PLA-2031, Monthly Operating Rept for Dec 1983

Monthly Operating Rept for Dec 1983

ML20079E434
Person / Time
Site:	Susquehanna
Issue date:	12/31/1983
From:	Kenyon B, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-2031, NUDOCS 8401170291
Download: ML20079E434 (26)

Text

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[ AVERAGE DAILY UNIT POWER LEVEL

,,h 3 DOCKET NO. 50-387

t. "% UNIT One E s0 DATE 01/09/84 COMPLETED BY L.A. Kuczynski O?RK Si TELEPHONE (717)S42-2181 MONTH December, 1983 DAY AVERAGE DAILY POWFP LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1058 37 0 2 1021 gg 0 3 36 39 0 0 0 4 20 5 0 21 0 _

6 0 0 22 7 0 3 0 8

0 0 24

, 0 . 25 0 10 0 26 0 0 0 11 27 ,

0 0 12 3 13 0 2, 0 14 0 30 0 15 0 3 0 16 0 INS 1RUCT10NS On this format list the average daily unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

8401170291 831231 PDR ADOCK 05000387 ft PDR ,

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L bk lHIM J OPERATING DATA REPORT 4 0 DOCKET NO. 50-387 DATE 01/09/84 OpkiC Sifs COMPLETED BY l. . A. Kuczynski TELEPilONE (717)S42-2181 OPERATING STATUS Unit 1 Susquehanna Steam Electric Station Notes

1. Unit Name:

2. Reporting Period: December, 1983 3293

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1068

7. Maximum Dependable Capacity (Net MWe): 1032

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

None

9. Power Level To Which Restricted,If Any (Net MWe): None

10. Reasons For Restrictions,if Any: None This Month Yr to-Date Cumulative

11. Hours In Reportu;2 Period 744 4.969 4,969

12. Number Of Hours Reactor Was Critical 51.8 3,845,3 - 3.845.3

13. Remeior Reserve Shutdown Hours 0 156.7 156.7

14. Hours Generator On-Line 5!.8 3.768.3 3,768.3

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 163.960 11.251.818 11,251,818

17. Cross Electrical Energy Generated (MWH) 52.900 3,666,550 3.666.550

18. Net Electrical Energy Generated (MWH) 50.757 3.536.373 3,536,373

19. Unit Service Factor 7J 75.8 75.8

20. Unit Availability Factor 7.0 75.8 75.8

21. Unit Capacity Factor (Using MDC Net) 6.6 69.0 69.0

22. Unit Capacity Factor (Using DER Net) 6.4 66.8 66.8

23. Unit Forced Outage Rate 0 12.0 12.0

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Each):

None

25. If Shut Down At End Of Report Period. Estimated Date of Startup:

7 February 1984

26. Units In Test Status (Prior to Commercial Operation): Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (9/77 )

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.a'y F'$] z UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-387 hD E NfC @p f[ REPORT MONTil December, 1983 UNITNAME One DAlt 01/09/84 COMPLETED BY L.A. Kuczvnski TELEPHONE (717)S42-2181

, .! ? }g .Yh Licensee E

% "o Cause & Corrective No. Date g 3g .c j E H

$E 5 j if; y Event Report #

g '2 mV {

g Action to Prevent Recurrence 3

20 831203 S 692.2 H 2 N/A ZZ ZZZZZZ Manual scram of reactor from a reactor power level of 33 percent to commence tie-in outage.

No action required to prevent recur-rence.

This was a scheduled event.

I 2 3 4 F: Forced Reason: Method: Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1 -Ma.1ual for Preparation of Data B. Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C. Refueling 3 Automatic Scram Event Report (LER) File (NUREG-D-Regu!atory Restriction 4-Other (Explain) 0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit I - Same Source (9/77) Il-Other (Explain)

F y

SUSQUEHANNA STEAM ELECTRIC STATION Docket Number 50-387 Date 01-09-84 Completed By L.A. Kuczynski Telephone (717)542-2181 i

Challanges to Main Steam Safety Relief Valves None Changes to the Offsite Dose Calculation Manual See Attachment Major Changes to Radioactive Waste Treatment Systems None Diesel Generator Unit Failures During the performance of Surveillance Test Procedure S0-24-005, " Eighteen Month Test Diesel Generator Air Start Operability, ESW Automatic Initiation, Auto Start and Twenty-Fcur Hour Diesel Operability Run", Ciesel Generator

'C' tripped due to a generator over excitation alarm / trip. The cause of the trip was determined to be related to Startup Transformer Tap changes that increased plant voltage during the test. The test was classified as non-valid in accordance with Regulatory Guide 1.108, Section c.2.e.(2) in that the trip was caused by a condition bypassed during emergency operation.

There have been no failures in_the last 100 valid test. A followup diesel surveillance test was conducted after the trip; diesel tripping logic and relay operation were found to be operational . The generator's field current was determined to be within its specified values. The generator protective relay settings are being evaluated and any necessary changes will be imple-mented.

The current surveillance frequency remains 31 days in compliance with Technical Specification Table 4.8.1.1.2-1 and Section c.2.d of Regulatory

- Guide 1.108.

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ATTACHMENT TO December,1983, Monthly Operating Report Change to tne Offsite Dose Calculation Manual o

These revised pages were made effective on October 25, 1983 upon signature by the Marager-Nuclear Support.

Changes have been denoted by revision bars in the right margin. The reasons for the changes are as follows:

Clarify that actual MPC values for identified mixtures can be used for liquid radwaste monitor setpoint determination in lieu of using the MPC for an unidentified mix (p.8).

To clarify setpoint methodology for the lianid radwaste effluent monitor (pp.8,8b)'.

To include methodology for cooling tower blowdown line and LRW discharge line and LRW discharge line flow rate setpoints (p.8b).

To reflect the fact that the SSES vent monitors use calibration factors to convert count rate to activity, therefore, setpoints are input as uCi/cc (p.11).

To correct SSES Tech. Spec, table number references (pp.14,17,22).

To clarify the frequency of analysis for several Radiological Environmental Monitoring Program (REMP) sample types (pp.41,42).

To update REMP sampling location descriptions and designations (pp.41,42,43,45).

To provide sample calculations for the updated LRW monitor setpoint methodology (p. A1,A2) .

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PENNSYLVANIA POWER & LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATivis -

0FFSITE DOSE CALCULATION MANUAL x

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TABLE OF CONTENTS Page Revision Date

1.0 INTRODUCTION

.................................. 1 7/12/82 2 5/11/82 3 4/77/83

' 4 5/11/82 s

5 5/11/82 4/27/83

' 6 2.0 SETP0INTS..................................... 7 4/27/83 2.1. LIQUID EFFLUENT MONITORS.................. 7 4/27/83 2.2 GASEOUS EFFLUENT MONITORS................. 8 4/27/83 8b 10/25/83 9 4/27/83 10 5/11/82 11 10/25/83 12 5/11/82 13 5/11/82 3.0. LIQUID EFFL'JENT CONCENTRATION MEASUREMENTS. . . . 14 10/25/83 15 10/25/83 ~

4.0 GASEOUS EFR UENT DOSE RATE MEASUREMENTS....... 16 4/27/83 4.1 NOBLE GASES............................... 16 4/27/83 4.2 RADIONUCLIDES OTHER THAN NOBLE CASES...... 17 10/25/83 18 4/27/83 19 4/27/83 3

20 4/27/83 5.0 INDIVIDUAL DOSE DUE TO LIQUID EFFLUENT. . . . . . . .

21 4/27/83 22 10/25/83 23 5/11/82 24 5/11/82 6.0 INDIVIDUAL DOSE DUE TO GASEOUS EFFLUENT....... 25 4/27/83 6.1 NOBLE GASES............................... 25 4/27/83

)

6.2 RADIONUCLIDES OTHER THAN NOBLE GASES...... 26 4/27/83 27 4/27/83 28 k 5/11/82 29 5/11/82

,; 7.0 TOTAL D0SE....................................

. 30 4/27/83 31 5/11/82

' 8.0 OPERABILITY OF WASTE TREATEMENT SYSTEMS....... 32 4/27/83

., 8.1 LIQUID WASTE TREATEMENT................... 32 4/27/83 N 8.2 GASEOUS WASTE TREATMENT................... 32 4/27/83 g' .

33 5/11/82 8.3 SOLID WASTE TREATMENT..................... 34 4/27/83

,L' ? -

35 4/27/83 3.6 5/11/82 37 5/11/82 38 5/11/82 1

OCT 25 GB3

_-_ ._.c.-,_.,_ _ _ , _ . _ - - . _ _ _ .

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9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PRCGRAM. 39 7/12/82 9.1 DEFI.NITI0NS...........................,,.. 39 7/12/82 -

9.2 MONITORING PR0 GRAM........................ 39a 4/27/83 9 . 3 CEN SUS P R0 GRAM . . . . . . . . . . . . . . . ; .'. . . . . . . . . . . - 40 4/27/83 40a 7/12/82 41 10/25/83 42 10/25/83

' 43 10/25/B3 44 5/11/82 45 !O/25/83 46' S/11/82 47 5/11/82

. 48 4/27/83 APPENDIX A - SAMPLE CALCULATIONS OF ODCM PARAMETERS........................... A-1 10/25/83 A-2 10/25/83 4-3 5/11/82 A-4 5/11/82 A-5 5/11/62

, A-6 5/11/82 A-7 5/11/82 l A-8 5/11/82 l A-9 5/11/82 A-10 5/11/82 A-11 .5/11/82 A-12 5/11/82 A-13 '5/11/82

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APPENDIX B - REPORTING REQUIREMENTS............... B-1 5/11/82 B-2 5'/11/82 B-3 5/11/82 B-4 5/11/82 APPENDII C - SITE SPECIFIC INFORMATION USED IN GASPAR....................... C-1 5/11/82 APPENDIX D - SITE SPECIFIC INFORMATION ' '

USED IN LADTAP....................... D-1 4/27/83  !

b-2 4/27/83-D-3 4/27'/83 11 CCT 251963 9

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_ _ _ _ _ _ _ _ _ _ _ _ .m.

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.u LIST OF TABLES

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a age Revision Date Table 1 Radiological Effluent 0bjectives and Standard's.... 6 4/27/83 Table 2 Dose Factors for Noble Gases and Daughters........ 12 5/11/82 Table 3 Annual Average Relative Concentrations and Deposition Rates..................................

1 18 5/11/82 )

! Table 4 Dose Parameters for Radionuclides Other Than i

Noble Gases....................................... 20 4/11/83 Table 5 Liquid Dose Parameters for' Adults................. 23 5/11/82 Table 6 Maximum Pathway Dose Factars Due to Radionuclides Other Than Noble Gases.............. 28 5/11/82 Table 7 Operational Radiologicsl Environmental Monitoring Progras................................ 41 10/25/83 42 10/25/83

• 43 10/25/83 l

table 8 Detection Capcbilities for Environmental 1

! Sample Analysis................................... 46 5/11/82 1

Table B-1 Radiological Environmenhal Monitoring Program Annual Summary.................................... B-3 5/11/.82 Table B-2 Reporting Levels for Nonroutine Operating

r. Reports........................................... B-4 5/11/82 l ,.

I I

iii ,0CT 25503

t A

LIST OF FIGURES Page, Revision Date Figure 1 Flow Chart of Offsite Dose Calculations..... 3 4/27/83 Figure 2 Liquid Radwaste System Flow Diagram......... 33 5/11/82 Figure 3 offgas' and Recombiner System Flow Diagram.. . 36 5/11/82 Figure 4 Standby Gas Treatment System Flow Diagram...

37 5/11/82

. Figure 5 Solid Waste Management System Flow Diagram.. 38 5/11/82 Figure 6 Onsite Environmental Sampling Locations -

Susquehanna SES............................. 44 5/11/82 Figure 7 offsice Environmental Sampling Locations -

Susquehanna SES............................. 45 10/25/83 iv ,

GCT 251503 9

I f= the flow setpoints as measured at the radiation '

monitor Iveation, in voluae per unit tine but in the ,

same units as F.

F= the dilution water flow setpoint as measured prior to the release point, in volume per ~ unit time.

Radioactive liquid effluents from the SSES are only discharged as batch releas'es and are discharged thruagh the liquid radwaste

effluent line. The radioactive liquid waste stream is diluted in the plant dis. charge (cooling tower blow-down) line prior to entering the Susquehanna River. The limiting batch release concentration (c) corresponding to the liquid radwaste effluent line monitor setpoint is calculated from the abcVe expression.

The MPC value used for the liquid effluent cencentration. limit (C) in the above expression for the liquid radwaste effluent line monitor setpoints is 1 x 10~I'uci/nl or the actual M?C for identified mixtures. Therefore, the expression fo: determining -

. the setpoint on the liquid radwaste effluent line monitor becomes:

e < (1 x 10

~

)FEf f (uci/ml) (2)

+

In order to prevent spurious isol'ations by the LRW effluent radiation monitor, the setpoint concentrati>n, c, can be defined as:

e = X*(A)

, where (A) is the actual tank activity, and I > l' The setpoint dilution factor must then be some facto.r Y (where Y > X), times the ninimum dilution factor.

F + f'\ = (A)

( f /M- MPC s

, where(F_+f')i a the minimum dilution factor f

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0CT 251983 ..

l

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- 8-

yf ,Y*(A) i t MC .

where F + f = the setpoint dilut!tn factor f -

The requiraments of Equation (2) are then met as follows:

" T'(A) = MPC IF + f g

f

)

Since, by definition, Y > I and Y(A) > X(A), then (c) = %(A) < KPC(IF + f)) f The setpoint concentration (c) can then be converted to a setpoint count rate value by use of the monitor calibration factor.

Setpoint (epm) = c (uci/ml)

(3)

Cal. Factor (UCi/ml per epm)

The setpoint for the dilution water flow (cooling tower blowdown) I is 5000 spm from either cooling tower basin. The setpoint for the LRW discharge flow can then be determined from:

F+f= (A) *Y.

f MPC .- .

Sample calculations for determining the release concentration limits and setpoints are given in Section t. 1.1 of Appendix A.

2.2 GASEOUS EFFLUENT MONITORS SPECIFICATION 3.3.7.11 .- IRE RADI0 ACTIVE GASEOUS EFFLUENT -

MONITORING INSTRUMENTATION CHANNELS SHOWN IN TABLE 3.3.7.11-1

, SHALL BE OPERABLE WITH THEIR ALARM / TRIP SETPOINTS SET TO FNSURE f

OCT 251983 4

_ _ _ _ .. _8b -- _ _ _ _ _ . __ _ __ , ,

I 1 .

500 = the 10 CFR 2b annual whole body dose limit (arem/yr) to an individual in an unrestricted .

area.

L =

the skin dose factor due to beta emissions for

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each (mremidentified nog)lefrom

/yr per UCi/m gasTable radionuclide

2. (1)

Mg =

the air dose factor due to gamma emissions for eachidentifiednoglegasradionuelide(1)

(mrad /yr per uCi/m ) from Table 2 (conversies constant of 1.1 converts air dose-nrad to skin dose-arem) .

3000 =

the 10 CFR 20 annual skin dose limit (nrem/yr) to an individu&l in an unrestricted area.

Xenon-135 should be the principal noble gas radionuclide rele'ased fr'om the reactor building vents and the standby gas treatnent system vent while 'Ienon-133 should be the principal noble gas radionuclide released from the turbine building vent due to the

. offgas holdup system. It is appropriate that these noble gas radionucides be used as the reference isotopes for establishing the particular monitor setpoints. The whole body dose will be the most limiting and the release rate limit is calculated by substituting the. appropriate values in Equation 4. After the

• release rate limit is determined for each vent, the correspond-ing vent concentration Itaits can be calculated based on normal vent flow rates:

Setpoint[ucif= 9'iv (UCi/sec) (6) j cc) Flow rate (cc/sec)

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OCT 251983 T

I

3.0 LIQUID EFFLU1NT CONCENTRATION MEASUREMENTS SPECIFICATION 3.11.1.1 - THE CONCEN'GAIION OF RADI0 ACTIVE MATERIAL RELEASED IN LIQUID EFFLUENTS TO UNRESTRICTED AREAS (SEE FIGURE 5.1.3-1)

SHALL BE LIMITED TO THE CONCENTRATIONS SPECIFIED IN 10 CFR PART 20, APPENDII B. TABLE II, COLUMN 2 FOR RADIONUCLIDES OTHER THAN DISSOLVED OR ENTRAINED NOBLE GASES. FOR DISSOLVED OR ENTRAINED NOBLE GASES.

THE CONCENTRATION SHALL BE LIMITED TO THE CONCENTRATIONS SPECIFIED IN TABLE 3'.11.1.1-1.* .

1 Liquid batch releases are controlled individually and each batch release is authorized based upon sample analysis and the existing dilution flow in the discharge line. The methods for sampling and analysis of each batch prior to release are g;ven in the applicable  ;

plant Procedures. A release rate limit is calculated for each batch based upon analysis, dilution flow and all procedural conditions being met before it is authorized for release. The liquid radvaste

~

effluent stream entering the discharge line is monitored and will automatically be terminated if the pre-selected monitor setpoint is exceeded as described in Section 2.1.

Additional monthly and quarterly analyses shall be performed in accordance with Table 4.11.1.1.1-1 of the SSES Technical Specifica- l tions. .

A discursion of the metho6 to be used in determining the fraction of the 10 CFR 20 annual concentration limits represented by each b' arch release is given in Section A.2.1 of Appendix A. Also, summation of these fractions from a series of batch releases within given time periods is described. *

• Table 3.11.1.1-1 contains th'e following Maxinum Permissible Concen- l trations of Dissolved or Entrained Noble Gases Released From the Site to Unrestricted Areas in Liquid Waste:

OCT 251983 9

. - .. - . - = -_ .- .. .

Nuclide MPC (UCi/ml)  !

Kr-85m 2E-4 Kr-85 SE-4 -

Kr-87 4E-5 Kr-88 9E-5 Ar-41 '

7E-5 Xe-133m SE-4 '

, Xe-133 6E-4 .

Xe-135m 2E-c Xe-135 2E-4 Computed from Equation 20 of ICRP2 (1959), adjusted for infinite cloud submersion in whter, end R = 0.01 rem /veek, o y = 1.0 gm/cm3 and PyTP = 1.0. ,

OCT 251983 .

- is -

f where:

Kg =

the whcle body dose factor due to gamma emissions foreachidentifiej)noblegasradionuclide(i)

(arem/yr per VCi/m from Table 2 Q'* =

the release rate of radionuclide (i) from vent (v) (;:Ci/sec).

(X/Q),= the highest calculated annual average relative concentration for any area at or beyond the site boundary in an un:estrieged area from vent reltese point (v)-(sec/m ) such as from Tab.e 3.

D wb

=

the annual wh le body dose (mrem /yr).

L =

the skin dose factor due to the beca emissions for each per (mram/yr identifieg)

UCi/m noble from gas Tableradionuclide

2. (1)

Mg =

the air dose factor'due to gamma emissions for each (mrad identified nog)lefrom

/yr per uC1/m gas Table radionuclide (1) 2 (conversion constant of 1.1 converts air dose-mrad to skin dos e-mram) .

D, =

the annual skin dose (mrem /yr).

Sample calculations for determining whole body and skin doses from noble gas radionuclides released from the SSES are given in Section A.2.2.1 of Appendix A.

4.2 RADIONUCLIDES OTHER THAN NOBLE GASES

, The methods for sampling and analysis of continuous ventilation releases for radioiodines, radioactive particulates, and other radionuclides except noble gases are given in the. applicable plant Procedures. Additional monthly and quarterly analyses shall be performed in accordance with Table.4.11,2.1.2-1 of the l SSES Technical Specifications. The dose rate in unrestricted areas due to radioactive materials released in gaseous' effluents nay OCT 25 583

( .

Cg = the average concentration of radionuclide (1) in  ;

undiluted liquid effluent during eine period, at, for -

any liquid. effluent batch release (uci/ml) .

F =

the discharge line dilution factor.for C gddring any l liquid effluent batch release. Defined as the tr.tio of the maximum unailuted liquid radvaste effluent line flow during release to the average flow from.the plant

~

discharge line to unrestricted rece.iving waters.

i Ag =

the composite dose parameter for the total body or any [

organ (r) for each identified principal gamma and bata emitter (i) (mrem /hr per pC1/ml) (see Equation 11, Table 5).

Ag =

K, (U,/D,+ Uf BF1 ) DFgT (11) where:.

k'= conversion factor of 1.1 x 1,,5 = (100 oci/ucO l10 3ml/kg) 8760 hr/yr

. U

=

a receptor person's water consumption by age group from Regulatory Guide 1.109 Table E-5. '

D

=

the dilution factor from the near field area of the release point to potable water intake. (The nearest potable water intake is located at Danville; dilutian factor is 321*.)

U f

a receptor person's fish consumption by age group from

• Regulatory Guide 1.109,. Table E-5.

i BF g =

the bioaccumulation factor for nuclide (1) in fish (pCi/kg per pCi/1) from Regulatory Guide 1.109 Table A-1.

DF =

' the dose conversien factor for nuclide (i) in a receptor person for pre-selected organ (r) (mrem /pC1) frca Regvlatory.Graide 1.109, Tables E-11, E-12, E-13, and E-14 -

The projected quarterly dose contribution from batch releases for which radionuclide concentratl.ons are determined by periodic compos-

, ite sample analysis, as stated in Table-4.ll.l.l.1-1 of the SSES Technical Spec'ification may be approxir.ated by assuming an' average concentration based on the prev'ious monthly or quarterly co=posite analysis. ,

. OCT 251983

J TABI.E 7 OPERATIONAL RADIOLOGICAL ENVIRONHENTAL HONITORING PROGRAM .

Page 1 of 3 l

Exposure Pathways Number of Samples Samplius and Type and Frequency and/ur Sample and I.ocationed Collection Frequency ,

of Analyala Airloorne .

Rcdiolodine and IIS2 (0.43 mi SW - Colomb llouse) Continual sempler operation Radiciodine Canister:

, Porticulates 981 (1.28 mi S - Transmisalon Line) with sample collection weekly.** analyze weekly for I-131 SS4 (0.76 mi E - W of Bio Consult) 12El (4.68 mi WSW- Berwick llospital) -

701 (13.51 mi SE - PP&L llazleton Particulate Samplers Chemical I.ab)* . . Analyze for gross beta j,

• radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> j' * -

following filter change.

Perform gamma isotopic analysis on composite sample (by location)

- quarterly. l Direct Radiation IS2 Security Fence - 0.24 mi X Quarterly Gamma Doses Quarterly.

ID2 Hocanaqua Substation - 3.97 mL H - .

2S3 Security Fence - 0.22 mi NNE 2B3 1.uzerne Outerwaar - 1.31 mi NNE 2F1 St. Adalberta cemetery - 5.88 mi NNE .

3S4 Security Fence - 0.30 mi HE

• 3D1 Pond 11111 - 3.88 m1 HE 3F1 Valania Resident (Nanticoke) -

9.10 mt HE -

l ca 3G3 Wilkes-Barre-Ilorton St. Substation -

15.80 ml HE l 4

El '

l 33 4S3 Security Fence - 0;23 mi ENE ~~ l j cn 4FI Pole (#) 46422 N35-197 - 4.75 mi ENE j gg 4C1 Hountain' Top,- Industrial Park -

g3 13.91 mi ENE

{ $S7 Security Fence - 0.22 mi E 5E2 Bloss Farm - 4.51 mi E 6S4 Security Fence - 0.18 mi Edu ,

6A3 State Police - 0.55 mi ESE 9

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TABI.E 7 (Continued) Page 2 of 3

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Exposure Pathways Number of Samples Sampling and Type ,and Frequency and/or Sample and E.ocations Collection Frequency of Analysis 6El St. James Churcl. - 4.74 mi ESE 7S3 Security Fence - 0.20 mi SE . , -

7El liarvood Transmission Line Pole A2 -

4.22 mi SE '

7C1 llazleton Chedical Lab - 13.51 mi SE" j 8S2 Security Fence - 0.22 mi SSE

• l 882 1.aMall Residence - 1.40 mi SSE .

. 8D2 Howry. Residence - 3.95 mi SSE 9SI Security Fer.ca - 0.26 mi S 9DI Smith Farm - 3.64 mi S 10S1 Security Fence - 0.43 mi SSW .

10D2 Rees Ryman Residence - 3.00 mi SSW IIS3 Security' Fence - 0.34 mi SW

, llEl Jaccbsen - 4.74 mi SW - .

C ,

.12S5 Security Fence - 0.36 mi WSW-8 12El Berwick Ilospital - 4.68 mg WSW ,

1201 Bloomsburg - 14.57 mi WSW 13S2 Security Fence - 0.38 mi W 13E4 Kessler Farm .4.10 mi W 14SS Security Fence - 0.47 mi WNW 14El Knouse Farm - 4.11 mL UNW ..

15S3 Security Fence - 0.34 mi NW 15F1 Zawatski Farm - 5.37 mi HW 16S! Security Fence - 0.29 mi NHW ,

16F1 Ilidlay I:esidence (lluntington Hills) - -

7.81 mi NNW Waterhorne Jurface 5S8lutakearea((upstream) Crah sample over monthly '

' Comma isotopic analyola 6S5 outfall area (downstream) period monthly. Composite 6S6 river water intake line Monthly compoalta tritisen analyals c3 6S7 cooling tower blowdown discharge Monthly composite quarterly.

l

,line c}

h(Drinking  !?!!2 Danville Water Co. Honthly composite - Cross beta and gamsna

_. (Approximately 30 miles downstream) isotopic analyses monthly.

U3 Comp'osite for tritium

'" analysis quarterly.

. ~.

TABLE 7 (Continued)- .

Page 3 of 3 Exposure Pathways Number of Samples Sampling s'nd Type and Frequency and/or Sample and Locations Collection Frequency of Analysis Ssdiment from 78 Bell Bend - 1.2 mi SE Semiannually Camma isotopic analysis )

Shoreline , ,

semiannually.

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Hilka** 12B2 Shultz Farm - 1.69 mi. WSW Semi-monthly when animals Camma isotopic an'd 1-131 13E3 Dent Farm - 4.9 mi. W are on pasture monthly analysis of each sample. '

$El Bloss Farm - 4.4 mi. E otherwise 1001 Davis Farm - 14 mi. SSW* ,

i f Fish and Outfall area Sample in season. Camma isotopic on Invertebrates 2H Falla. Pa. Dues.pleofeacgofthe edible portions. l (Approximately 30 ,m1 1;HE) following species :

1. Walleye

2. Catfish 5 Food Products l'251 Kinner:-Farm - 1.15 WSW At time of harvest Comma isotopic.on

• vegetable ,

edible portions. -

llD1 Zehner Farm - 4.3 mi SW vegetable 702 IIeller's Farm - 1.5 mi SE fruit 2H1 Yalick's Produce - 21 mi NNE" -

vegetable .

aThe location of samples and equipment were designed using the guidance in the Branch Technical Position to NRC Reg.

Guide 4.8. Rev. I Nov. 1979. Reg. Cuide 4.8 1975 and ORP/SID 72-2 Environmental Radioactivity' Surveillance Guide..

Therefore, the airborne sampler locations were based upon X/Q and/or D/Q. ,

aAA dust loading study (RHS-TR-81-01) concluded that the assumption of I for the' transmission correction factor for grosa beta analysis of air particula'te sapples is valid. Air particulate samples need siot be weighed to determine a transmission correction factor, ma*If a milk sample is unavailable for more than two sampling periods from one or more of the locations, a vegetation sample shall be substituted until a suitable milk location is evaluated. Such an occurrence will be docunented in the !!EMP annual report.

Control sample locatio'n.

H. ** Temporary locations until compoultor is installed in intake and discharge then lines; frequency changes to to composite sample collected over one-month period and location changes to 6S6 intake line 6S7 discharge line.

" The upstream sample will.be taken in the lotske line and which is beyond significant influence of the discharges.

ay, The downstream sample will be taken in the discharge line.

• • Other species in the same family could be sampled instead of the stated species if deemed desirab?e by the l

• , biological consultanta.

Ther: is no river water intake c.t Derwick for airinking water. See Suaquehanna SES-ER-01, Appendix C. page NAD-3.1. l The entculated dose for D.,nville to the infant thyroid was 0.I3 mrem per year. Therefore, t here la no need to i _....-n, ,, . . ...,_,,,,,e we0sx0 anx0 mtr(facco _am _0-0 3 D asqa 1 es i s.

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-"- OCT 25 !ss

a APPENDIX A SAMPLE CALCULATIONS OF 00CM PARAMETERS A.1 SETPOINTS A.l.1 Licuid Effluent Monitors -

For an unidentified mixture with an assumed MPC of IE-7 pC1/ml, an actual activity of IE-5 uC1/ml, and a blowdown flow setpcint.of 5000 gpm, the setpoint concentration, e, can be determined from e = X-(A). If X = 3, then'the actual setpoint concentration is:

e

• X- (A) = 3-(1E-5) e = 3E-5 UCi/ml The setpoint value for the liquid effluent monitors is then determined by Equation 3 in the ODCM. For the above release conditions, the setpoint value, assuming a typical calibration factor' of 1.3 x 10- UCi/ml per epm, would be: ,

Setpoint epm =I 'e

+ Background (epm)

(Cal.Factorj Setpoint cpm = 3E-5

+ Background

-8 1.3 x 10 ,

~

Setpoint epm = 2.3E3 + Background The LRW dischdrge flow setpoint is then determined as follows:

~

F + f = Y*(A) f MPC where Y is made equal to 10.

OCT 251983 A-1

^

Og F

- ~

i .

/ 5000 + f '- 10-(1E-5)

( f / LE-7 ,

f = 5 gpm 1

For an identified mixture with an ac ual'MPC of 7.22E-7 uCi/ml and the .same activity, blowdown flow and X and Y values as above, the LRW discharge monitor setpoint value and LRW discharge flow setpoint become:

Setpoint :oncentration (c) = 3E-5 uCi/ml Setpoint value =.2.3E3 cpm + Background LRW discharge flow setpoint (f) = 36 gpm A.1.2 ,

Gaseous Effluent Monitors To determine the total release rate limit (Q'gy) for all vents in the SSES, the highest calculated annual average relative concentration (X/Q), for any sector offrite must be determined. For the SSES site, the critical downwind sector is the West. sector with an annual dispersion factor of 2.6 x 10-5 ,,,j,3 (f rom Table 3) . Equation 4 in the ODCM is used to determine the release rate limit for the

v. tole body dose. If the principal noble gas radionuclide

, , released is Xenon-133, the whole body dose factor (K,) from -

Table 2 would be 2.94 x 102 mrem /yr per UC1/m 3

. Substitut-ing these values into Equation 4, the total release rate limit '(Q ' y) for the whole body dose in Xenon-133 equiva-lent from all vent,rileases at the SSES would be 6.5 r 10 uCi/see:

OCT 251993 e

e A-2

'O

- s .

. PR&j. Pennsylvania Power & Light Company Two North Ninth Street

• Allentown, PA 18101 + 21517705151 Bruce D. Kenyon V!ce President-Nuclear Ope?stions 215/770-7502 JAN 12 B84 Director, Data Automation &

Managerrent Information Division Attention: Mr. M. R. Beah!

Management Information Branch Office of Fesource Management U.S. Nuclear Regulatory Cm mission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION MCNIHLY OPERATING REPORT - DEQ NBER 1983

' ER 100450 FILE 841 PIA-2031 Docket No. 50-387

Dear Mr. Beebe:

The December 1983 nonthly operating report for Susquehanna SES Unit 1 is attached.

Very truly yours, 1

TW

. D. Ken W

Vice Presid Muclear Operations Attachment cc: Dr. Thcmas E. Murley INPO Pecords Center Regional Mministrator-Region I Suite 1500 U.S. Nuclear Pegulatory Cm mission 1100 Circle 75 Parkway 631 Park Avenue Atlanta, Georgia 30339 Kir.g of Prussia, PA 19406 Director Mr. Thmas E. Pollog Office of Inspection and Enforcenent Department cf Environmental U.S.' Nuclear Regulatory Ccunission Resources Washington, D.C. 20555 Bureau of Radiation Protection Attn: Document Control Desk (12 copies) P.O. Box 2063 Harrisburg, PA 17120 '

Mr. G. Rhoads - NRC-Mr. R. Perch - NBC

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