PLA-2330, Monthly Operating Repts for Sept 1984

Monthly Operating Repts for Sept 1984

ML20108B166
Person / Time
Site:	Susquehanna
Issue date:	09/30/1984
From:	Kenyon B, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-2330, NUDOCS 8411150333
Download: ML20108B166 (25)

Text

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' N 4@ AVERAGE DAILY UNIT POWER LEVEL j E 00 . . . . '

E DOCKET NO. 50-387 k

m a" One UNIT DATE October 5, 1984 L , A. Kuczynski RIC Si COMPLEED BY TELEPHONE (717)S42-3759 MO N September, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe-Net) 1033 1025 37 2 1009 gg 1010 3 1023 39 1038 4 1032 20 1031 5 1039 21 1022 6 1042 614 22 7 1043 23 734 s 1035 24 963 9 902 1011 25 ..

10 1033 26 1030 11 1028 1043 27 12 941 1044 23 13 1029 714 29 34 1028 760 30 15 712 -

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INSTRUCTIONS 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.

(9/77) 8411150333 840930 PDR ADOCK 05000387 R PDR .

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E L"L-. Ws J OPERATING DATA REPORT  ;

O DOCKET NO. 50-387 4 DATE October 5, 1984 O L. A. Kuczynski NIC SY COMPLETED BY TELEPHONE (717)S42-3759 OPERATING STATUS Unit 1 Susquehanna Steam Elect ric Station Notes

1. Unit Name:

2. Reporting Period: September, 1984

3. Licensed Thermal Power (MWt): 3.293

4. Nameplate Rating (Gross MWe):

1,152

5. Design Electrical Rating (Net MWe): 1,065 1,068

6. Maximum Dependable Capacity (Gross MWe):

7. Maximum Dependable Capacity (Net MWe): 1.032

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 Reporting Period 720 6,575 1 ,544

12. Number Of Hours Reactor Was Critical 720 4,613 5 8,458.8

13. Reactor Reserve Shutdown Hours 0 249.1 405.8

14. Hours Generator On.Line 720 4,488.9 8,257.2

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2,206.860 13.674.000 24.935.661

17. Gross Electrical Energy Generated (MWH) 716,120 4.453.730 8.120.280

18. Net Electrical Energy Generated (MWH) 689.988 4,288,825 7,825,198

19. Unit Service Factor 100 68.3 71.5 ~

20. Unit Availability Factor 100 68.3 71.5

21. Unit Capacity Factor (Using MDC Net) 92.9 63.2 65.7

22. Unit Capacity Factor (Using DER Net) 90 61.2 63.6

23. Unit Forced Outage Rate 0 15.4 13.8

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

Refuelinq Outage: February 9, 1985: 15 weeks.

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

26. Units in Test Status tPrior to Commercial Operation): Forecast Achiesed j INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION _

(4/77 )

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• UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 5_0-387 .

f UNIT NAME One

$D Peal f

o DATE October 5. 1984 e COMPLETED BY LA. Kuczynski IC REPORT MONTif September, 1984 TELEPHONE (717)S42-3759 w.

_ E E jg 3jj j E3 Licensee ,E-t, En, Cause & Corrective

. Date g 3g jg5 Event u? E'E Action to H

fE 5 jgg Report a mO gO g Prevent Recurrence c5 11 840915 S 0 H 5 NA RC FUELXX Scheduled power reduction to optimize fuel use until refueling outage.

12 840922 S 0 H 5 NA RC FUELXX Scheduled power reduction to optimize fuel use until refueling outage.

Replacement of reactor recirculation pump motor generator set brushes w:,s al so accompl i shed.

13 840929 5 0 H 5 NA RC FUELXX Scheduled power reduction to optimize fuc: use until refueling outage.

1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual 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-Regulatory Restriction 4-Continuation 0161)

E-Operator Training & Ucense Examination from previous month F-Administrative 5-Reduction 5 G-Operational Error (Explain) Exhibii 1 - Same Source (9/77)

I1-01her (Explain) 9-Other

t UNIT 1 b.

SUSQUEHANNA STEAM ELECTRIC STATION Docket Number 50-387 Date October 5, 1984 Completed by L. A. Kuczynski Telephone (717)S42-3759 Challenges to Main Steam Safety Relief Valves None Changes to the Offslte Dose Calculation Manual See Attachment.

Major Changes to Radioactive Waste Treatment Systems None.

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ATTACHMENT TO UNIT ONE September,1984, Monthly Operating- Report

_ Changes to the Offsite Dose Calculation Manual These revised pages were made effective July 9,1984, upon signature by the Manager-Nuclear Support.

Changes' have been denoted by revision bars In the right margin.

The change,s ere made to incorporate a new setpoint calculation method-ology for vent monitors, based e,.. actual (or expected) effluent isotope mixes.

s y4 AVERAGE DAILY UNIT POWER LEVEL D }

Y -

CO .... I 1 DOCKET NO. 50-388 L' N' UNIT Two Ip DATE October 5, 1984 L.A. Kuczynski R[C SY COMPLETED BY TELEPHONE (717)542-3759 m September, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 714 37 2 0 729 is 3 0 19 689 _

4 189 20 564 _

5 371 0 21 6 399 129 22 7 410 502 23 3 50 24 583 9 321 25 705 to 630 26 771 11 733 27 987-12 720 28 1002

!3 571 1014 29 14 580 39 30 15 721 3, 16 710 INSTRUCTIONS 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.

(9/77)

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3 LA+ RZ J ) OPERATING DATA REPORT O DOCKET NO. 50-388 4 ig DATE October 5, 1984 OpNIC SY COMPLETED BY L . A. Kuczynski .

TELEPHONE (717)S42-3759 OPERATING STATUS Unit 2 Susquehanna Steam Elect ric Station N05

1. Unit Name:

2. Reporting Period: September. 1984

3. Licensed Thermal Power (MWt): 3.293

4. Nameplate Rating (Gross MWe): 1.152

5. Design Electrical Rating (Net MWe): 1.065

6. Maximum Dependable Capacity (Gross MWe):

• To be determined.

7. Maximum Dependable Capacity (Net MWe):

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 Reporting Per:od 720 2.147 2,147

12. Number Of Hours Reactor Was Critical 612.8 1.653.4 1.653.4_

13. Reactor Reserve Shutdown Hours 152.6 495 495

14. Hours Generator On-Line _ 567.4 1,333.7 1,333 7

15. Unit Reserve Shutdown Hours 0 142.4 i42.4

16. Gross Thermal Energy Generated (MWH) 1.182.556 2.127.542 2.127 si42

17. Gross Electrical Energy Generated (MWH) 374,820 629,070 629.070

18. Net Electrical Energy Generated (MWH) 356.012 587,463 587,463

19. Unit Service Factor NA NA NA

20. Unit Availability Factor NA NA NA

21. Unit Capacity Factor (Using MDC Net) NA NA NA NA NA NA

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate NA NA NA

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

Pre-Commercio1 October 27, 1984, 10 weel<s.

25. If Shut Down At End Of Report Period, Estimated Date of Startup: October 2, 1984

26. Units In Test Status (Prior to Commercial Operat on): Forecast Achieved INITIAL CRITICALITY 05/09/84 05/08/84 INITIAL ELECTRICITY 06/28/84 07/03/84 COMMERCIAL OPER ATION 12/31/84 (4/77)

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DOCKET NO. 50-388 ,,

UNIT SHUIDOWNS AND POWER REDUCTIONS -

PPat UNIT NAME Two

$@ o DATE October 5, 1984 d COMPLETED BY L.A. Kuczynski_

Ric 5 REPORT MONT11 September. 1984 TELEPHONE (717)S42-3759

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, jE 3 y E~ Licensee E t, E*L Cause & Corrective No. Date g H

3g j= 5 i jg5 j ;g g Event Report a g'2 mV g

h V Action to Prevent Recurrer.ce d

• 9 840828 F 72.2 A 4 84-017 HA VALVEX Reactor scram following turbine trip on moisture separator drain tank high level . Cause for high level was mal-functioning drain valve on piping f rom high pressure turbine exhaust to moisture sepa rator.

10 840908 F 20.4 A 3 84-018 HA INSTRU Reactor scrammed as a resul t of a tur-bine control valve fast closure signal (See attached page) 11 840913 F 0 B 5 N/A CB INSTRU Power reduction for reactor reci rcu-lation system troubleshooting.

12 840920 S 37.3 B 3 N/A ZZ ZZZZZZ Reactor scram occurred as part of l schedul ed startup testing .-

13 840930 F 22.7 H 3 84-021 ** ** Reactor scram due to turbine trip on l

l high moisture separator drain. tank

• Renun bered per NRC dir ection. (See attached page) i ... Unde t ermined at t bis t ime.

! I 2 3 4 F: Forced Reason: Method: Exhibit G. Instructions

! S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data

! B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C. Refueling 3. Automatic Scram. Event Report (LER) File (NUREG-l D-Regulatory Restriction 0161)

E-Operator Training & License Examination 4-pontinuationrom previous month F-Administrative 5-Reduction 5 G-Operational Error (Explain) 9-Other Exhibit I - Same Source (9/77) Il-Other (Explain) ,

L

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.,f G .v UNIT 2 SHUTDOWNS AND' POWER REDUCTIONS (continued):

No. 10 i generated f rom a false power-load unbalance signal during performance of a surveillance. The unit responded per design throughout the transient. -

The pressure transmitter which provided the - false input was recalibrated and a procedure change was made to alert operations personnel of impending turbine trip -if the circumstances develop again. The procedure also provides action to be taken to prevent the turbine trip.-

No. 13 level. Evaluation of cause(s) and action (s) to prevent recurrence still being determined.

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-SUSQUEHANNA STEAM ELECTRIC STATION Docket-Number 50-388 Date October 5,1984 Completed by L.A. Kuczynski Telephone (717)S42-3759 .,

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Challenges to Main Steam Safety Relief Valves None.

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PENNSYLVANIA POWER & LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE. DOSE CALCULATION MANUAL i

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1 Prepared By .

L h Date d/ .T Y Reviewed By Date 2 8 i

f PORC Review Required Yes ( ) No (d Date 1 - , 'l Approved By [ '

4 r$ Date 7 k k '

. Managiir-Nuc1har / Support 4

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TABLE OF CONTENT $

, Pm Revision Date

1.0 INTRODUCTION

.................................. 1 7/12/82 2 5/11/82 3 4/27/83 4 5/11/82 5 5/11/82 6 4/27/83 2.0 SETP0INTS..................................... 7 4/27/83 2.1 LIQUID EFFLUENT MONITORS.................. 7 4/27/83 8 10/25/83 8b 1/20/84 2.2 GA$E005 EFFLUENT MONITORS................. 9 1/20/84 10 7/09/84 11 7/09/84 12 7/09/84 13 7/09/84 3.0 LIQUID EFFLUENT CONCENTRATION MEASUREMENTS.... 14 10/25/83 15 10/25/83 4.0 GASEOUS EFFLUENT DOSE RATE ITASURDIENTS. . . . . . . 16 4/27/83 4.1 NOBLE CASES............................... 16 4/27/83 4.2 RADIONUCLIDES OTHER THAN NOBLE CASES. . . . . . 17 10/25/83 X 17A 7/09/84 18 4/27/83 19 4/27/83 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 CAS ES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 4/27/83 6.2 RADIONUCLIDES OTHER THAN NOBLE GASES...... 26 4/27/83 27 4/27/83

. 28 5/11/82 29 5/11/82 7.0 TOTAL D0SE.................................... 30 4/27/83 31 5/11/62 8.0 OPERABILITY OF WASTE TREATEMENT SYSTEMS....... 32 4/27/83

. 8.1 LIQUID WASTE TREATEMENT................... 32 4/27/83

8. 2 GASEOUS WASTE TREATMENT. . . . . . . . . . . . . . . . . . . 32 4/27/83 33 5/11/82 8.3 SOLID WASTE TREATMENT..................... 34 4/27/83 35 5/14/84 l 36 5/11/82 37 5/11/82 38 5/11/82 0

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9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. 39 7/12/82 9 .1 DEFIN ITIONS . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 39 7/12/82 9.2 MONITORING PROGRAM........................ 39a 5/14/84 9.3 CENSUS PR0 GRAM............................ 40 5/14/84 40a 7/12/82 41 10/25/83 42 10/25/83 43 , 5/14/84 44 5/11/82 45 5/14/84 46 5/11/82 47 5/11/82 48 4/27/83 APPENDIX A - SAMPLE CALCULATIONS OF ODCM PARAMETERS........................... A-1 10/25/83 A-2 7/09/84 A-3 7/09/84 A-4 7/09/84 A-4A 7/09/84

. A-4B 7/09/84 A-4C 7/09/84 A-5 5/11/82 A-6 5/11/82 s A-7 5/11/82 A-8 5/11/82 .

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 APPENDIX B - REPORTING FIQUIREMENTS . . . . . . . . . . . . . . . B-1 5/11/82 B-2 5/11/82 B-3 5/11/82 B-4 5/11/82 APPENDIX 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

. D-2 4/27/83 D-3 4/27/83 4

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C0h"ROL _ED LIST OF TABLIS M Revision Date Table 1 Radiological Effluent Objectives and Standards... . 6 4/27/83 Table 2 Dose Factors for Noble Gases and Daughters........ 17A. 7/09/84 -

Table 3 Annual Average Relative _ Concentrations and Deposition Rates.................................. 18 5/11/82 Table 4 Dose Parameters for Radionuclides Other Than Noble Cases....................................... 20 4/27/83 Table 5 Liquid' Dose Parameters for Adults................. 23 5/11/82 Table 6 Maximum Pathway Dose Factors Due to Radionuclides Other Than Noble Gases.............. 26 5/11/82 Table 7 Operational Radiological Environmental Monitoring Program................................ 41 10/25/83 42 10/25/83 43 5/12/84 Os Tcble 8 Detection capabilitie: f:r T. viron= ental Sample Analysis................................... 46 5/11/82 Table B-1 Radiological Environmental Monitoring Program Annual Summary.................................... B-3 5/11/82 Table B-2 Reporting Levels for Nonroutino Operating Reports...........................................

B-4 5/11/82 e

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1. All exposure pathways of significance at the critical.

. receptor locations;

2. Dose contributions to critical receptors from multiple release points; and

3. Dose contributions from major radioisotopes expected to be present in gaseous effluents.

The general methodology for establishing plant ventilation gaseous' effluent monitor setpoints is based upon vent release rates derived from site-specific meteorological dispersion j conditions, vent flow rates, and measured or expected radioiso-topic mixtures in the gaseous affluents. The vent release rates can then be converted to vent concentrations for input as set-points for the applicable detectors. Since the vent monitors

() are programmed to calculate concentrations of, iodine-131 and particulate being released based on the rate of accumulation of i activity on the filters, setpoints can be established for the iodine and particulate channels.

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- . - - , , , y-,-- y _ , - - - - - , , - - -, , - - , - --~r-, ,,g--n,n- -ume <nww ,,,--,w a, m n,- ,-a-wr,,,-p.,g m-- ww.7--w, mew,--ge-

y.~ The following method is used for calculating vent monitor high radiation ,

( alarm setpoints:

1. An isotopic mixture is selected for the detector in question, if applicable. Noble gas and particulate detector setpoints are based-on actual isotopic mixtures obtained from vent sample analysis or the

• FSAR/FES expected. release mixtures if actual samples do not contain sufficient detectable activity to accurately ertimate the mixtures.

The assumed isotopic mixtures are periodically reviewed to verify that they remain representative of plant effluents.

f

2. The selected noble gas or particulate mixture is used in the CASPAR l

program run to calculate the associated doses. The total source term (total curies used for the calculation) does not matter as long as the proper nuclides are present in the relative proportions indicated in sample analysis data or FSAR/FES tsbles.

For the iodine-131 setpoint, any release total for I-131 can be

) entered. The highest calculated annual average relative concentra-j tions (x/Qs) at the site boundary are used for these GASPAR calcula-l tions.

3. The follovir.g ratio concept is used to calculate a release rate limit for the assumed mixture-(or I-131):

{

Calculated Dose (mres) = Dose Rate Limit (arem/yr) 1 j Total CASPAR Source Ters (C1) Limiting Release Rate (Ci/yr) l The limiting release rate of the assumed mixture (or I-131) can therefore be calculated.:

Limiting Release (Ci/yr) =

(Total CASPAR Source Term, Ci) (Dose Rate Limit, mrem /yr)

(Calculated Dose, mram) 10 * " "

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@ For the noble gas setpoint,.the calculated whole body and skin dose b

v rates via the plume pathway are subject to the 10CFR20-derived limits of 500 and 3000 area /yr. respectively. The'whole body dose rate limit is usually most restrictive. For particulates and for iodine-131, the maximum calculated organ dose via the inhalation pathway is subject to the limit of 1500 area /yr.

4. The limiting release rates are converted to limiting vent concentra-tions using high limit vent flow rates.

Limiting Vent Concentration, uCi/cc =

.s (Limiting Release Race, C1/yr) (10E6uci/Ci)

(5.26ES min /yr)- (Vent High Limit Flow Rate, cc/ min)

Sample calculations of liquid and gaseous effluent monitor setpoints are presented in Appendix A. *

• Vent flow rates and sample flow rates are monitored and recorded for each of the five SSES release points. The measured flow rates are used to calculate vent concentrations and release rates. Flow

( channel setpoints are set at 10"'and 90% of the calibrated sensor ranges to provide indication of possibly abnormal flow races.

SPECIFICATION 3.11.2.6 - THE CONCENTRATION OF HYDROGEN OR OXYCEN IN THE MAIN CONDENSER OFFCAS TREATMENT SYSTEM SHALL BE LIMITED TO LESS THAN OR EQUAL TO 4% BY VOLUME.

Hydrogen reccabiners are used at SSES to maintain the relative concentration of components of potertially explosive gas mixtures

, , outside the explosive envelope. The main condenser offgas treatment ,

system explosive gas monitoring system (offgas hydrogen analyzers) have setpoints of 1% hydrogen to alarm and 2% hydrogen to isolate.

JUL 091984 (C . -

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TABt.E 2 ,

DOSE FACTORS FOR NOBl.E CASES ABS DAbCHTERS* *

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- 14: ale Body Camma Air Beta Air Dose Factor Skin Dose Factor Dose F=-tor Dose Factor E L M N Radiomuclide (aremfyrkrpC1/m - (aree/yrhrpC1/m (erad/yr M r pCi/m ) (arad/yr Mr pC1/m )

Kr-C3m 7.56E-02 1.93E+01 2.SSE+02 ,-

Kr-85m 1.17E*03 1.46Ee03 1.23E*03 1.97Ed3 Kr-85 1.61E*01 1.34E+03 1.72E+01 1.95E+03 9.73E*03 6.17E+C5  ;.03E+04 Kr-87 5.92E*03 Kr-48 1.47E* 04 2.37E+03 1.52E+04 2.93E+03 Kr-89 1.66E*04 1.01E*04 1.73E+04 -

1.06E+04 i

l 0 Kr-90 1.56E*04 7.29E+03 1.63E+04 7.83E+03

> Xe-131m 9. ISE* 01 4.76E+02 1.56E*02 1.11E+03 Xe-333m 2.51E*02 9.94E+02 3.27E+02 1.48E+03 Ie-133 2.94E+02 3.06E*02 3.53E+02 1.05E+03 1e-135m 3.12E*03 7.11E+02 3.36E+03 7.39E+02 Ie-135 1.81E+03 1.86E*03 1.92E+03 2.46E+03 Xe-137 1.42E*03 1.22E+04 1.51E+03 1.27E+04 Ic-138 8.83E*03 4.13E+03 9.21E+03 4.75E+03 Ar-41 8.84E+03 2.69E+03 9.30E+03 3.2SE+03 I

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• The listed dose factors are for radiomuclides that may be detected in gaseous effluents and derived Ir:m Table 5-1 in Beg. Cetde 1.109. ,

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.k.:. l ' 5000'+ f = 10 (IE-5)

~ (g .f IE-7 f = 5 spa For an identified mixture with an actual MPC of 7.22E-7 pCi/ml and the same activity, blowdown _ flow and X and_Y, values as above, the LRW discharge monitor setpoint value and LRW dis-charge-flow setpoint become:

4

'Satpoint concentration (c) = 3E-5 pCi/ml Satpoint value = 2.3E3 cpm + Background-LRW discharge flow setpoint (f) = 36 gpm 4- A.1.2 Gaseous Effluent Monitors A.1.2.1 Noble Gas Monitor To determine the release rate limit for noble gases, "t '

an isotopic mixture representative of plant effluents is selected. For example, the following mixture from

Table 4.4 of the SSES Final Environmental Statement (FES) can be used

.

Argon-41 25 Ci/yr per reactor Krypton-83m 4 Krypton-85m 1,700 Krypton-85 270 Krypton-87 . 32 Krypton-88 660 Xenon-131m 71 i 1

Xenon-133m 14 Xenon-133 12,500 Xenon-135m 220

Xenon-135 590 Xenon-138 290

, Total. 16,376 Ci/yr per reactor

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JUL 091984 A-2

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5 lg .

jX The above annual release quantities are entered into GASPAR with the following annual average dispersion estimates (

Reference:

1982 SSES Meteorology Report):

Relative Concentration 4.1E-5 sec/ms Decayed Relative Concentration 4.1E-5 sec/m 8 Decayed Depleted Relative Cencentration 3.8E-5 sec/m 8 2

Deposition Rate 4.2E-8 m This set of annual average meteorological parameters is the most conservative over the period 1973-1982.

The total body dose via the plume pathway which results is 18.3 mram. Equation 5 of the ODCM is then used to calculate the limiting release rate from each of the five plant release points:

l

. cy Limiting Release Rate =

(32,752 C1)

(500 mram/yr) = 8.95E4 C1/yr per vent (36.6 mrem) (5 vents)

This limiting release rate is then converted to limiting (setpoint) concentrations using Equation 6 of the ODCM and high limit vent flow rates.

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Sample High Limit Vent Flow Rates:

. Unit 1 Reactor Building Vent 4.75E9 cc/ min Unit 2 Reactor Building Vent 4.75E9 cc/ min Standby Gas Tt;eatment System Vent 5.04E8 cc/ min

, Unit 1 Turbine Building vent 8.63E9 cc/ min Unit 2 Turbine Building Vent 6.50E9 cc/ min 60 JUL 0 91984 A-3

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Limiting Vent Concentration =

(8.95E4'Ci/yr/ vent)

(1E6 uC1/C1) = 3.58E-5 uCi/cc for (5.26E5 min /yr) (4.75E9 cc/ min) Reactor Buildings 1&2

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Substituting the other vent flow rates into Equation 6 as above, the following noble gas high radiation set-point co.3centrations are calculated for the remaining vents:

Standby Gas Treatment System 3.37E-4 uC1/cc Unit 1 Turbine Building 1.97E-5 uCi/cc Unit 2 Turbine Building 2.62E-5 uCi/cc A.1.2.2 Iodine-131 Monitor

() When the FES expected annual release quantity for 1-131 (2.40E-1 curies) is entered into CASPAR with the dispersion estimates of A.1.2.1, the maximum calculated organ dose via the inhalation pathway is 4.88 mrem to the child thyroid. Using Equation 5 of the'0DCM, the limiting 1-131 release rate is calcu-laced as follows:

Limiting Release Rate = ,

(.24 C1) (1500 mrem /yr) = 1.48E1 Ci/yr/ vent (4.88 mrem) (5 vents)

Using Equation 6 of the ODCM, the limiting (setpoint) l-131 concentrations can be calculated for each of

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Limiting Vent Concentration =

-(14.8 Ci/yr/ vent) (1E6 uCi/C1) = 5.92E-9 uCi/cc for -

(5.26E5 min /yr) (4.75E9 cc/ min) Reactor Buildings 1&2 Substituting the other vent flow rates into Equation 6 of the ODCM above, the high radiation setpoints for 4 the remaining plant vents are calculated to be the following:

Standby Gas Treatment System 5.58E-8 uCi/cc Unit 1 Turbine Building 3.26E-9 uci/cc Unit 2 Turbine Building 4.33E-9 uCi/cc A.1.2.3 Particulate Monitor

'(Q ,j Following are the SSES Final Environmental Statement (FES) expected annual release. quantities for particu-late radionuclides:

Cr-51 1.2E-4 Ci/yr per reactor Mn-54 3.6E-4 Fe-59 1.6E-4 3 Co-58 5.8E-5 Co-60 1.1E-3 Zn-65 5.5E-5 l Sr-89 1.8E-5 Sr-90 3.1E-6 1

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Cs-136 1.3E-3 Cs-137 2.1E-4 Ba-140 4.2E-5 Ce-141 2.9E-5 Total 3.6E-3 Ci/yr per. reactor When the above annual release quantities ara eutered into GASPAR with the annual average dispersion esti-mates of A.1.2.1, the maximum calculated organ dose via the inhalation pathway'is 1.33E-2 mrem to the teen lung. Using Equation 5 of the ODCM, the limit-ing release rate of particulates can be calculated:

Limiting Release Rate =

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(7.2E-3 Ci) (1500 mrem /yr) = 8.12E1 C1/yr/ vent (2.66E-2 mrem) (5 vents)

Using Equation 6 of the ODCM, the limiting (setpoint) particulate concentrations can be calculated for each of the five plant vents.

Limiting Vent Concentration =

(81.2 Ci/yr/ vent) (lE6 uCi/C1) = 3.25E-8 uCi/cc for (5.26E5 min /yr) (4.75E9 cc/ min) Reactor Buildings 1&2 When the vent flow rates for the remaining five plant .

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vents are substituted into Equation 6 as above, the following high radiation setpoint concentrations result.

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Standby Gas Treatment System 3.06E-7 uCi/cc

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Unit'l Turbine Building 1.79E-8 uCi/cc .

i Unit 2 Turbine Building 2.38E-8 uCi/cc W

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PPal. Pennsylvania Power & Light Company Two North Ninth Street

• Allentown, PA 18101 = 21517705151 Bruce D. Kenyon Vice President-Nucleat Operations 215/770-7502 OCT 091984 Director, Data Automation &

Management Information Division Attention: Mr.-M. R. Beebe Management Information Branch Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STE..d ELECTRIC STATION MONTHLY OPERATING REPORTS ER 100450 FILE 841 Docket Nos. 50-387/NPF-14 PLA-2330 50-388/NPF-22

Dear Mr. Beebe:

The September 1984 monthly operating reports for Susquehanna SES Units 1 and 2 are attached.

Very trul yours, 3

E N b A B. D. Kenyon Vice President-Nuclear Operations Attachment cc: Dr. Thomas E. Murley INPO Records Center Regional Administrator-Region I Suite 1500 U.S. Nuclear Regulatory Commission 1100 Circle 75 Parkway 631 Park Avenue Atlanta, Georgia 30339 King of Prussia, PA 19406 Director Mr. Thomas E. Pollog Office of Inspection and Enforcement Department of Environmental U.S. Nuclear Regulatory Commission Resources Washington, D.C. 20555 Bureau of Radiation Protection Attn: Document Control Desk (12 copies) P.O. Box 2063 Harrisburg, PA 17120 Mr. R. H. Jacobs - NRC Mr. R. L. Perch -~NRC I

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