PLA-2708, Semiannual Effluent & Waste Disposal Rept,Data Period:Jan-June 1986

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Semiannual Effluent & Waste Disposal Rept,Data Period:Jan-June 1986
ML20214V955
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 06/30/1986
From: Carson B, Keiser H, Widner T
PENNSYLVANIA POWER & LIGHT CO.
To: Murley T
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
PLA-2708, NUDOCS 8612100023
Download: ML20214V955 (85)
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Text

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7 .

SUSQUEHANNA STEAM ELECTRIC STATION SEMIANNUAL EFFLUENT & WASTE DISPOSAL REPORT DATA PERIOD: JANUARY - JUNE 1986 Pennsylvania Power & Light Company Two North Ninth Street Allentown, Pennsylvania 18101 August 1986 sea 222888i! 8t8888si 1GM R PDR G{

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ . - - _ .. . . . _ , , _~_y... _ .,_,..-_..c,_ . _ _ . - _ , -.._.,_,-.7m . _._,,

9 SUSQUDIANNA STEAM EIECIRIC STATION SENIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT REPORT PERIOD: 01/01/86 - 06/30/86 Prepared by: . . > 3h nd Shb/%

Y.E. Widner / B. H. Carson Health Physicist Health Physics Specialist Level II Reviewed: . IM - M B. W. Grahu Environmental Group Supervisor- Nuclear Approved: re [ /2,r[

K.' E. Shank Radiological & Environmental Services Supervisor l

Pennsylvania Power & Light Company Two North Ninth Street Allentown, Pennsylvania 18101

4 TARfR OF OWITNIS E

M 1

1. Introduction and Supplemental Information. . . . . . . . .

Data.................. 9

2. Effluent and Waste Disposal
3. Changes to the Offsite Dose Calculation Manual 21 and the Solid Waste Process Control Program......
4. Reports of Exception to the SSES Effluent 76 Monitoring Program...............................

9 1

I l

r LIST OF TABLES w

E5E 6

Table 1: Supplemental Infomation. . . . . . . . . . . . . . . . . . . . . . . . . .

10 Table 2: Airborne Effluents- Sussnation of All Releases.....

11 Table 3: Airborne Effluents................................

Table 4: Waterborne Effluents- Stssnation of All Releases... 12 13 Table 5: Waterborne Effluents..............................

Table 6: Solid Waste and Irradiated Fuel Shipments......... 14 A.................. 15 Table 7: Solid Radioactive Waste- Class B.................. 17 Table 8: Solid Radioactive Waste- Class C.................. 18 Table 9: Solid Radioactive Waste- Class Table 10: Estimated Total Errors Associated with Effluent 19 Measurements.....................................

Table 11: Effluent Data Not Reported in Previous Semiannual Report................................ 20 l

I l

11

i l l

l LIST OF FIGURES a P.ec.J Figure 1: Airborne Effluent Release Points: 4 Location and Deta11.............................

Figure 2: SSE3 Waterborne Ef fluents: 5 Release Pathway.................................

i 111

p P

4. ~

SECIION 1 IN11t000CIION AND SUPPUSENTE INFORMATION 1

INIRODUCTION a

is located in Salem Township, he hydanna Steam Electric Station (SSES)

Luzerne Com ty, Pennsylvania. It is on the west bank of the Susquehanna River, 8 las northeast of Berwick. The Station consists of two boiling water reactor generating units, each with 1,050 W not electrical capacity. The reactor and generating units were supplied by General Electric, while the Bechtel Corporation served as architect-engineer and constructor.

Construction of the Station began in the early 1970s. Fuel load began in Unit 1 in July of 1982. Initial criticality was achieved in the Unit I reactor on September 10, 1982. The reactor reached 100% power for the first time on February 4,1983. Consercial operation of Unit I was

' decIsred on June 8, 1983. Initial criticality of Unit 2 occurred 12, 1985.

on May 8, 1984. Unit 2 was declared commercial on February Airborne effluents are released from the Susqushe . Station via five rooftop vents on the reactor building (see Figure 1). Each vent is continuously monitored, and a program of periodic saepling and analysis is conducted as specified in the plant Technical Specifications.

All waterborne effluents are released in batch mode and are saspled and analyzed prior to release. Waterborne effluents from the site are released into the cooling tower blowdown line for dilution prior to release to the Susquehanna River (See Figure 2). Blowdown line flow rates are at least 5,000 gym during periods of liquid redwaste release.

The diluted effluent is introduced to the river by way of a perforated diffuser pipe placed on the river bed. The diffuser serves to rapidly and uniformly six the the station discharge with the main flow of the river.

This report presents a summary of the quantities of radioactive materials which were released from the Susquehanna Steam Electric Station during the period from January 1, 1988 to Jm e 30, 1986. In addition, this _

report serves as a medium for notifying the US Nuclear Regulatory -

Commission staff of changes to PPSL's Offsite Dose Calculation Manual (ODC30 and Solid Waste Process Control Program (PCP) and documentation of any exceptions to the SSE3 effluent monitoring program which must be '

reported per Technical Specif1 cations 3.3.7.10 and 3.3.7.11.

Table 1 contains supplemental infornation pertaining to offluents from the Susquehanna plant. Included are regulatory limits, sampling and analysis methods, and characterization of the resuber and duration of batch and abnormal releases, if any.

Table 2 contains a summation of all airborne releases, grouped into the radionuclide categories of gases, particulates, lodines, and tritium.

Average release rates are presented and compared to the applicable limits. Table 3 presents the totals of specific radionuclides in airborne effluents.

2 B

, ,w-,wn,-, - - - e-,--e,- ---,-.----,w-- - - - --- - - - - - ---- ---

Waterborne effluents are sammarized in Table 4. Average diluted concentrations are presented and compared to the applicable limite.

" Table 5 presents the release quantitles of specific radionuclides in waterborne offluents over the report period.

Tables 6 through 9 present a characterization of the solid radioactive waste shipped off site during the report period. Included are the volumes and curie contents associated with each type of solid waste.

An estimate of major nuclide composition is presented for each waste type, as well as the russber of waste shipments from the site, how they were transported, and their final destination.

Table 10 contains estimates of the errors associated with the measurements  ;

involved in quantifying offluents. Sampling errors, counting errors, and errors associated with detemining effluent flow rates and volumes all contribute to the total error of effluent measurements. Error estimates are presented for each category of radionuclide detected in airborne and waterborne ef fluents and solid wastes during the report period.

Table 11 presents offluent data from previous report periods which was not available at preparation time for the associated semiannual report.

Section 3 of this report is reserved for doctamentation of changes to the Offsite Dose Calculation Manual and the Solid Waste Process Control Program. A revised copy of the administrative procedure which describes j the Process Control Program is included along with a statement of the purpose and nature of the changes.

Section 4 presents a listing of cases (if any) in which airborne or waterborne effluent monitoring instrtamentation was declared inoperable and was not restored to operability within the time period specified in Technical Specification Table 3.3.7.10-1 or 3.3.7.11-1 Action Statements.

3

+

FIGURE 1 AIRBORNE EFFIEENT REIJMSE POINIS- LOCATION ME) DETAIL

,hN - l il e it T

s illb 11 4.

r

\

w J .

VN\

,.,/'..' '

Ihj

'2 g! ua

./. ~/ y g '

/// /

/\

8 o i /

1!

I 8

l, I

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4

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FIGURE 2 c.

SSES WAIERBORNE EIFIEENIS-REIZASE PAIHWAY t

FE t

RADWASIE EUIIDING le%,,

a s

%)  %

e O .

LIQUID RADWASIE o 6 j

I 2 DIN LIE allons/ batch f

8E (100 gpa maxionss)

'p ' '

CDMPOSIIE SAMPIIR collects

/ approximately 20 ml overy RADIATION MONITOR has alare/tr!P 20 minutes fross blowdown line for monthly analysis setpoint calculated based on each batch isotopic analysis SUSQ. RIVE VALVE tenn nates release on 7- N oo, o < , , , _T high radiation. Iow sample flow, or low blowdown flow L DIFFUSER. near bottors of river rapidly mixes discharges with the flow of the river 5

TAIKE 1 .

SENIANNUAL EFFLUENT & WASIE DISPOSAL REPORT DATA PERIOD: JANUARY - JUNE 1986 SUPPIBENIAL INFORMATION J

1. Regulatory Limits
a. Fission and Activation Gases: 0.851 C1/mirante (Release rate limit based on Technical Specification dose rate limit of 500 aren/yr from noble gases). This number is calculated based on the expected mix of noble gas radionuclides presented in Table 4.4 of the SSE3 Final Environmental Statement NUREG-0564.

I b. Iodine-131: 141 microcuries/ minute (Release rate limit based on Technical Specification dose rate limit of 1500 mren/yr from iodine-131, tritium, and particulates with half-lives greater than eight days).

c. Particulates: 772 microcuries/ minute (Release rate limit based on Technical Specification dose rate limit of 1500 mres/yr from i

iodine-131, tritium, and particulates with half-lives greater than j eight days. This number is calculated based on the expected mix of l

particulate radionuclides presented in Table 4.4 of the SSE3 Finst Environmental Statement, NUREG-0564.

2. Maxismsa Pomissible Concentrations The concentrations of radioactive materials in waterborne effluents l are limited to the concentrations specified in 10G R Part 20 Appendix B i

l Table II, Colum 2. for radionuclides other than dissolved or entrained noble gases.

For dissolved or entrained noble gases, the concentrations are limited i

to the following values, as stated in the applicable Technical Specification: _

Nuclide MPC (uCi/ml) esKr a 2 E-4 j esKr 5 E-4 s7Kr 4 E-5 88Kr 9 E-5

  • 1Ar 7 E-5

( tasXe m 5 E-4 l

tasXe 6 E-4 l sasXe a 2 E-4 tasXe 2 E-4 l

These values are calculated using Equation 20 of ICRP Publication l

2 (1959), adjusted for infinite cloud submersion in water.

l

3. Methods of Quantifying Effluents
a. Fission and Activation Gases: Gas samples are routinely collected monthly and analyzed with a Ge(L1) detector system which incorporates l

a data reduction program to detemine radionuclide composition in tems of specific activity. Data tapes from the continuous vent monitors are used to determine the average concentration of noble 6

' - gases.'Ih3 Ge(L1) icatopio ccan to used to convert tha continuous vent monitor activity to actual activity based on the detemined nuclide mixture. he vent and sangle flow rates are continuously

  • monitored, and the average flow rates for each vent are used to calculate the total activity released in a given time period.

When the continuous monitors are out of service, manual grab

samples are taken from each vent once each eight hours (once each four hours for the standby gas treatment vent).
b. Iodines: Iodine is continuously collected via an isokinetic sampling assembly in each vent. Filters are normally exchanged once per week and analyzed on a Ge(L1) system. He daily average flow rates for the vents and sample ptasps are averaged for the duration of the sampling period, and a ratio of vent flow rate to sample flow rate is determined. He ratio is used to detemine the total activity of each isotope released during the time period in question. When the continuous monitors are out of service, lodine is continuously collected on charcoal cartridges attached toair samplers which draw directly from the affected rooftop vent (s) or from alternate sampling ports available on the sample lines.
c. Particulates: Particulates are continuously collected via an isokinetic sampling assembly in each vent. Filters are nomally exchanged once per week and analyzed on a Ge(L1) system. Flow rate corrections are performed as for lodines. When the continuous vent monitors are out of service, particulates are continuously sampled directly from the affected rooftop vent (s) or from alternate sampling ports available on the sample lines,
d. Waterborne Effluents: Each tack of liquid radwaste is sampled and analyzed for principle gansna emitters prior to release. Each saaple tank is recirculated for a sufficient amount of time prior to sampling to ensure that a representative sample is obtained.

Saaples are analyzed on a Ge(L1) system and release posits are generated based on the values obtained from the isotopic analysis and the most recent values for trititan, gross alpha, iron-55, and strontium-89 and -90. An aliquot based on release volume is saved and added to monthly and quarterly composite containers.

The monthly tritium analysis is done in-house. The quarterly ~_

composite is sent to a vendor laboratory for iron-55, strontium-i 89 and -90, and gross alpha analyses. ,

f The concentration of each radionuclide in each batch is decayed from l

the time of consiting to the midpoint of the release period, and is I then multiplied by the voltane of the batch to detemine the total quantity of each nuclide released in each batch. The isotopic totals for each are sunened to determine the total source term for the report period.

l t

7

4. Batch Releases J
a. Waterborne 236
1. Number of Batch Releases: 5.28E+04 minutes
2. Total Time Period for Batch Releases: 3.90E+02 minutes
3. Maximum Time Period for a Batch Release: 2.24E+02 minutes
4. Average Time Period for a Batch Release:

1.40E+01 minutes

5. Minisman Time Period for a Batch Release:
6. Aversgo Stream Flow During Period of Release of Effluent into a Flowing Stream: >5.38E+03 gym (cooling tower blowdown) 9.60E+06 gym (Susq. River) i
b. Airborne 0
1. Number of Batch Releases: NA i 2. Total Time Period for Batch Releases: NA
3. Maximum Time Period for a Batch Release: NA
4. Aversgo Time Period for a Batch Release:

NA

5. Miniumsa Time Period for a Batch Release:
5. Abnomal Releases
a. Waterborne 0
1. Ntamber of Releases: NA
2. Voltano Released: NA
3. Total Activity Released:
b. Airborne 0

1 1. Ntamber of Releases: NA

2. Total Activity Released:

O 8

SECIION 2 3

EFFLUENT AND WASTE DISPOSAL DATA 9

TAB M 2 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT - 1986 AIRBORNE EFFLUDTIS - SUMMATION OF AIL REMASE3 ,

Nuclide Category Unit First Quarter Second Quarter A. Fission and Activation Gases <6.56E+02 22.66E+01 <6.35E+02

1. Total Release 1 C1 21.64E+02
2. Average Release <8.08E+01 uC1/sec 22.11E+01 <8.44E+01 23.38E+01 Rate for Period
3. Percent of <5.95E-01 22.39E-02 <5.69E-01 Applicable Limita  % 21.49E i B. Iodine-131 <3.16E-04 26.36E-05 <2.79E-04
1. Total Release C1 14.30E-05
2. Average Release uC1/sec 15.53E-06 <4.06E-05 28.09E-06 <3.55E-05 Rate for Period
3. Percent of 23.44E-04 <1.51E-03 Applicable limita  % 22.35E-04 <1.73E-03 C. Particulates
1. Particulates with i Half-lives >8 Days i Released C1 21.52E-04 <1.76E-03 26.69E-05 <1.25E 2. Average Release l

Rate for Period uC1/sec 21.95E-05 <2.26E-04 28.51E-06 <1.59E-04

3. Percent of Applicable Limita  % 21.52E-04 <1.76E-03 26.61E-05 <1.24E-03
4. Gross Alpha Activity Released C1 27.17E-07 <1.24E-06 <2.61E-06 D. Tritium <1.98E+01
1. Total Release C1 21.10E+01 <1.80E+01 21.11E+01
2. Average Release '

uC1/sec 21.41E+00 <2.31E+00 21.41E+00 <2.52E+00 -

Rate for Period

3. Percent of <5.16E-02 Applicable Limita  % 22.89E-02 <4.75E-02 22.89E-02 1 Notation: The first value presented (2) includes only activity positively detected at the 95% confidence level. The second value

(<) includes detected activity plus the Lower Limit of Detection 1

values of any samples in which activity was not detected at the 95% (L.

2Besed on release rate limit derived from dose rate Technical Specification.

8 Based on release rate corresponding to *H Maxismsa Pemissible Concentration (2.0 E-07 uC1/cc) in unrestricted areas. A relative concentration of 4.1 E-05 sec/ma is assumed.

10

TABUE 3 SEMIANNUAL EFFLUENT AND WASTE DISPOSAL REPORT - 1986 AIRBORNE EFFLUENIS (Curies)1 First Quarter Second Quarter Nuclide A. Gases esKr a 2.86E-01 1.63E+02 2.66E+01 1ssXe 2.66E+01 Total 1.64E+02 B. Iodines <3.16E-04 16.36E-05 <2.79E-04 1stI 14.30E-05 C. Particulates with Half-lives > 8 d stCr 1.66E-06

<2.22E-04 14.84E-05 <1.50E-04 s*Mn 27.98E-05

<2.36E-04 <1.83E-04 ssFe <8.17E-05 seCo 18.45E-06 <1.19E-04

<2.42E-04 21.85E-05 <1.68E-04 seCo 16.18E-05

<2.67E-04 <1.89E-04 esZn <6.94E-06 s'5r <4.68E-06

<8.21E-07 <1.29E-06 seSr <7.13E-05 12*Cs <1.06E-04

<9.89E-05 <7.61E-05 137Cs

<9.44E-05 <6.34E-05 141Ce

<3.68E-04 <2.59E-04

      • Ce <1.25E-03 Total 21.52E-04 <1.76E-03 16.69E-05 1 Notation: The first value presented (t) includes only activity positively detected at the 95% confidence level. The second value

(<) includes detected activity plus the tower Limit of Detection values of any samples in which activity was not detected at the 95% CL.

t 11 i

-I I

J

5 TABIR 4 SDlIN#UAL EFFLtetr Me WASTE DISPOSAL REPORT - 1986 WAIERBORFE EFFLLer13 - SLMIATION OF A[L RELEASE 3 First Quarter Second quarter Nuclide Category Unit l ,

A. Fission & Activation -

i Products <7.99E-02 22.23E-01 <2.55E-01 i

1. Total Releaset C1 15.52E-02
2. Average Diluted <1.45E-07 14.11E-07 <4.70E-07 Concentration uC1/ml 21.00E-07
3. Percent of 6.41E-03 2.43E-02 Applicable Limita  %

B. Tritism 6.61E+00 4.56E+00

1. Total Release C1
2. Average Diluted 8.40E-06 Concentration uC1/mi 1.20E-05
3. Percent of 4.00E-01 2.80E-01 Applicable limits  %

C. Dissolved and Entrained Gases <1.77E-01 18.18E-04 <2.92E-01

1. Total Release C1 23.045-03
2. Average Diluted <5.385-07 uC1/ml 25.51E-09 <3.215-07 21.51E-09
Concentration l 3. Percent of <8.05E-01 23.78E-03 <1.34E+00 Applicable Limit *  % 21.38E-02 i

D. Gross Alpha Radioactivity Ci <1.66E-04 <2.07E-04 Released l

f E. Voltano of 2.09E+06 Waste Released gal. 2.19E+06 i

11ters 8.30E+06 7.92E+08 F. Voltane of Dilt$ tion '

j Water Used

\

>1.43E+08 >1.41E+08

1. During Periods of gal.

>5.35E+08 Release liters >5.43E+08

>6.92E+08 >7.10E+08

2. Over Datire Period gal.

>2.69E+09 11ters >2.62E+08 SNotation: '1he first value presented (1) includes only activity positively detected at the 95% confidence level. The second value i

(<> includes detected activity plus the [mwer Limit of Detection values of any sseples in which activity was not detected at the 95% (L.

2 Based on quarterly dose limits from liquid effluents.

3 Based on the Maximan Pomissible Concentration for 3H in effluents to unrestricted areas (3.0 E-03 uC1/cc).

  • Based on the most restrictive Maxisman Pomissible Concentration for a noble for a gas, 4.0 E-05 uC1/cc (e7Kr) free SSE3 Tech Spec Table 3.11.1.1-1.

12

1 TABER 5 SE3dIANNUAL EFFIEENT AND WASIE DISPQ5AL REPORT - 1986 .

WA7ERBORNE EFFIEENIS (Curies)1 First Quarter Second Quarter Nuclide .

6.61E+00 4.56E+00 A. Trit 11sn ,

B. Fission and Activation Products 6.48E-06 a*Na 1.57E-01 s1Cr 4.45E-02 <2.54E-02 23.88E-03 <4.48E-03 22.51E-02 s*h <8.30E-03 <7.92E-03 ssFe <6.22E-03 22.19E-04 <1.49E-03 24.35E-03 ssFe <7.288-03 seCo 21.98E-03 <2.57E-03 26.84E-03

<3.72E-03 11.43E-02 <1.49E-02 seCo 22.90E-03 <1.25E-02 esZn 21.27E-03 <2.60E-03 21.08E-02

<4.15E-04 <3.17E-04 eSSr <5.54E-05 se5e <4.15E-05 8.05E-06 ssNb <7.90E-03 ssMo <4.185-03 2.48E-06 ssTc e 118Ag a 5.00E-04 4.79E-03

<1.06E-03

'(

tall <5.805-04

<1.83E-03 <1.31E-03

'184Cs 6.54E-OS 1asCs <1.80E-03 1a7Cs <8.65E-04

<7.15E-04 <1.22E-03 141Ce <5.37E-03 14+Ce <3.15E-03

<7.99E-02 22.23E-01 <2.558-01 Total 25.52E-02 C. Dissolved and Entrained Gases <6.79E-05 41Ar <7.485-05

<1.70E-04 <2.02E-04 esKr a <2.82E-01 esKr <1.68E-01 _

<3.81E-05 e7Kr <5.43E-05

<2.91E-04 <3.07E-04 eeKr <5.48E-03 taaXe a <3.36E-03

<3.37E-03 25.00E-04 <2.52E-03 1aaXe 22.36E-03 <1.15E-03 1asXe a <7.74E-04

<8.31E-04 23.185-04 <6.305-04 assXe 26.77E-04 <2.92E-01 Total 23.04E-03 <1.775-01 28.18E-04 1 Notation: The first value presented (2) includes only activity positively detected at the 95% confidence level. The second value

(<> includes detected activity plus the Lower Limit of Detection values of any samples in which activity was not detected at the 95% CL.

13

TABG 6 SEMIANNUAL EELIENI AND WASE DISPOSE REP 0ttr SOLID WASE AND IRRADIAIED FtEL SHIPMiNIS Data Period: January 1. 1986 - June 30. 1986 i

l A. SOLID WASE SHIPPl!D OETSIE FOR BURIE OR DISPOSE Mode of Transnortation Destination M h of Shiemments 73 Truck Barnwell. SC 2 Truck Richland. WA B. IRRADIAI1!D FUEL SHIPbENIS M =har of Shlomants Mode of Transoortation Destination none not applicable not applicable f

14

.a TABER 7 Page 1 of 2 SDlIANNUAL EFFIIENI AND WASTE DISPOSAL REP 0ttr .

SOLID RADI0 ACTIVE WASTE- CIASS A*

Data Period: January 1. 1986 - June 30, 1986 4

~

Reactor Water / Condensate Liquid RW ._'

Source of Wacte Condensate and Processing Domineralizar Fuel Pool Denineralizer Filters Clean-Up Regeneration (Filter Media.

Fmployed (Bead Resin) Sludge.Evap.

(Powdex) (Evaporator (Waste Stream) Concentrates) Concentrates Container 540 1870 4590 Volume (fts) 5100 Total Activity 906.832 202.031 300.2 .3383 Content (C1)

Above Detemined By: .

' a) measurement C C b) estimation C C l c) measurement i and correlation factors Fe-55 24 % Fe-55 80 % Fe-55 78 %

Principle Fe-55 42 % 7% Cr-51 10 %

Cr-51 27 % Cr-51 22 % Cr-51 Radionuclides Co-60 4% m-54 5%

(Identity and h-54 13 % Mn-54 22 %

Co-60 18 % H-3 4% Co-60 4%

Percent Co-60 10 % Co-58 3%

Co-58 6% Co-58 7% m-54 3%

Coopoettion) Co-58 2%

Zn-65 2% Zn-65 6%

Fe-59 2% ,

4 Above Detemined by: ~

a) measurement C C b) estimation C C c) measurement .

and correlation factors -,,-

High Integrity Cathon Steel Carben Steel Type of Carbon Steel Liners Linare Containers Liners Container Solidification Portland Portland Agent or Dewatered Dewatered Cement Cement Absorbent

  • As defined in 10G R Part 61.

1 f

15

- TAB m 7 Page 2 of 2 SDilANNUAL !!PELUI!NI AND WASTE DISPOSAL REPORT SOLID RADIOACTIVE WASTE- GASS A*

Data Pr: lod: Jantsry 1, 1986 - June 30, 1986 Source ist Waste and Process.tre Non- Compacted O!!y Employed Ceepsetable Trash Trash Waste (Waste Stream)

Container 4357.5 180 Volume (!ts) 680 .

Total Activity 6.34 8.64 .076 Content (C1)

~

Above Determined By:

, a) measurweent B B B b) estimation c) measurement ar.d corrolatica factors '

Fe-55 55 % Fe-55 55 % Fe-55 42

  • Principle h-54 17 %  %-54 17 % Cr-51 16 %

Radionuclides .

h-54 15 %

(Identity and Co-60 17 % Co-60 17 %

Fe-59 11 % Fe-59 11 % Co-60 13 %

Percent. 7%

Composition) Fe-59 l Co-58 7%

l Above Determined by:

a) measurement B B B _-

b) estimation

- c) measuren mt-and

, correlation x J factors

  • Type of Strm g, tight 55 Gallon 55 Gallon Containers 17H D.ums 17H Drums Container Solidification Agent or N/A N/A Oil-Dri Absorbent
  • As defined in 10GR Part 61.

s 18

  • ' TABtB 8 Page 1 of 1 SEMIntA!AL EPFIAENI AND WASTE DISPOSAL REP 0Kr -

SOLID RADIOACTIVE WASTE- GASS B*

Data Period: January 1. 1986 - June 30, 1986 I

sou,c.ofsa.t.

I and Processing Employed

  • NO CLASS B WASTE GENERATED *

- . (Waste Stream) ,

Container-Voltsee (fts) .-

1 Total Activity Content (C1)

Above Determined By:

a) measurement v b) estimation s c) measurement 1 and '

correlation _

factors Principle Radionuclides ,r (Identity and Parcant.

Composition)

Above Determined by: .

a) measurement .

b) estimation c) measurement and y

correlation factors e. . .

Type of Container Solidification Agent or Absorbent ~

17

TABEE 9 Paga 1 et i SEMIANNUAL EETLUENI AND WASTE DISPO5AL REP 0ttr SOLID RADIOACIIVE WASTE- CLASS C*

, 3 ,

Data Period: January 1. 1986 - June 30, 1986 l l Source of Waste and Processing Esplayed

  • NO C[ ASS C WASIE GENERAll!D *

(Waste Stream)

Container Voltsee (fts)

Total Activity Content (C1)

Above Determined By:

a) measurement b) estiention c) measurement and correlation factors Principle Radionuclides (Identity and Percent Composition) l Above Deter 1 mined by:

a) measurement b) estimation -

c) measurement and ,

correlation factors Type of Container Solidification Agent or Absorbent

18

'

  • TABEE 10 SEMIN#30AL EPPLUENr AM) WASTE DISPOSAL REPORT ESTIMAIED 'IUIAL ERRORS ASSOCIATED WITH EFETJJENr EASUREMINIS
  • Data Period: January 1. 1986 - June 30, 1986 Estiented Total Error hurement .
1. Airborne Effluents 15.9 %
a. Fission and Activistion Gases 13.3 %
b. Iodines 15.8 %
c. Particulates 5.7 %
d. Trititan
2. Waterborne Effluents 5.0 %
a. Fission and Activation Products 3.3 %
b. Trititan I

8.4 %

c. Dissolved and Entrained Gases
3. Solid Wastes
a. Condensate Domineralizers (Band Rosin - Dewatered) 15.1 %
b. Reactor Water Cean-up Fuel Pool Clean-up 15.1 %

(Powdex-Dewatered)

c. Condensate Dominera11sers Regeneration ~_

(Evaporator Concentrated - Solidified) 15.1 %

d. Liquid RW Filters (Filter Media. Sludge and Evaporator Concentrates - Solidified) 15.1 %

25 %

e. W table Trash 25 %
f. Compacted Trash 25 %
g. Olly Waste (Absorbed) 19

~

TABEE 11 SENIANNUE EFFLUENT AND WASTE DISPOSE REPotr DATA NOT REPORIED IN PREVIOU5 SEMIAl@RJE REPORT __

l l

Nuclide Category Unit Fourth Quarter 1985 A. Airbo m e Effluents N/A N/A B. Liquid Effluents

1. Cr-51 C1 1.31E-03 l

20

I SECTION 3 .

O t

e m

21

= - - a .

O CHANGES 1011E OFFSITE DOSE CAfrtLATION MANtJAI, TIEEE N NO REVISIONS TO TIE SSE3 OETSITE DOSE CAIftLATION MANUAL DURING THE REPORT PERIOD.

spa-

)

i 22

CHAmm 10 THE SOLID WASTE PROfTM OCNIROL PROGRAM REVISIONS 8 AND 7 10 SSES PLANI PROCEDURE AD-QA-311. SOLID WASTE N N PROGRAM, WERE PREPARED AND APPROYED DURING THE REPORT PERIOD. CDPIES OF M AFFECIED PAGES ARE INCLUDED FO[IAWING THIS PAGE.

INE CHANGES MADE, WHICH ARE SUhMARIZED ON PAGE 2 W EACH REVISED PROCEDURE, DO NOT REDUCE THE OVERA[L 00NFORMAN2 0F THE SOLIDIFIED WASTE PRODUCI TO EXISTING CRITERIA FOR SOLID WASTES.

i i

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23

I

- ' ' ^ *T' M.m v c . , .. . ,

PROCEDURE COVER SHEET .

l PENNSYLVANIA POWER & LIGHT CO.

SUSQUEHANNA STEAM ELECTRIC STATION AD-QA-311 SOLIO WASTE PROCESS CONTROL PROGRAM Revision 6 Page 1 of 58 Effective Date M-6M71 Expiration Date /,E'87 i

Revised Expiration Date  !

)ROCEDURE TYPE: PORC I,

, NON-PORC , Alternate Review 30RC MTG. NO. h- 0 4-3 (If applicable) man

'O.O .', p,;

9

,'% gW C>ft;&g d bn  ; m".% ua<q

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Prepared by Date 9 [h &,

Reviewed by N I Date /18C .

Recommended (@ect'io( ead/ Manager

' Date '-l[ k!b '

/ fiAbnu r, - Date 4,4/-66 Supef)Mn6eTtf P1Ent f ~

FORM A0-QA-101-1, Rev. 2, Page 1 of 1

O. 1 3,

SSES PROCEDURE CHANGE APPRf ] O , ..

COL NO. hQ[/ REV.

(3) PROCEDURE NO. AD_- QA - _3// REV.

r-vF9 (I.) IITLE PROCEDURE TYPE: PORC ( , NON PORC [ ]

S D L) O 46NTE h 6s ccciact pRc}(n e .

(5) REQUESTED CHANGE CHANGE APPLICABILITT UNIT 1 (tl5IT 2 []

5 C G- NtTACAEg ,

(6) REASON FOR CHANGE kbb To C, heck \M p te T o m C,e r

\\ e ,.~ s k chchek, k IdeoN]

SQec s Oc, he Awo w Es gesci-uT10N To s e cGt I Oc.. tre l'

(NOTE: SEE REVERSE SIDE, ITEMS I, II, III, AND IV. THEN COMPLETE PART 7 & 8)

DOES THIS CHANGE ALTER THE INTENT OF THE PROCEDURE 7 TES NO /

(7) TES NO -

(SA) DOES THIS CHANGE CONSTITUTE A 50-59 ACTION 7 NO -

(85) DOES THIS CHANGE CONSTITUTE A UNRETIEWED SAFETT QUESTION 7 YES (9) RECONMENDED IVE PERMANENT STATUS TES W NO (l "NA" POR PER h W.E STATUS (10) EIPIRATION DAT(,,, AlA's 40 nAvs NArTyrs von TrMposinY stiT"s

% wu;7c3 ,ggg,g DATE 5-/E6 )b50P. _ . .

f. Organic peroxides
g. Phenol-concentrated /
h. Acetone
1. Butane J. Carbon Disulphide
k. Chloroform
1. Ethyl Ether
m. Ethylene Dichloride
n. Methylene Chloride

Attachment A

' ' AD-QA-311 -

Revision 6 Page 31 of 58 Solidification Record Sheet Part II Sampling and Pre-Solidification Analysis Instructions

a. Step 1 - Identify which mixing tank A or B or other tank that is to be processed by a check mark, or identify.
b. Step la - Enter sample number. ,
c. Step 2 - Check that the pH of the sample taken from the tank to be processed is within a range acceptable for solidification.
d. Step 3 - Enter the wet weight percent settled solids and 3 the weight percent sodium sulfate, and the percent water by volume of the sample.

}

e. Step 4 - Enter the density of the sample taken from the tank. Be sure to use the density of the whole sample not just of the liquid phase.
f. Step 5 - Check off the quantity of oil in the sample by noting either "none" or less than one percent, "< IP." or indicating the percentage of oil.

> g. Step 6 - Check that a copy of the radionuclide analysis is attached.

['

h. Step 7 - Based on the isotopic analysis attached enter the curie concentration.

~

~

.I 1. Step 8 - Determine final product density.

J. Step 9 Identify here tne type of cement used (i.e.,

Type I)

k. Step 10a - For the process feed pump (OP-304) provide the pump flow rate to be used for the solidification process. If a Vendor Supplied system is provided enter waste volume.

FORM AD-QA-311-1, Rev. 6, Page 2 of 18 r

. Attachment A AD-QA-311 Revision 6 Page 36 of 58 Solidification Record Sheet Part IVa System Preparation and Processing Instruction (Vendor or alternate system)

a. Step 1 - Enter the serial number of liner to be used.
b. Step 2 - Check.that PP&L identification number is stenciled on the liner. (This must be the same as the number in Part III step 6).
c. Step 3 - Verify that the liner is properly positioned and ALARA consideration has been made for spills and expected dose rates.
d. Step 4 - Check and verify pre-waste transfer data,
e. Step 5 - Radwaste Supervision authorization to commence waste transfer.

fl Step 6 - Check and verify post waste transfer data.

g. Step 7 - Enter solidification parameters.
h. Step 8 - Check and verify presolidification data.
i. Step 9 - Radwaste supervision authorization to commence solidification.

J. Step 10 - Enter processing start time.

k. S'tep 11 - Enter processing stop time.
1. Step 12 - Remove mixer head drive from liner.
m. Step 13 - Check vacuum filters cleaned and emptied. _
n. Step 14 - Record hydraulic pressure.
o. Step 15 - QC verification for hardness / solidification by manual penetration tests visual observation for water in the liner.

, p. Step 16 - The actual curing time prior to capping shall be entered here.

q. Step 17 - Enter the Final solidified waste volume in cubic feet.
r. Step 18 - Supervisor review and release liner to Health Physics.

FORM A0-QA-311-1, Rev. 6, Page 7 of 18 l

6 l

l

, Attachment A AD-QA-311 -

Revision 6 Page 38 of 58 SOLIDIFICATICN RECORD SHEET Part I Cover Page

1. LINER Identification No.
2. WASTE TYPE (RWCU Filter sludge cannot be entered)
3. Sequential Liner No. of Waste Type
4. BATCH No.
5. Test Solidification required Yes/No
6. Approval for use Radwas+e Supervision FORM AD-QA-311-1, Rev. 6, Page 9 of 18

Attachment A AD-QA-311 Revision 6 Page 39 of 58 SOLIDIFICATION RECORD SHEET Part II Sampling and Pre Solidification Analysis

1. Waste Mixing Tank Sampled A ___B Other Date/ Time l la. Sample Number
2. Waste Stream pH Check
3. Type of Waste 1
a. Wet WT. % settled solids
b. WT. % Sodium Sulfate
c.  % Water by volume
4. Waste sample density gm/ml
5. Oil Content (check a or b, or enter % by volume in c)
a. None
b. Less 1%
c.  % oil
6. Isotopic Analysis Attached F' Check l 7. Estimated Curie Concentration uC1/cc
8. Final product density gm/cc
9. Type of cement to be used 1

Include nomenclature of type of waste, i.e. bead resin, powdered resin, carbon, oil, diatomaceous earth sodium sulfate or combination, etc, FORM AD-QA-311-1, Rev. 6, Page 10 of 18

4

. Attachment A- '

AD-QA-311 Revision 6 Page 40 of 58

10. Mixing Ratios SSES INPLANT SYSTEM VENDOR SYSTEM i Initial Initial
a. Waste (OP-304) gpm Waste ft' i b. Cement (0S-305) lb/ min Cement lbs/ft* of waste
c. Sodium Silicate (OP-309) gpm Sodium Silicate ib/ft' of waste Other additive liters / gallons hours. .

11,. -Cure time required

12. .The above tank has been analyzed and is acceptable for

- solidification at the indicated mixing ratios.

Chemistry Supervision Date Time J

f 1

i i

i FORM AD-QA-311-1, Rev. 6, Page 11 of 18 4

4

~

O

. Attachment A

. AD-QA-311 Revision 6 Page 44 of 58 Part IVa System Preparation and Processing (Vendor or alternate system)

1. Liner Serial Number
2. PP&L Liner Identification Number on liner Check
3. Liner properly positioned and ALARA consideration made Check
4. PRETRANSFER
a. Fill Head Installed and Properly Secured

. Check

b. All Transfer Lines Properly Connected / Secured Check All Transfer Lines Inspected for Visible Signs of Wear
c. Dewatering Hose Connected to Pump Skid Suction Check
d. High Level Alarm Probe Installed and Tested Check
e. Liner apron installed Check
5. Authorization to commence transfer.

Radwaste Supervision Date Time

6. POST-WASTE TRANSFER
a. Transfer Lines Flushed and All Valves Secured Check
b. Fill Head Removed Check
c. High Level Alarm Probe Removed and Plug Replaced Check
d. Inspection Plate Secured Check FORM A0-QA-311-1, Rev. 6, Page 15 of 18

. Attachment A' -

AD-QA-311 Revision 6 Page 45 of 58

7. Solidification parameters Waste in liner actual ft' Cement to be added to liner Ibs actual lbs Sodium Silicate to be added to liner Ibs actual lbs actual lbs/ft 2/ gallon Other additive added to liner Calcium Hydroxide to be added to liner lbs actual lbs QC Verification Date Time
8. PRE-SOLIDIFICATION
a. Mixer Head Drive Assembly Installed and Secured Check
b. Flexcon Cement Feed Properly Installed Check
c. Hopper Installed and Slide Gate Opened Check
d. Cement Discharge Brushed Out Check
e. Ball Valve Opened l Check
9. Authorization to commence solidification ~

Radwaste Supervision Date Time

10. Time processing started
11. Time processing stopped
12. Mixer Head Drive Assembly Removed from Liner and Installed in Stand Check
13. Vacuum Filter Cleaned and Emptied Check
14. Hydraulic Pressure Check FORM AD-QA-311-1, Rev. 6, Page 16 of 18

. Attachment A AD-QA-311 Revision 6 Page 46 of 58

15. Liner check for complete solidification and visible water or drainable water.
a. Penetration check (6.2.6.d)

QC Verification /Date/ Time

b. Visible water (6.2.6.d)

QC Verification /Date/ Time

16. Curing time actual (A minimum of 30 hrs is required.)
17. Final container solidified waste volume ft' of ft* ustble.

This is  % of the filled container volume.

18. Supervisory review and Health Physics notification.

Liner # meets the following criteria:

a. TYPE: A, B, C (circle one)
b. Classification: STABLE / UNSTABLE (circle one)

(operating procedure number used)

c. >85% Container volume utilized: YES/NO (circle one)

Radwaste Supervision Date Time PART V Filled Liner Data

1. Filled Liner Radiation Levels
a. Top mr/hr Bottom mr/hr 4 Quadrants 1 mr/hr 2 mr/hr .

3 mr/hr 4 mr/hr

b. Smearable Activity dpm/100cm
c. Container washdown / decon performed Yes/NR
d. Smearable activity after washdown/decon dpm/100cm FORM AD-QA-311-1, Rev. 6, Page 17 of 18

,-Attachment A AD-QA-311 -

Revision 6 Page 47 of 58

e. Liner ready for transfer to storage HP Tech. Date Time
2. Storage Location: RW / /

Date Time Initials LLWHF Date Time In i ti a l.s 3 .- Liner Capped / /

Date Time Initials

4. Shipment #
5. Solidified waste acceptable for disposal at burial site HP Foreman-Radwaste Date Time Quality Control Review Date Time
6. REMARKS:

FORM AD-QA-311-1, Rev. 6, Page 18 of 18

. Attachment B AD-0A-311 Revision 6 Page 48 of 58 DEWATERING RECORD SHEET Part I Cover Page

a. Step 1 - Enter the liner identification number from Radwaste Supervisor Log Book.
b. Step 2 - Enter the waste identification (i.e., Bead resin, Powdex, carbon, etc..)
c. Step 3 - Initial to ensure all documents are brou'ght together.

Part II Sampling and Pre-Dewatering Analysis

a. Step 1 - Sample the appropriate tank af ter a recire period of 1/2 hour or 1 tank volume as a minimum.
b. Step la - Enter Sample Number.

'c . Step 2 - Same as Step 1.

d. Step 3 - Collect a liquid sample from the traterial to be dewatered to assure the liquid will not be corrosive to a carbon steel liner.
e. Step 4 - Determine the oil content of the material to be dewatered.
f. Step 5 - Conduct an isotopic analysis of the material to be dewatered.
g. Step 6 - Enter the specific activity.
h. Step 7 - Enter the sample density.

FORM AD-QA-311-2, Rev. 6, Page 1 of 9

. Attachment B -

AD-QA-311 Revision 6 Page 50 of 58 Part IV Dewatering Operations Documentation

a. Step 1 - Check and verify pre waste transfer data.
b. Step 2 - Radwaste Supervision approval to commence waste transfer.
c. Step 3 - Check and verify post waste transfer data,
d. Step 4 - Radwaste Supervision approval to commence dewatering.
e. Step 5 - A specific operating procedure for the container will be used to document the applicable dewatering functions.
f. Step 6 - Enter Final Dewatered Waste volume.
g. St'ep 7 - Supervision review of dewatering documentation.

Part V Dewatered Container Data

a. Step 1 - Document the container radiological data on a blank survey form and attach the form to the Dewatering Record Sheet.

Use HP-TP-800 to assist in determining curie content of material being dewatered.

b. Step 2 - The storage location shall be assigned by the HP Radwaste Supervision.
c. Step 3 - Enter date and time liner is capped or sealed,
d. Step 4 - The shipment # and destination shall be designated by the HP -

~

Radwaste Supervision.

FORM AD-QA-311-2, Rev. 6, Page 3 of 9

. ~.

Attachment B

' A0-QA-311 Revision 6 Page 52 of 58 Part II Sampling and Pre-Dewatering Analysis

1. Waste Mixing Tank Sampled A B Check /NA Check /NA la. Sample Number
2. Other tank sampled Name
3. pH of liquid contained within solids if a Carbon Steel liner is used pH
4. Oil Content (check one)

None less than 1?e Isotopic Analysis attached 5.

Check

6. Specific activity of Dewatered Sample pCi/gm
7. Sample density gm/cc The above tank containing solids has been sampled and found to contain the isotopes and specific activities as indicated on the attached data sheets.

Chemistry Foreman Date Time FORM AD-QA-311-2, Rev. 6, Page 5 of 9 A

, - - , - - - - - -- ---.m ,,, , ,- - - -p, ,,, - - - - - - - , ---,g --n-.

o

. Attachment B AD-QA-311 -

Revision 6 Page 54 of 58 Part IV Dewatering Operations Documentation

1. PRE-WASTE TRANSFER
a. Liner Properly Positioned Check
b. Fill Head Installed and Properly Secured if required Check
c. All Transfer Lines Properly Connected / Secured All Transfer Lines Inspected for Visible Signs of Wear. Check i

Dewatering Hose Connected to Pump Skid Suction d.

Check

e. High Level Alarm Probe Installed and Tested Check
2. Authorization to commence transfer.

Radwaste Supervision Date Time  !

1

3. POST-WASTE TRANSFER
a. Transfer Lines Flushed and All Valves Secured Check
b. Fill Head Removed if required Check _I

~

c. High Level Alarm Probe Removed and Plug Replaced if required Check l
d. Inspection Plate Secured if required Check
4. Authorization to commence dewatering.

Radwaste Supervision Date Time

5. Attach the complete specific operating procedure check off sheet for the specific dewatering container being used Check FORM A0-QA-311-2, Rev. 6, Page 7 of 9

, Attachment B g

AD-QA-311 Revision 6 Page 55 of 58 I

I 6. Final Dewatered Waste Volume Ft2

7. Dewatering check off sheet review and (Use specific check sheet for liner being used) transferred to HP Foreman Radwaste Liner # meets the following criteria:
a. TYPE: A, B, C (circle one)
b. Classification: STABLE / UNSTABLE (circle one)
c. :85% Container Volume Utilized: YES/NO (circla one)

(applicable to steel liners only)

Radwaste Supervision Date Time Part V Dewatered Container Data

1. Container Radiation Levels
a. Top mr/hr Bottom mr/hr 4 Quadrants 1 mr/hr 2 mr/hr 3 mr/hr mr/hr 4
b. Smearable Activity dpm/100cm 2
c. Container washdown/decon performed Yes/No
d. Smearable activity after washdown/decon dpm/100cm 2 (attach radiological survey form)
e. Liner ready for transfer to storage HP Tech Date Time FORM A0-QA-311-2, Rev. 6, Page 8 of 9

. Attachment B

, AD-QA-311 Revision 6 Page 56 of 58

' Part V (Cont'd.)

2. Storage location: RW / /

Date Time Initials LLWHF / /

Date Time Initials

3. Liner capped or sealed / /

Date Time Initials

4. Shipment #

Destination HP Foreman-Racwaste Date Time Quality Control Review Date Time

5. REMARKS:

1 FORM A0-QA-311-2, Rev. 6, Page 9 of 9

PROCEDURE COVER SHEET PENNSYLVANIA POWER & LIGHT CO.

SUSQUEHANNA STEAM ELECTRIC STATION AD-QA-311 SOLID WASTE PROCESS CONTROL PROGRAM Revision 7 Page 1 of 60 Effective Date 1 05' $#c Expiration Date "/ M 8 8

(

\ t a g

! Revised Expiration Date I )ROCEDURE TYPE: PORC Y , NON-PORC , Alternate Review 20RC MTG. NO. 6-0 9 A (If applicable) ,

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Prepared by 1 IN Date 7/!S6 Reviewed by T JJ A Date 7//f/g6 i RecommendedsI / d[ N Date ~) /f- f/

l '3 ' tion Head / Manager Date ~7,!2 f6 Sup tendent of Plant FORM. A0-QA-101-1, Rev. 2, Page 1 of 1 L.

, AD-QA-311 Revision 7 Page 2 of 60 PROCEDURE REVISION INDEX

Title:

SOLIO WASTE PROCESS CONTROL PROGRAM Procedure No. AD-QA-311 Effective Rev. No. Description of Revision Date 7 1. Incorporated PCAF 1-86-767.-

2. Added responsibilities to the Radwaste Supervisor.
3. Added responsibilities for Nuclear Quality Assurance.
4. Added responsibilities for Materials Section.
5. Deleted reference to AD-QA-313.
6. Added 6.10, Use of High Integrity Containers.
7. Added CAUTION statement to FORM A0-QA-311-1 in response to NCR 86-375.

l

AD-QA-311

  • Revision 7 Page 3 of 60 TABLE OF CONTENTS PAGE SECTION 5

1.0 PURPOSE

~

5 2.0 SC0PE 5

3.0 REFERENCES

7 4.0 RESPONSIBILITIES 4.1 Senior Project Engineer - Radwaste 7 5

4.2 Shift Supervision 7 4.3 Radwaste Supervisor 7 4.4 Chemistry Group 8

4.5 Health Physics Radwaste Supervision 9 4.6 Quality Control 9 4.7 I & C Supervisor 10 4.8 Auxilary System Operator 10 4.9 Vendors providing solidification and/or Dewatering Services 10

~

4.10 Nuclear Quality Assurance 10 11 4.11 Materials Section 11 5.0 DEFINITIONS 12 6.0 PROCEDURE 6.1 Waste Types 12 16 6.2 Solidification Product Control 6.3 Solidification Agent Control 22 i G.4 Equipment Calibrations 23 6.5 Solidification Record Sheet 23

, AD-QA-311 Revision 7 Page 4 of 60 PAGE SECTION ,,

6.6 Solidification Processing 24 6.7 Radioactive Spent Resin Dewatering 24 6.8 ' Changes to the Solid Process Control 25 6.9 Container Inspections 25 6.10 Use of High Integrity Containers 25

[

6.11 Storage of High Integrity Conta ners 26 6.12 Uses of High Integrity Containers 26 6.13 Closure of High Integrity Containers 28 7.0 RECORDS 29 ATTACHMENTS ATTACHMENT' PAGE A Solidificatien Record Sheet 30 B Dewatering Record Sheet 48 C Susquehanna Guaranteed Waste Volume Record 57 l D U.V. (sunlight) Exposure Tracking Record Sheet 59 ,

. A0-QA-311 Revision 7 .

Page 6 of 60 -

l 3.14 AD-QA-765, Solid Radwaste Program 3.15 AD-QA-605, Calibration of Installed Plant Instrumentation 3.16 CNSI Topical Report " Mobile Cement Solidification System" 4313-01354-01P-A 3.17 CNSI Topical Report " Polyethylene High Integrity Containers" CNSI-HIC-14571-01-P l 3.18 CNSI Topical Report "CNSI Dewatering Control Process Containers Topical i Report" CNSI-DW-11118-01-P 3.19 DHEC-HIC-PL-001 South Carolina Certificate of Compliance for CNSI High Integrity Containers 3.20 DHEC-HIC-PO-006 South Carolina Certificate of Compliance for CNSI Overpak High Integrity Containers 3.21 DHEC-HIC-FRP-003 South Carolina Certificate of Compliance for CNSI Fiberglass Reinforced Polyester 24 Inch Pressure Vessel as a High l Integrity Container .

t 3.22 CNSI FO-AD-002 Operating Guidelines for use of Polyethylene High Integrity Containers 3.23 CNSI F0-AS-004 Operating Guidelines for use of Fiberglass Reinforced Plastic High Integrity Containers 3.24 CNSI FO-0P-019 Polyethylene High Integrity Container Overpak Handling Procedure 3.25 WHNI STD-D-03-009 USERS MANUAL for HNOC RAOLOK-100, RADLOK-200 and .

RADLOK-500 containers 3.26 WHNI ST0-0-03-008 USERS MANUAL for HNOC RADLOK-55 container 3.27 OHEC-HIC-PL-005 South Carolina Certificate of Compliance for WHNI RADLOK-100 and RADLOK-200 containers.

3.28 DHEC-HIC-PL-004 South Carolina Certificate of Compliance for WHNI RADLOK-55 container ,

3.29 CHEC-HIC-PL-0014 South Carolina Certificate of Compliance for WHNI RAOLOK-500 1

3.30 NOI-QA-6.5.1 Radwaste Program 3.31 AD-QA-210, Procurement Control Activities ,

l i I

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-t- *' +'- - < '

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- AD-QA-311

' ~

Revision 7 Page 8 of 60 4.3.8 Maintains a log of Batch processes for test Solidification requirements.

4.3.9 Ensure Radwaste solidification personnel are adequately trained per NTI-QA-42.3.

4.3.10 Classification of waste to be processed.

4.3.11 Ensure that waste streams loaded into High Integrity Containers are sampled and evaluated for radionuclide and chemical composition applicable to the use of High Integrity Containers.

4.3.12 Ensure proper selection of High Integrity Containers for the waste stream being processed and packaged.

. 4.3.13 Ensure proper inspections and documentation are complete .

prior to use of a High Integrity Container and container is properly used up to the point of transfer to Health Physics.

4.3.14 Complete and process High Integrity Container General Certification statement to ensure the container is used properly.

4.4 Chemistry Group responsibilities:

4.4.1 Sampling as required.

4.4.2 Performing required analysis in accordance with approved chemistry procedures.

Performing test solidification if required.

4.4.3 4.4.4 Providing the Isotopic mix and concentration of isotopes detected in the material sampled for solidification.

4.4.5 Providing mix ratios to the Radwaste Supervisor.if analysis results indicate the waste type is out of the normal envelope for Solidification or an abnormal waste type is encountered.

4.4.6 Ccopleting Chemistry portion of the Solidification Record Sheet. (Attachment A) and Dewatering Record Sheet.

(Attachment B).

4.4.7 Ensures personnel are adequately trained per NTI-QA-41.2.

4.4.8 Provide sampling and analysis support as' necessary for the use of High Integrity Containers. -

" " . AD-QA-311 Revision 7 -

. Page 10 of 60 4.7 I&C Supervisor Ensure that periodic calibrations and inspections are performed as required.

4.8 Auxiliary Systems Operator is responsible for:

4.8.1 Operating the solidification and dewatering equipment in accordance with approved operating procedures as directed by the Radwaste Supervisor and Assistant Unit Supervisor.

4.8.2 Completing applicable portions of the Solidification and Dewatering Record Sheet.

4.9 Vendors providing Solidification and/or Dewatering services.

4.9.1 Vendors providing solidification and/cr dewatering service shall have in place a valid contract for said services and provide test data or make same available for PP&L review during vendor audits to demonstrate that their services and equipment meet the applicable regulatory and burial site limitations for the function they are'providing.

4.9.2 Vendors shall provide training documentation to demonstrate that the personnel being provided, to conduct the applicable service, are in fact trained and knowledgeable in the applicable functions.

4.9.3 Vendors shall provide procedure that are or can be placed into the SSES procedure format for the functions being

  • provided.

C.

i 4.9.4 Vendors shall have an acceptable Quality Assurance Program that covers the services being provided. The vendor shall work within the SSES Quality Assurance Program when applicable.

4.9.5 Vendors shall complete applicable sections of Attachments A,B and C as required for each liner processed.

i 4.10 Nuclear Qua,lity Assurance is Responsible for:

4.10.1 Receipt inspection of High Integrity Containers and document review to ensure conformance.

4.10.2 Ensure Certificate of Compliance (C of C) is received with the High Integrity Container.

g --

-- -- - , - ,-. ~ , . - - , - - , , , - , , - - , , , , , , -

. AD-QA-311 Revision 7 Page 11 of 60 4.11 Materials Section is responsible for:

4.11.1 Ensure High Integrity Containers are not exposed to ultra violet light (sunlight).

4.11.2 Ensure proper material certification is complete prior to issuance of High Integrity Containers to the plant for use.

4.11.3 Completion of applicable portions of Form AD-QA-311-4.

5.0 DEFINITIONS

~

5.1 Batch - The total volume of waste contained in a waste mixing tank, '

i spent resin tank concentrates tank or phase separator that has been sampled for solidification.

5.2 Solidification - A conversion of radioactive materials from liquid and solid systems to a monolithic immobilized solid with definite volume and shape,-bounded by a stable

. surface of distinct outline on all sides (free standing), with a free water content of less than

.5% by volume.

5.3 Waste Type - The specific content of the waste to be solidified and may be Evaporator Concentrates, Filter Demineralizer Media, Dewatered Filter Sludges, Dewatered Bead resins or a coinbination of each.

5.4 Waste Pre-Conditioning - The physical or chemical adjustment of the waste to bring it within an established envelope to' assure solidification, e 5.5 Curing Time - The time allowed for the solidified product to set prior to transporting or capping the liner.

5.6 Mixing Ratio - The amounts of waste, cement and additive required for satisfactory solidification.

5.7 Test Solidification - The mixing of waste (s) and solidification agents in the labratory to support selection of mixing ratios.

5.8 Dewatered - The removal of water from solid material to a point where less than 1% or 0.5% by volume remains as applicable to containers used and burial site limits.

5.9 Liner - The physical container in which the solidification product is deposited.

AD-QA-311 Revision 7 "

Page 25 of 60

f. Quality Control personnel shall provide verification as required by the Dewatering Record Sheet.

6.7.5 The HP Foreman Radwaste shall assure that SSES is a authorized user of High Integrity Containers (HIC) used at SSES for the purpose of Radwaste disposal prior to the use of a cpecific type HIC.

6.8 Changes to the Solid Waste Process Control Program.

6.8.1 Any changes to the Solid Waste Process Control Program shall be provided in the semiannual Radioactive Effluent Release Report filed with the NRC.

6.8.2 Any changes to the Solid Waste Process Control Program shall be approved by the Plant Operations Review Committee (PORC).

6.9 Container Inspections 6.9.1 Quality Control shall inspect the containers to be used for solidification and dewatering.

a. This inspection shall assure High Integrity containers are acceptable for use in accordance with the Certificate of Compliance.
b. This inspection shall assure that prior to use, the containers to be used for solidification or dewatering are intact and their internals are free of any visual damage that would prevent them from performing their intended function. _

6.10 Use of High Integrity Containers (HIC) 6.10.1 Prior to using a High Integrity Container, procedures shall be established to define the specific requirement that shall be met during the use of the container.

6.10.2 The procedure shall contain:

a. Documentation requirements that specific conditions have been met such as inspection and exposure to degrading conditions.
b. Instructions as to how to handle the container and properly close the container.
c. Instructions for the on-site storage of loaded containers for ultimate shipment for disposal.

A0-QA-311 Revision 7

  • Page 26 of 60 6.10.3 The procedures shall provide a method for documenting required information relevant to the container from initial receipt to shipping for disposal.
a. Required information shall be based upon the container certificate of compliance and disposal site requirements,
b. Retention and utilization of the documentation shall be defined in the procedures.
c. The procedures shall establish specific Quality Control inspection requirements.

6.10.4 Prior to the first shipment of a specific type of High Integrity Container, authorization shall be requested and received from the applicable regulatory agency governing the use of the container in question at the disposal site of concern.

6.11 Storage of High Integrity Containers 6.11.1 High Integrity Containers (HIC) stored in direct sunlight or in areas where there is a strong source of ultraviolet radiation must be filled within one year of the date of manufacture.

6.11.2 High Integrity Containers stored away from any sources of ultraviolet radiation must be filled within two years of the manufacture date, or specific guidance from the vendor must be obtained.

6.11.3 Once filled a High Integrity Container may be stored in an approved storage facility for up to (5) five years prior to burial. ,

6.11.4 Short exposures to sunlight, such as occurring during shipment and on site transfer need not be counted when determining total ultraviolet exposure.

6.12 Uses of High Integrity Containers 6.12.1 High Integrity Containers may be used to package the following waste materials for burial at the Barnwell South Carolina low level waste burial site.

a. Dewatered bead ion exchange resin
b. Dewatered powdered ion exchange resin r

- Attachment A *

. AD-QA-311 Revision 7 5

-Page'32 of 60 Part II cont'd Instructions

1. Step 10b .For the cement feed system (05-305) provide the cement feed rate to be used for the solidification J process. If vendor supplied System is provided, enter Cement Volume in ib/ft' of waste.

I

m. Step 10c - For the liquid sodium silicate feed p;mp (OP-309) provide the pump feed rate to be used in the solidification process. If Sodium Silicate or other agent is used with vendor provided systems, enter volume in Ib/ft 2 of waste.
n. Step 11 - Enter the actual curing time of test solidification.
o. Step 12 - Chemistry Superv'ision shall sign with'the date and time signed that the waste in the identified tank "

has been sampled and analyzed in accordance with

  • approved procedures and is acceptable for solidification at the indicated mixing ratios.

i i

d N '

. Ja,

, -r.c =

/

s

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FORM AD-QA-311-1, Rev. 7, Page 3 of 18 t

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,. - - . _ , - . - - , _ . - . . - . - . - - - . - - - ~ _ _ . , . , . - - - - . - . - - - - - - .

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Attachment A s 3

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AD-QA-311 Revision 7

' - Page 44 of 60 PartIViSy.stemPreparationandProcessing (Vendor or alternate system)

1. Liner Serial Number D
2. PP&L Liner Identification Number on liner Check q, 3. Liner properly positioned and ALARA consideration made Check
4. pRETRANSFER ,
a. Fill' Head Installadcand Properly Secured Check

^

b. The following checks are. complete.

Initial (1) 611 ' transfer lines properly. connected / secured.

(2) %11 transfer lines inspected for visible signs of wear, e (3) Transfer line drair< s valves: checked closed and capped.

" (4) Proper transfer valve opene'd.

(5) Three way valva in " Fill" position.

(6)! Communications' established.-

c. Dew [teringHoseConnectedtoPumpSkidSuction Check
d. HighLevelAlarm.Proba'$stalledandTested

- Check '_

e. Liner apron installed -

Check

5. Au*.horization ?.o conntnce transfer.

Radwaste Supervision ' Date Time

6. POST-WASTE TRANSFER
a. Transfer Lines Flushed and All Valves Secured

- Check

b. Fill Head R'emoved

, Check FORM AD-QA-311-1, Rev. 7, Page 15 of 18

,1

,x ,

W

- Attachment A

  • AD-QA-311 Revision 7 Page 45 of 60
c. High f.e dl Alarm Probe Removed and Plug Replaced
d. Inspection Plate Secured Check
7. Solidification. parameters Waste in liner actual ft' Cement to be added to liner lbs actual lbs Sodium Silicate to be added to liner ibs actual lbs Other additive added to liner actual lbs/ft'/ gallon Calcium Hydroxide to be added to liner lbs actual lbs QC verification Qate Time-s

/

8. PRE-SOLIDIFICATION CAUTION T

. FOR SOLIDIFICATION OF WASTE CONTAltiERS WHICH WERE PREVIOUSLY USED, AND EMPTIED BY

'SLUCING SUCH AS SODIUM SULFATE, A SEPARATE BATCH NUMBER SHALL BE ASSIGNED AND WILL REQUIRE SAMPLING FOR TEST SOLIDIFICATION AND ISOTOPIC ANALYSIS.

t al Mixer Head Drive Assembly Installed an'd Secured Check

b. Flexcon Cemint Feed Properly Installed Check _
c. Hopper Installed and Slide Gate Opened l d. Cement Discharge Brushed Out

' Check I

l 9 Y e. Ball Valve Opened Check Authorization to commence solidification 9.

Radwaste Supervision Date Time l '

' 10. Time processing started ,

, FORM AD-QA-311-1, Rev.' 7, Page 16 of 18 l

l l

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F ilt y

e

.+ ., S

. Attachment 0 o u' AD-QA-311 Revision 7 Page 59 of 60 q

l.\ HIGH INTEGRITY CONTAINER U.V. EXPOSURE TRACKING RECORD SHEET j

a. Step 1 - Enter container vendor serial number from Certificate of Compliance or Receipt Inspection Report.
b. Step 2 - Enter date of receipt.
c. Step 3 - Enter date of manufacture,
d. Step 4 - Enter hours of uitra violet light exposure from C of C.
e. Step 5 - Enter date NQA completes receipt inspection.
f. Step 6 - Check to ensure material tag is attached,
g. Step 7 - Enter I urs of ultra violet (sunlight) light exposure the container received since receipt prior to delivery to plant.
h. Step 8 - Enter date cf issuance to the plant.
i. Step 9 - person in plant receiving container signs for receipt of container at plant.

t

j. Step 10 - Enter date of receipt at plant.
k. Step 11 - Enter date container is filled with waste. Must be within 2 years of manufacture date.
1. Step 12 - Enter date container is shipped for burial. Must be within 5 years '_

of date of manufacture.

m. Step 13 - Enter hours of ultra violet exposure since delivery to plant.
n. Step 14 - Enter total hours of ultra violet exposure. Add items Step 4, Step 7 and Step 13.
o. Step 15 - Person completing form signs, dates and attaches this form to the -

dewatering record sheet if applicable.

FORM AD-QA-311-4 Rev. O, Page 1 of 2 i

m-,

' Attachment 0

  • AD-QA-311 Revision 7 Page 60 of 60 HIGH INTEGRITY CONTAINER U.V. EXPOSURE TRACKING RECORD SHEET
1. Container serial number
2. Date of receipt
3. Date'of manufacture
4. Hours of U.V. exposure at time of receipt
5. Receipt inspection complete (Date)
6. Material tag (Green) attached (Check)
7. Hours of U.V. exposure since receipt
8. Date of issuance to plant
9. Received by (Plant)
10. Date of receipt
11. Date of filling (within 2 yrs of Mfg. Date)
12. Date of shipment (within 5 yrs of Mfg. Date) 3
13. Ho'urs of U.V. exposure since delivery to plant
14. Total hours of U.V. exposure (Items 3,6,12)

< 15. Completed by Date

(

f l

l FORM A0-QA-311-4 Rev. O, Page 2 of 2 l

l

[

" SFBIION 4 5

n REPORTS OF EXCEPIION TO I1E SSES ITFLUENI MONITORING PROGRAM INERE WERE NO INSTANCES DURING 'INE REPORT PERIOD IN WHICH AIRBOILNE OR WATERBORNE EFFLUENT MONITORING INSTRUMENIATION VAS DECLARED INOPERABLE AND WAS NOI RESIORED 10 OPERABILITY WITHIN THE TIME PERIOD SPECIFIED IN TECHNICAL SPECIFIFCATION TABG 3.3.7.10-1 OR 3.3.7.11-1 ACIION STATEMENIS.

)

i 76 I

P \

]M] Pennsylvania Power & Light Company Two North Ninth Street

  • Allentown, PA 18101 = 215 / 770w5151 Harold W. Keiser Vice President-Nuclear Operations 215/770-7502 AU6 291986 Dr. Thomas E. Murley Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 SUSQUEHANNA STEAM ELECTRIC STATION SEMI-ANNUAL RADIOACTIVE EFFLUENT RELEASE REPORT Docket Nos. 50-387/NPF-14 PLA-2708 FILE R41-2A and 50-388/NPF-22

Dear Dr. Murley:

In accordance with 10CFR50.36a(a)(2) and the Susquehanna SES Unit 1 and 2 Technical Specifications, attached is the Semi-Annual Radioactive Effluent Release Report for SSES Units 1 and 2 covering the period January 1 through June 30, 1986.

Very truly yours, H. W. Keiser Vice President-Nuclear Operations cc: Director Office of Inspection & Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Director of Nuclear Reactor Regulation Attention: Ms. E. Adensam, Project Director BWR Project Directorate No. 3 Division of BWR Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Ms. M. J. Compagnone - USNRC Mr. L. R. Plisco - USNRC 26 9,\\

.\

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