge overall system characteristics and final water / cement homogene-ity. A copy of the ATCOR test procedure is attached as Enclosure (E). After receipt of the system at Yankee, a similar test sequence will be used to test' the n-7 l 3

t-j . system using actuai waste liquid and cement / lime inputs. This test l will be described in the installation and test procedure, OP-5000.220, to be written to implement this design change. i 'i 1.14 System Operating Tips l l Once the system has been installed and tested it will be turned over j to the Operations Departmant and put into service. The following is a list of items that should be taken into account when system operating 1 procedures are developed: 1. The filter on the cement / lime hopper vent should be cleaned after j each addition of cement / lime mixture to assure proper air flow. j 1 2. After each drumming session, the gate valve on the hopper should j be closed. A container should be placed under the clean-out door and the door opened. The screw-feeder'should be run in reverse to clear the cement / lime mixture and prevent caking. 1 I 3. Agitation of the waste / cement / lime mixture will ca ~ e it to set faster than normally expected. Various pH control :aemicals will also accelerate this process. Do not let the' mixer run in a thickening mixture or motor damage may result. Do not let the mixture solidify around the blades. 4. When raising the cium against the mixing head, make sure that the drum seats properly or gasket damage could result. 5. Do not add any solid wastes to the drum before or during mixing or damage to the blades and motor could result. - Suf ficient detailed information to support the reason for i the change without the benefit of additional or supplemental information. This topic is addressed in Section 2.0 of this PDCR entitled " Reason for Modification." - An evaluation of the change, which shows the predicted re-leases of radioactive materials in liquid and gaseous efflu-ents and/or quantity of solid waste that differs from those previously predicted in the license application and amend-ments thereto. This topic is addressed in Section 2.0 of this PDCR entitled " Reason for Modification." - A comparison of the" predicted releases of radioactive mate-rials, in liquid and gaseous effluents and in solid waste, to the actual releases for the period prior to when the changes are to be made. The predicted decrease in solid waste volume is discussed in Section 2.0 of this PDCR enti-tied "Re,ason for Modification." 2.0 REASON FOR MODIFICATION The Waste Liquid Drumming '>ystem currently in use at the plant is both la bor and dose-intensive. Consequently, the new system was designed to re-duce both the man-hours and man-rems spent drumming. The operator is removed from direct contact with the waste addition and mixing steps by B-3

1, virtue of the system's semiautomated design. This greatly reduces the op-erator's dose and risk of contamination. Process controls built into the system allow precise waste / cement / lime ratios and mixing times which yield repeatable results with a. higher percentage of waste liquid per drt.m, as shown below (Reference 4). Current Prepsed ATCOR Yankee Description. System System Weight Waste Per Drum 310 lb 220 lb Annual Cement / Lime 47 tons 52 tons-Waste Packaging Efficiency Volume 66% 50% Number of Drums Per Batch 8 11 Annual Number of Solidified 177 (73 drums 250 Orums for Disposal less annually) 3 3 Annual Disposal Volume of Solidified 1,327.5 ft 1,875 ft Waste 3 i Disposal Volume Savings 547.5 ft i The system will also achieve a higher drumming rate by ccmpleting the whole! process in one place and eliminating the need to manually handle bags of l cement and lime. Installation of this system should result in a decrease { in waste disposal costs and operator exposure while drumming. - A summary of the evaluation that lead to the determination that the change could be made in accordance with 10CFR50.59. Thi's topic is addressed in Section 14.0 of this PDCR enti-tied " Safety Evaluation." 14.0 SAFETY EVALUATION-In order to make the waste liquid drumming process more efficient and keep operator exposure ALARA, the plant proposes to install a semiautomated Waste Liquid Drumming System manufactured by ATCOR Engineered Systems. A, full description of this system can be found in Section 1.0 of thitdocu-ment. Installation and operation of this system will have little impact on any plant system not directly associated with the drumming process. All compo-nents of this system and all interface points with existing plant systems are classified as Non-Nuclear Safety (NNS) and, as such, are not necessary to safely shut down the plant or mitigate the results of an accident. In addition, it can be stated that: The probability of occurrence or the consequences of an accident or a. malfunction of equipment important to safety previcusly evaluated in the FSAR is not increased. The Waste Liquid Drumming System is not mentioned in any FSAR accident analysis. Section 209 of the FSAR deals with the Waste Disposal System and mentions drumming activities only briefly with no details as to drumming procedures or equipment. I H-9 ________--_----_-__--___A

e b. The possibility for an accident or malfunction of a different type than any evaluated previously in the FSAR is_ not created. The proposed Waste tiquid Drumming System will handle only normal plant wastes and is located in an area of the plant originally de-signed for this purpose, c. The margin of safety, as defined in the basis for any Technical Speci-fication, is not reduced. The,Wastc, Liquid Drumming System is not mer,tioned in any Technical Specification basis. Based on the above, this modification does not constitute an unreviewed safety question as descritad in 10CFR, part 50.59, and there is reasonable assurance that the health and safety of the public will'not be endangered. - An evaluation of the change which shows the maximum expo-sures to member (s) of the public at the site boundary and to the general' population that differ from those previously estimated in the license application and amendments thereto. Since the new Drumming System wil'r be physically located adjacent to the existing Drumming System and will produce drummed wastes that meet the existing requirements, no change will occur in the estimated maximum exposure at the site boundary or for the general population. An estimate of the exposure to the plant operating personnel as a result of the.chinge. The plant conducted an ALARA review of the installation and operation of the new Drumming System with the following results: a. Installation of the system will cause an estimated ex-posure of 1.322 man-rem to Maintenance personnel. b. Operation of the system will save an estimated 1.830 man-rem / year to Operations personnel. See Refer-ence 11, contained in Enclosure (I). G H-10 l -...____m_..

~ ' ]lh t: or 's a" l APPENDIX I I l l Sup.plemental Information 1 1 First and Second Ouarters. 1989 -1. Technical Specification Limits - Dose and Dose Rate lechnical Specification and catecory Limil a. Noble Cagga 1 1 3.11.2.1 Total-tody dose rate. 500 mrem /yr 3.11.2.1 Skin dose rate 3000 mrem /yr 3.11.2.2 Gamma air dose 5 mrad in a quarter 3.11.2.2 Gamma air dose 10 mrad in a year l 3.11.2.2 Beta air dose 10 mrad in a quarter 3.11.2.2' Beta air dose 20 mrad in a year b. 2ndine-131. Trit _imn and Radionuclides in Particulate Form With Half-Lives Greater Than 8 Days 3.11.2.1 Organ dose rate 1500 mrem /yr 3.11.2.3 Organ dose 7.5 mrem in a quarter 3.11.2.3 Organ dose 15 mrem in a year c. Liquids 3.11.1.2 Total body dose 1.5 mrem in a quarter 3.11.1.2 Total body dose 3 mrem in a year 3.11.1.2 Organ dose 5 mrem in a quarter 3.11.1.2 Organ dose 10 mrem in a year I-1 7986R

4. 2 APPENDIX I (Continued). 2. Technical Specification Limits - Concentration Technical Specification and Catecorv Limit

a. ' Hnhle_Gasna :

No MPC limits b. Iodine-131. Tritium and Radionuclides No MPC limits in Particulate Form With Half-Lives Creater 7,han 8 Days c. Liquida 3.11.1.1 Total sum of the fraction of MPC (10CFR20.. Appendix B, Tables II, Column 2), excluding noble gases less than: 1.0 3.11.1.1 Total noble gas concentration 2E-04 uCi/cc 3. dtASDLCEnt.L.And Approximations of Total Radioactivity a. Noble cases " Continuous discharges" are determined by indirect measurement. . Primary gas samples are taken periodically and analyzed. It is assumed that in primary to secondary leakage all gases are ejected through the air ejector. In primary coolant charging pump leakage all gases are ejected to the primary vent stack either during flashing or liquid waste processing. " Batch discharges" are i determined by direct measurement. Errors associated with these ) measurements are estimated to be f55 percent. j l l i 1-2 4 l L7986R l i 4 J

o-La O. APPENDIX I (Continued) b. Iodines Iodines are continuously monitored by drawing a sample from the primary vent stack through a particulate filter and charcoal cartridge. The filter and charcoal cartridge are removed and analyzed weekly. The errors associated with these measurements are estimated to be 125 percent. I c.. Particulate The particulate filter described in (b) above is analyzed weekly. The errors arsociated with the determination of particulate effluents are estimated to be 30 percent. d. Lignid Effluents Liquid effluents are determined by direct measurement. In line composite samples are analyzed for strontium - 89, strontium - 90, iron - 55, gross alpha activity aad carbon - 14. There is no l compositing of samples for tritium or dissolved fission gas analysis. For continuous discharges composite samples are used for gamma isotopic analysis. A gamma isotopic analysis is performed on a representative sample for each batch release using the Marinelli Beaker geometry. The errors associated with these measurements are as follows: fission and activation products, 20 percent; tritium, 1 0 percent; dissolved fission gases, 120 percent; alpha activity, 1 135 percent. l l l I-3 7986R I

o-1 APPENDIX I I (Continued) i 4. Intch Releases a. LLquida Flrst Ouarter Number of batch. releases: 26 Total time period for batch releases: 4879 minutes Maximum time period for a batch release: 310 minutes Average time period fut batch releases: 188 minutes Minimum time period for a batch release: 20 minutes Average stream flow during period (Sherman Dam): 658 cfs Average discharge rate: 37.1 gpm Second Ouarter Number of batch releases: 19 Total time period for batch releases: 11375 minutes Maximum time period for a batch release: 1380 minutes Average time period for batch releases: 599 minutes Minimum time period for a batch release: 220 minutes Average stream flow during period (Sherman Dam): 636 cfs Average discharge rate: 19.9 gpm b. Gases There were no batch releases during the first and second quarters. l I-4 7986R

( of 'c. l APPENDIX'I (Continued) 1 l.. 5. Abnormal' Releases-a. Liquid There were no nonroutine liquid releases during the reporting period. b. Gases There were no nonroutine gaseous releases during the reporting period. l 1 I-5 7986R ________.____.___.______-.__.____a}}

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