PLA-2580, Monthly Operating Repts for Dec 1985

Monthly Operating Repts for Dec 1985

ML20210F944
Person / Time
Site:	Susquehanna
Issue date:	12/31/1985
From:	Keiser H, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-2580, NUDOCS 8604020312
Download: ML20210F944 (30)

Text

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"% UNIT One p g DATE _ January 8, 1986 f 4 L.A. Kuczynski RfC SY CoMPLEHD BY TELEPHONE (7171547-3759 MO N December, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (Mwe.iw 1

1,041 37 1,035 2 651 gg 1,044 3 0 39 1,045 .

4 0 20 1,044 5

149 21 864 6 639 22 1,015 7 855 23 _

1,043 _

8 979 24 1,041 9 1,044 25 1,045 10 1,043 26 1,045 11 1,039 27 1,045 32 1.042 23 1,045 13 1,043 1,044 29 14 1,044 30 1,046 15 1,041 1,044 33 16 1,037 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 rnegawatt.

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. w un .7 W _ S_1.~_ _ 3 L3-- Zi'. J OPERATING DATA REPORT O DOCKET NO. 50-387 DATE January 8, 1986 OpRfC i S [g COMPLETED BY L.A. Kuczynski TELEPHONE (717)S42-3759 OPERATING STATUS Unit 1 Susquehanna Steam Electric Station N"

1. Unit Name:

2. Reporting Period: December, 1985

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross 31We1:

1152

5. Design Electrical Rating (Net 31Wel: 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 MWel: None

10. Reasons For Restrictions. If Any: None This Month Yr..to Date Cumulaine i1. Hours in Reporting Period 744 8,760 22,513

12. Number Of Hours Reactor Was Critical 689 5,598.5 15,991.2

13. Reactor Reserve Shutdown Hours 55 239.2 710.6

14. Hours Generator On Line 678.4 5,471.9 .15,618.8

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2,131,678 16,958,337 47.587.325 699,870 5,508,462 15,498,992

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical EnerEy Generated (MWH) 673,147 5,264,168 14,844,730__.,

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19. Unit Service Factor 91.2 62.5 69.4

20. Unit Availability Factor 91.2 _

62.5 69.4 -

21. Unit Capacity Factor iUsing MDC Net) 87.7 58.2 63.9 I 22. Unit Capacity Factor (Using DER Net) 84.9 56.4 61.9 l

23. Unit Forced Outage Rate 8.8 5.6 11.2

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each n Refueling Outage; Februarv 15, 1986r 84 days.

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

26. Units In Test Status (Prior to Commercial Operation): Forecast Achiet ed l

INITIAL CRITICALITY INITIA L ELECTRICITY COMMERCIAL OPERATION l

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d DOCKET NO. 50-387

UNIT SHUTDOWNS AND POWER REDUC 110NS UNIT NAME One ..

$ DATE January 8, 1986 k @6 NIC C[ REPORT MONT11 Decernber,1985 COMPLETED BY TELEPHONE L.A. Kuczynski (717)542-3759 Page 1 of 3 m

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Prevent Recurrence c5 8 851202 P 65.6 A 3 85-034 EB RELAYX On December 2, 1985 at approximately 1504 a ' Sudden Pressure' relay assoc-iated with Emergency Safeguards System (ESS) Transfonner 111 misoperated.

This caused a trip of ESS Transformer 111 which normally supplies ESS buses 1C and 2C. The momentary power loss to the IC and 2C buses and the associated AC distribution panels caused the speed of all three feedwater pumps on each unit to lockup (fail constant) 'and caused a simultaneous runback and lock- '

up of the 'A reactor recirculation pumps. The speed of the 'A' reactor recirc ptmp on each unit decreased slightly before locking up, which caused reactor vessel water level to increase. Unit I scranried on high (continued)

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 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)

EOperator Training & Ucense Examination from previous month F-Administralise 5-Reduction i Goperational Error (Explain) E xhibit I - Same Source 19/77) llother (Explain) 9-0ther

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UNITSHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-387 k PP8L o

f UNIT NAME Om DATE January 8, 1986 k #4fC S Ig REPORT MONT11 Drusnber, 1985 COMPLETED BY L.A. Kuczynski TELEPHONE (717)542-3759 Page 2 of 3

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, 3E 3 yYE Licensee 5 t, g9, Cause & Corrective No. Dat e - g 3g ( ,g g 5 Event y E '8 Action to H

c3 E 5 j@g Report a mV fU Prevent Recurrence c5 65.6 8 851202 F A 3 85-034 EB RELAYX vessel water level. Unit 2 scrammed on low vessel water level when attempts to restore feedwater level control were unsuccessful.

An uninterruptable power supply to the feedwater control circuitry has been added to Unit 1 and Unit 2. This will enable the feedwater system to respond to vessel level transients during electrical system perturbations.

The relay (Qualitrol 910 Series Rapid Pressure Rise Relay) was partiallydis-assemblcd and inspected on site but a failure mechanism could not be ident-ified. The relay has been returnt<1 to the manufacturer for further analysis.

In the interim, the sudden pressure (continued)

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 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)

EOperator Training & License Examination from previous month F-Administratise 5 G-Operational Esrov (Explain) 5-Reduction Exhibis 1 - Same Source (9/77) li-Other (E xplain) 9-Other

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• UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-387 UNIT N AME One

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[ DATE Januarv 8, 1986

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1. @5# REPORT MONTH DhA 1985 COM.LETED BY L A Knmvnski TELEPHONE (717)542-3759 Page 3 of 3 l

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, jE 3j yY3 Licensee P, jn. Cause & Corrective No . Date g 3g jg5 Event g? al Action to H

$5 5 Report a mV  !' Prevent Recurrence 3

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8 851202 F 65.6 A 3 85-034 EB RELAYX relay trip function has been bypassed on all four ESS transformers (101,111, 201, 211). The sudden pressure relays only provide transforrrer protection, and bypassing their function does not reduce the reliability of the ESS buses. Diffcrential protection is still provided for all four ESS transforfners.

I 2 3 4 F: Forced Reason: Method: Exhibit G Instructiims 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 & License Examination from previous month F-Adnunistrative 5-Reduction 5 Goperational Eston (Explam) Exhibit I Same Source (9/77) llother (Explain) 9-Other

s UNIT 1 SUSQUE!! ANNA STEAM ELDCTRIC STATIN Docket No. 50-387 Date January 8, 1986 Canpleted by L.A. Kuczynski Telephone (717)S42-3759 Challences to Main Steam Safety Relief Valve Following the scram of Decanber 2,1985, SRV's 'B' and 'E' actuated autanatically.

They rescated properly.

RX PRESSURE (psig) RX PRESSURE (psig)

SRV OPEN CIDSE AT SRV OPEN AT SRV CIOSE B 15:08:02 15:08:14 1079 978 E 15:08:04 15:08:12 1074 994 Changes to the Offsite Dose Calculation Manual See Attached.

Major Changes to Radioactive Waste Treatnent Systens None.

1

AVERAGE DAILY UNIT POWER LEVEL

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w DOCKET NO. 50-388 Cf)l g L7 UNIT 'No Ip C DATE January 8, 1986 ,

Jggc 3Y COMPLETED BY L.A. Kuczynski )

TELEPHONE (717)542-3759 MONTH December. 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILv POWER LEVEL (MWe. Net) ( g w e , ,,

g 820 g7 1,053 2 510 is 1.053 3 0 g, 1,052 ,

4 0 20 1,034 5

0 586 21 6 0 600 22 7 0 23 937 _

s 199 1,048 24 9 757 23 1.053 10 860 26 1,054

!! 975 27 1.052 1,051 990 12 23 13 1.053 29 1,051 1,055 1,052 34 30

• 1,053 1.050

15 3l 16 1,053 INSTRUCTIONS l On this format, list the average daily unit power levelin Mhe Net for each day in the reporting month. Compute to

the nearest whole megawatt.

(9/77)

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

26. Units in Test Status tPrior to Commercial Operation): Forecast Achiesed INITIA L CRITICA LITY INITIA L ELECTRICITY COMMERCIAL OPERATION (o n' t

%pANN4 I ,I . q , a A g ' I UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-388 d UNITNAME 'Iko $ DATE .Tannarv 9. 14R6 , COMPLETED BY L.A. Kuczynski % RIC @6I REPORT MONTH December, 1985 TELEPHONE (717)542-3759 Page 1 of 3 n. - E E , .5 ? }g }I3 Licensee ' [-r, g e, Cause & Corrective N. . . Date g 3g jg5 Event g? 63 Action to H fE '5 Report 2r mo !O Prevent Recurrence 2~ f;i =5 v 5 18 851202 F 141.4 A 3 50-387/ EB RELAYX On December 2, 1985 at approximately 85-034 1504 a ' Sudden Pressure' relay assoc-(Unit 1 LER) iated with Emergency Safeguards System (ESS) Transformer 111 misoperated. This caused a trip of ESS Transformer 111 which normally supplies ESS buses IC and 2C. The momentary power loss to the IC and 2C buses and the associated AC distribution panels caused the speed of all three feedwater pumps on each unit to lockup (fail constant) and caused a simultaneous runbac'c and lock-up of the 'A' reactor recirculation pumps. The, speed of the 'A' reactor recirc pump on each unit decreased slightly before locking up, which caused reactor vessel water level to increase. Unit 1 scranmed on high (continued) I 2 3 4 F: Forced Reason: Method:' Exhibit G - Instru: ions S: Scheduted 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 & License Examination from previous month F-Adnunistrative G-Operational Error (Explain) 5-Reduction 5- - Exhibit I - Same Source (9/77) Il-Other (Explaini 9-0ther %pANf% 4 $5) fi \ m " .... p ~ UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-388 d UNIT NAME h j $ Peat DATE January 8, 1986 k RfC 6I REPORT MONTII December.1985 COMPLETED BY L.A. Kuczynski TELEPHONE (717)542-3759 ' Page 2 of 3 "i - ,  !? 3 Ek Licensee [g  !". Cause & Corrective No. Date i 5? d 3sE Event t; 7 l' Action to H 5 <E U c3 E jig Report a [ '8 Prevent Recurrence i c5 18 851202 F 141.4 A 3 50-387/ EB RELAYX vessel water level. Unit 2 scranmed 85-034 on low vessel water level when (Unit 1 LER) attempts to restore feedwater level control were unsuccessful. An uninterruptable power supply to the feedwater control circuitry has been added to Unit 1 and Unit 2. This will enable the feedwater system to respond to vessel level transients during electrical system perturbations. The relay (Qualitrol 910 Series Rapid Pressure Rise Relay) was partiallydis-assembled and inspected on site but a failure mechanism could not be ident-ifled.- The relay has been returned to the manufaturer, for further analysis. . In the interim, the sudden pressure (continued) I 2 3 4 F: Forced Reason. Method: Exhibit G. Instructions S. Schedufed A. Equipment Failure (Explain) l-Manual for Preparation of Data B Maintenanceof 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 G-Operational Eiror (Explain) 5-Reduction Exhibit 1 - Same Source (9/77) 11-01her ( Esplain) 9-Other 4.M 4 h! 4=-rr) \ y3 p - tfd ML UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-388 j @ UNIT NAME N $@ .C [ DATE Jarutwv R _ 14R6 COMPLETED BY L.A. Kuczynski y RfC $ REPORT MONTH Decernber, 1985 TELEPHONE (717)542-3759  ; Page 3 of 3 n.. - E c , {g 3 y ~E y Licensee Eg ge, Cause & Corrective No. Date g ~g ( j 5 Event p gO'8 Action to . H y= 5 <~ g =t Report a mV vo Prevent Recurrence c5 18 851202 F 141.4 A 3 50-387/ EB RELAYX relay trip function has been bypassed 85-034 on all four ESS transfonners (101,111, (Unit 1 LER) 201,211). The sudden pressure relays only provide transfonner protection, and bypassing their function does not reduce the reliability of the ESS buses. Differential protection is still provided for all four ESS transfonners. 19 851221 S 0 A 5 N/A IIC PIPEXX Power was reduced for condenser tube plugging work in order to minunize personnel exposure. 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 of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Scram. Event Report (LER) File INUREG-D Regulator) Restriction 4 Continuation 0161) Eoperator Training & License Examination from previous month F-Administrative G-Operational Error IExplain) 5-Reduction 5-Exhibit I . Same Source 19/77) IIOther (Explain) 9-Other , . .- .=_ - .- _ . _ - _ ._ UNIT 2 SUSQUEHANNA STEAM ELECTRIC STATICN Docket No 50-388 Date January 8, 1986 Cmpleted by L.A. Kuczynski Telephone (717)S42-3759 1 Gallenges to Main Steam Safety Relief Valves Following the scram of December 2, 1985, SRV 'A' was manually actuated twice.' It reseated properly. RX PRESSURE (psig) RX PRESSURE (psig) -OPEN CIOSE AT SRV OPEN AT SRV CIDSE 15:25:41 15:25:43 1012 1006 15:25:51 15:33:43 ~995 736 T Ganges to .the Offsite Dose Calculation Mynlal See Attached. ! Major Changes to Radioactive Waste Treatment Systcyns None. I i i + 4 I i 1 4 . . . ~ . . . . _ . . _ . . _ _ . . . _ . . _ _ . . . , _ . . . . _ . ~ . . . , - . . . . _ . . . . _ , _ . _ _ _ . , . . _ _ _ , . _ _ _ , , . . _ . _ _ _ . - . . . _ . , , - - _ _ _ . . _ . , - _-- _ . - . ... ._ __ -~ _ . - .- _ . m ATTACHMENT January 1986 This revision to the ODCM became effective November 22, 1985, upon signature by the Manager-Nuclear Support. Changes have been denoted by revision bars in the right margin. A summary of the changes follows:

1. :The Methodologies for the Service Water, RHR Service Water and the Main

Condenser Offgas Pretreatment monitor alarm set points were added to <

1 reflect current station operating procedures (pages 9, 9a and 12).

2. Operational REMP sample locations and collection frequencies were updated (pages 41, 42 and 43). 1 5 3. A Dose Assessment Policy Statement section was include 3 to document calculational designs, methodologies, or bases not specifically outlined in the text of the ODCM (pages 49 and 50).

4. Sample set point calculations in Appendix A were updated to reflect current station operating procedures (pages A-1 through A-2B).

i J J 4 ) + 4 } - 9 mm4 +-%.7.--,r, ,----.vn-.-,,- ,,w,,1-v--. -..<w,.,--.,n--%, r,m.m,pe,--.y-,- .,.-.-c+, ---- ,,-.3.,-y ,.-, .m,..-.--- ,- - . . ,,--+ey- -r .,m r ,-,e-v -v~.- 9 4 4 PENNSYLVANIA POWER & LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL l Pr. par.d By k 1.- Dat. // ! 2 2.,/p $~ .. 1... 37 7[EMnf o. . n,h2/er , ,,,r.... ,, . aeLP22 Panag.r-N6 clear Supppt .... ii/u W a, . s' S CONTROLLED TABLE OF CONTENTS g 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 ab 1/20/84 2.2 GASEOUS EFFLUENT MONITORS................. 9 11/22/85 9a 11/22/85 10 7/09/84 11 7/09/84 12 11/22/85 l 13 4/26/85 3.0 LIQUID EFFLUENT CONCENTRATION MEASUREMENTS.... 14 10/25/83 15 10/25/83 4.0 GASEOUS EFFLUENT 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 17A 4/26/85 18 4/27/83 19 4/27/83 20 4/26/85 5.0 INDIVIDUAL DOSE DUE TO LIQUID EFFLUENT........ 21 4/27/83 22 4/26/85 23 5/11/82 24 5/11/82 6.0 INDIVIDUAL DOSE DUE TO GASEOUS EFFLUh2'T. . . . . . . 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 5/11/82

.9 5/11/82 7.0 TOTAL DOSE.................................... 30 4/27/83 31 5/11/82 8.0 OPERABILITY OF WASTE TREATMENT SYSTEMS........ 32 4/27/83 8.1 LIQUID WASTE TREATMENT.................... 32 4/27/83 8.2 GASEOUS WASTE TREATMENT................... 32 4/27/83 33 $/11/82 8.3 SOLID WASTE TREATMENT..................... 34 4/27/83 35 5/14/84 36 5/11/82 37 5/11/82 38 5/11/82 NOV 2 2 2 1 I 9.0 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM. 39 7/12/82 9.1 DEFINITIONS............................... 39 7/12/82 9.2 MONITORING PR0 GRAM........................ 39a 4/26/85 9.3 CENSUS PR0 GRAM............................ 40 5/14/84-40s 7/12/82 41 11/22/85 42 11/22/85 43 11/22/85 44 5/11/82 45 4/26/85 46 5/11/82 47 5/11/82 48 4/27/83 10.0 DOSE ASSESSMENT POLICY STATEMENTS............. 49 10/28/85 50 10/28/85 APPENDIX A - SAMPLE CALCULATIONS OF ODCM PARAMETERS........................... A-1 11/22/85 A-2 11/22/85 A-2A 11/22/85 A-25 11/22/85 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 A-7 $/11/82 A-8 $/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 REQUIREMENTS............... B-1 5/11/82 1 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 APPENDIX E - METHODS USED TO GENERATE NSI-4.6 DOSE RATE CALCULATION WORKSHEETS .......................... E-1 4/26/85 E-2 4/26/85 E-3 4/26/85 g 2 2 0P,5 11 t CONTROUEn LIST OF TABLES g Revision Date Table 1 Radiological Effluent Objectives and Standards.... 6 4/27/83 Table 2 Dose Factors for Noble Gases and Daughters........ 17A 4/26/85 Table 3 Annual Average Relative Concentrations and Deposition Rates.................................. 18 5/11/82 Table 4 Dose Parameters for Radionuclides Other Than , Noble Cases....................................... 20 4/26/85 Table 5 Liquid Dose Parameters for Adults................. 23 5/11/82 Table 6 Maximum Pathway Dose Factors Due to Radionuclides Other Than Noble Cases.............. 28 5/11/82 Table 7 Operational Radiological Environmental Monitoring Program................................ 41 11/22/85 42 11/22/85 43 11/22/85 Table 8 Detection Capabilities for Environmental Sample Analysis................................... 46 5/11/82 1 Table B-1 Radiological Environmental Monitoring Program Annua l S u mma ry . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . B-3 5/11/82 Table B-2 Reporting Levels for Nonroutine Operating Reports........................................... B-4 5/11/82 i t i l nay 22 BB5 , i 111 l 7 ~ Radiation setpoints for these monitors are set at 2E-5 uCi/cc cesium-137 equivalent. Considering the radionuclides predominant in SSES liquid effluents, e.g., Co-58, Co-60. Fe-59, Mn-54 and Cr-51, use of a setpoint based on the Cs-137 MPC is conservative based on the following parameters:

1) photon abundance (85%)

2) magnitude of applicable MPC (2E-5 pCi/ce)

Because Service Water & RHR Service Water are not normal release pathways for liquid effluents, no credit should be taken for possible dilution scenarios. All service water should be maintained below 2E-5 pCi/cc Cs-137 equivalent. In order to minimize the chance of a change in the background of a monitor masking a significant trend in monitored activity, the alarm setpoints for the Service Water and RHR Service Water monitors are determined as follows:

a. When monitor background < (2E-5)/ Cal. Factor:

HI RAD Setpoint = 0.5 Background + (2E-5)/ Cal. Factor DOWNSCALE or LOW RAD Setpoint = 0.5 Background

b. When monitor background > (2E-5)/ Cal. Factor:

HI RAD Setpoint = Background + 0.5 (2E-5)/ Cal. Factor DOWNSCALE or LOW RAD Setpoint - Background - 0.5 (2E-5)/ Cal. Factor Where Setpoint = Alarm threshold value to be entered into monitor (cps for Service Water, cpm for RHR Service Water). e  % y Background { Monitor background at most recent background determination (cps for Service Water, cpm for ? RHR Service Water). (2E-5) = Cs-137 Maximum Permissible Concentration (uCi/ml). Cal. Factor = Monitor response factor per unit Cs-137 concen-tration determined during most recent calibra-tion (uci/al,per cps for Service Water, pCi/mi per cpm for RHR Service Water). The ALERT RAD setpoints for the RER Service Water monitors are maintained at 30% of the applicable HI RAD setpoint (cyc). 2.2 CASEOUS EFFLUENT MONITORS , SPECIFICATION 3.3.7.11-THERADIOACTIVECA5EOUSEFFLUENTMONITORING INSTRUMENTATION CHANNELS SHOWN IN TABLE 3.3.7.11-1 SHALL BE OPERABLE WITH THEIR ALARM / TRIP SETPOINTS SET TO ENSURE THAT THE LI'MITS OF SPECIFICATION 3.11.2.1 ARE NOT EXCEEDED. THE ALARM / TRIP SETPOINTS OF THESE CHANNELS SHALL BE DETERMINED IN ACCORDANCE WITH THE METHOD-OLOGY AND PARAMET!'.RS IN THE ODCM. Noble gas activity. monitors, iodine samplers, and practiculate samplers are present on the reactor building ventilation system (Units'l'and 2), the turbine building ventilation system (Units 1 and 2), an1 the standby gas treatment system. Effluent system flow rate and sanpler flow rate are measured on all of the systems allowing the vent monitor microprocessor to calculate release rates based on measured flow rates. Precautions, limitations, and set-points applicable to the operation of the SSES gaseous effluent monitors are provided in the apriicable plant Procedures. Setpoints are conservatively established for each ventilation effluent monitor so that the instantaneous dose rates corresponding to 10 CFR 20 annual dose limits in unrestricted areas will not be exceeded. Conservatism is to be incorporated into the determination of each setpoint to account for: - 9a - NOV 2 2 M85 For the noble gas setpoint, the calculated whole body and skin dose 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 mrea/yr.

4. The limiting release rates are converted to limiting vent concentrations

-using high limit vent flow rates. Limiting Vent Concentration, uCi/cc = (Limiting Release Rate, Ci/yr) (10E6uCi/Cil (5.26ES min /yr) (Vent 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 indica-tion of possibly abnormal flow rates. The main condenser offgas pre-treatment monitor provides indication of offgas activity prior to input to the holdup system. Alarm setpoints are based on two times (HI) and three times (HI HI) the steady state full power offgas activity readings ("unita" from log monitor). The DOWNSCALE setpoint is maintained at 2 units. The HI HI setpoint should not be set to exceed 3E5 pCi/sec based on correlation of monitor response with sample analysis data. NOV 2 2 GBt e TABLE 7 OPERATI0tiAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Page 1 of 3 Exposure Pathways Number of Samples Sampling and Type and Frequency 1 and/or Sample and Locations

• Collection Frequency of Analysis Airbo rne Rrdiciodine and 11S2 (0.43 mi SW - Golomb House) Continual sampler operation Radioiodine Canister:

Particulates 981 (1.28 mi S - Transmission Line) with sample collection weekly.** analyze weekly for 1-131 SS4 (0.76 mi E - W of Bio Consult) 12E1 (4.68 mi WSW- Berwick Hospital) 7G1 (13.51 mi SE - PP&L Hazleton Particulate Sampler: Chemical Lab)* Analyze for gross beta 2S2 (0.89 mi NNE - Susq. Energy Info. radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> , , Center) fullowing filter change. > 15S4 (0.56 mi NW - Tranuaission Corridor) Perform gamma isotopic }" ID2 (3.92 mi N - Mocanaqua Substation) analysis on composite 3D1 (3.36 mi NE - Pond Hill) sample (by location) l 12G1 (14.6 mi WSW - Bloomsburg Service' quatterly. Cente r) a Direct Radiation IS2 Perimeter Fence - 0.24 mi N Quar.terly Gamma Dose: Quarterly. ID2 Hocanaqua Substation - 3.97 mi N 2S3 Perimeter Fence - 0.22 mi NNE I 2B3 Luzerne Outerwear - 1.31 mi NNE f 2F1 St. Adalberts Cemetery - 5.88 mi NNE 3S4 Perimeter Fence - 0.30 mi NE l 3DL Pond Hill - 3.36 mi NE I 3F1 Valania Resident (Nanticoke) - 9.10 mi NE 3G3 Wilkes-Barre-Horton St. Substation - at 15.80 mi NE" l 52 4S3 Perimeter Fence - 0.23 mi ENE l gg 4E1 Pole (#) 46422 N35197 - 4.75 mi ENE po 4G1 Mountain Top,- Industrial Park - .. 13.91 mi ENE , fk . 5S7 Perimeter Fence - 0.26 mi E l SE2 Bloss Farm - 4.51 mi E 6S4 Perimeter Fence - 0.18 mi ESE 6A1 State Police - 0.55 mi ESE TA!LE 7 (Continued) Page 2 of 3 Exposure Pathways Number of Samples Sampling and Type and Frequency end/or Sample and Locations Collection Frequency of Analysis 6El St. James Church - 4.74 mi ESE 6S9 Perimeter Fence - 0.20 mi ESE ' 7S6 Perimeter Fence - 0.21 mi SE 7El Harwood Transmission Line Pole #2 - 4.22 mi SE 7G1 Hazleton Chemical Lab - 13.51 mi SE" 8S2 Perimeter Fence - 0.22 mi SSE I 882 LaWall Residence - 1.40 mi SSE 8D3 Mowry Residence - 3.95 mi SSE l 9S2 Security Fence - 0.17 mi S I 9D1 Smith Farm - 3.64 mi S 10S1 Perimeter Fence - 0.43 mi SSW I 10D2 Ross Ryman Residence - 3.00 mi SSW 11S3 Security Fence - 0.34 mi SW 11El Jacobsen - 4.74 mi SW s 12S3 Perimeter Fence, - 0.36.mi WSW l $ 12ElBerwickHospital-4.68mgWSW e 1201 Bloomsburg - 14.57 mi WSW 13S2 Perimeter Fence - 0.38 mi W l 13E4 Kessler Farm - 4.10 mi W 14SS Site Pole 43996/N34230 0.47 mi WNW l 14El Canouse Farm - 4.11 mi WNW l 15F1 Zawatski Farm - 5.37 mi NW 15SS Perimeter Fence - 0.36 mi NW I 16S1 Perimeter Fence - 0.29 mi NNW 8 16S2 Perimeter Fence - 0.34 mi NNW l 16F1 Hidlay Residence (Huntington Mills) - 7.81 mi NNW Witarborne Surface SS8 intake area (upstream) Crab sample over monthly C===a isotopic analysis 6S5 outfall area (' downstream period- monthly. Composite h 6S6 river water intake line* ) I Monthly composite tritiumanalysisatleastl 6S7 cooling tower blowdown discharge Monthly composite quarterly. (( line IhDrinking 12H2 Danville Water Co. Monthly composite Croas beta and gamma (Approximately 30 miles downstream) isotopic analyses monthly. Composite for tritium analvata at 1.a e I TABLE 7 (Continued) Page 3 of 3 Exposure Pathways Number of Samples Sampling and Type and Frequency cad /or Sample and Locations Collection Frequency of Analysis 1 S diment from 7B Bell Bend - 1.2 mi SE Semiannually Gamma isotopic analysis I Shoreline semiannually. Milk *** .12B2 Shultz Farm - 1.69 mi. WSW Semi-montnly when animals Gamma isotopic and 1-131 13E3 Dent Farm - 4.9 mi. W are on pasture, monthly analysis of each sample. SE1 Bloss Farm - 4.4 mi. E othe rwise 10G1 Davis Farm - 14 mi. SSW" 10D1 Ryman Farm - 3.0 mi SSW l d Fish and Outfall area Semiannually. One sample Gamma isotopic on Invertebrates 2H Falls Pa. a from each of two recrea- edible portions. (Approximately 30 mi NNE) tionally important species. from any of the following families: bullhead catfish, { w sunfish, pikes, or perches. ' 8 Food Products llD1 Zehner Farm - 3.3 mi SW l At time of harvest Gamma isotopic on vegetable edible portions. 'The location of samples and equipment were designed using the guidance in the Branch Technical Position to NRC Reg. Guide 4.8, Rev. 1 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.

• • A dust loading study (RMS-TR-81-01) concluded that the assumption of I for the transmission correction factor for

. gross beta analysis of air particulate samples is valid. Air particulate samples need not be weighed to determine a transmission correction factor.

• • • If a milk sample is unavailable for more than two sampling periods f rom one or more of the locations, a vegetation cample shall be substituted until a suitable milk location is evaluated. Such an occurrence will be documented in the REMP annual report.

• Control sample location.

Temporary locations until compositor is installed in intake and discharge lines; then frequency changes to composite sample collected over one-month period and location changes to 6S6 intake line, 6S7 discharge line. sr The upstream sample will be taken in the intake line and which is beyond significant influence of the discharges. 5@ The downstream sample will be taken in the discharge line. p3 There is no river water intake at Berwick for drinking water. See Susquehauna SES-ER-OL Appendix C, page RAD-3.1.

po The calculated dose for Danville to the 1,;fant thyroid was 0.13 mres per year. .Therefore, there is no need to take a composite sample over two-week period and perform an 1-131 analysis.

, Yk The sample collector will determine the species based upon availability, which may vary seasonally and yearly. l ~ 10.0 DOSE ASSESSMENT POLICY STATEMENTS 10.1 For determination of compliance with bSES Technical Specification dose limits, effluent totals shall be based only on activity posi-tively detected at the'95% confidence level. '10.2 For determination of compliance with SSES radioactive effluent dose limits which are on a "per reactor unit" basis:

a. Effluents from the Unit 1 Reactor Building vent and the Unit 1

~ Turbine Building vent shall De included as Unit I releases.

b. Effluents from the Unit 2 Reactor Building vent and the Unit 2 Turbine Building vent shall be included as Unit 2 releases.

c. Effluents from the Standby Gas Treatment System vent shall be equally divided between Unit 1 and Unit 2 release totals.

d. Waterborne effluents shall be equally divided between Unit I and Unit 2 release totals.

10.3 Doses from effluent pathways other than the usual, monitored path-ways shall be included in determining compliance with site dose limits if an assessment made in accordance with the parameters and assumptions of the ODCM indicates that the total calculated dose contribution from unmonitored pathways exceeds 5% of the calculated dose from normal, monitored pathways. 10.4 When the Standby Gas Treatment System is not being used, there remains a small amount of flow from the SGTS vent. This residual flow is exhaust from the battery rooms in the control structure. Because there are no identifiable sources of radioactivity in these rooms, auxiliary particulate and iodine sampling and noble gas grab ggy 2 2 665 , _ _ ~ _ . _ _ . .._-, _ _ . _ _ , _ _ _ , - . . _ . _ , - _ _ _ . _ _ _ - . i sampling at 4-hour intervals are not required from the SGTS vent when the SGTS continuous vent monitor is out of service, provided that -

a. the Standby Gas Treatment System is not being used,

b. there are proper administrative controls in place to ensure that'the required sampling will begin within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> if the treatment system is operated.

10.5 Effluent monitor alarm / trip setpoints calculated in accordance with

the ODCM shall be considered upper limit values. Higher (leas conservative) setpoints shall not be used, however lower (more conservative) setpoints may be used as required to maximize the utility of the monitor.

H0V 2 2 1945 APPENDIX A SAMPLE CALCULATIONS OF ODCM PARAMETERS A.1 SETPOINTS A.I.1 Liquid Effluent Monitors A.I.l.1 Liquid Radwaste Discharge Line Monitor For an unidentified mixture with an assumed MPC of IE-7 uCi/ml, an actual activity of IE-5 pCi/al, and a blowdown flow setpoint of 5000 gpa, the setpoint concentration, c, can be determined from c = X'(A). If X = 3, then the actual setpoint concentration is: c = X'(A) = 3*(IE-5) c = 3E-5 uCi/m1 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 -8 uCi/al per cpm, would be: Setpoint cpm = __ c + Background (cpm) Cal. Factor Setpoint cpm = 3E-5 + Background -8 1.3 x 10 Setpoint cpm = 2.3E3 + Background The LRW discharge flow setpoint is then determined as follows: NOV 221985 A-1 I s , c F + f = Y-(A) f HPC where Y is made equal to 10. 5000 + f = 10*(IE-5) f IE-7 f = 5 spa For an identified mixture with'an actual MPC of 7.22E-7 uC1/mi and the same activity, bicwdown flow and X and Y values as above, the LRW discharge monitor setpoint value and LRW discharge flow set-' point become: Setpoint concentration (c) = 3E-5 pC1/al Setpoint value = 2.3E3 cpu + Background LRW discharge flow setpoint (f) = 36 gpm A.I.l.2 Service Water Monitor Sample Data A: Background - 300 eps Calibration Factor = 1.5E-8 pCi/ml per cps (2E-5)/ Cal. Factor = 1333 cps Because 300 cps is less than 1333 cps: HI RAD Setpoine = 0.5 Background + (2E-5)/ Cal. Factor = 0.5 (300 cps) + (2E-5)/(1.5E-8) = 150 cps + 1333 cps = 1483 cps DOWNSCALE Setpoint = 0.5 Background = (0.5)(300 cps) = 150 cps Sample Data B: Background = 1400 cps Calibration Factor = 1.5E-8 pCi/ml per cps (2E-5)/ Cal. Factor = 1333 cps Because 1400 cps is greater than 1333 cps: HI RAD Setpoint = Background + (0.5)(2E-5)/ Cal. Factor = 1400 cps + (IE-5)/(1.5E-8) = 2067 cps DOWNSCALE Setpoint = Background - 0.5 (2E-5)/ Cal. Factor) = 1400 cps - 0.5 (2E-5)/(1.5E-8) = 1400 cps - 667 cps = 733 cps ,_2 NOV 2 2 1985 9 , ss A.1.1.3 RHR Service Water Monitor Sample Data A:. Background = 160 cpm Calibration Factor = 3.9E-9 pCi/mi per cpm (2E-5)/ Cal. Factor = 5128 cpm Pecause 160 cpm is less than 5128 cpa: HI RAD Setpoint = 0.5 Background + (2E-5)/ Cal. Factor = 0.5 (160 cpa) + (2E-5)/(3.9E-9) = 80 cpm + 5128 cpm = 5208 cpm LOW RAD Setpoint = 0.5 Background = 0.5 (160 cpm) = 80 cpm ALERT Setpoint = 0.8 HI RAD Setpoint = 4166 cpm Sample Data B: Background = 6000 cpm Calibration Factor = 3.9E-9 pCi/ml per cpm (2E-5)/ Cal. Factor = 5128 cpm Because 6000 cpm is greater than 5128 cps: HI RAD Setpoint = Background + (0.5)(2E-5)/ Cal. Factor = 6000 cpm + (IE-5)/(3.9E-9) = 6000 cpm + 2564 cpm = 8564 cpm LOW RAD Setpoint = Background - 0.5 (2E-5/ Cal. Factor = 6000 cpm - 0.5 (2E-5)/(3.9E-9) = 6000 cpm - 256A cpm = 3436 cpm ALERT Setpoint = 0.8 HI RAD Setpoint = 6851 cpm A.1.2 Gaseous Effluent Monitors A.1.2.1 Noble Gas Monitor To determine the release rate limit for noble gases, 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: (Qy 22 B85 A-2A ! 5 . .,,.= Argon-41 25 C1/yr per reactor Krypton-83a 4 Krypton-85a 1,700 Krypton-85 270 Krypton-87 32 Krypton-88 660 Xenon-131m 71 Xenon-133a 14 Xenon-133 12,500 Xenon-135m 220 Xenon-135 590 Xenon-138 290 Total 16,376 Ci/yr per reactor i Il0V 2 21985 A-2B - - ~ , - . - - - . . . - , _ . - - - - . . . . . . - - - . _ _ . _ - - . _ _ , . , - - , _ . . . . - - - - A o . (@ Pennsylvania Power & Light Company Two North Ninth Street

• Allentown, PA 18101 + 215 / 770 5151 Harold W. Keiser Vice President-Nuc!aar Operations 215/770-7502 JAN 151986 Director, Data Automation &

Management Information Division Attention: Mr. M. R. Eeebe Management Information Branch Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION MONTHLY OPERATING REPORTS ER 100450 FILE 841 Docket Nos. 50-387/NPF-14 PLA-2580 50-388/NPF-22

Dear Mr. Beebe:

The December 1985 monthly operating reports for Susquehanna SES Units 1 and 2 are attached.

Very truly yours, e

H. W. Keise Vice President-Nuclear Iperations Attachment cc: Lr. Thomas E. Murley Regional Administrator-Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406 Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555 Attn: Document Control Desk (12 copies)

Mr. R. H. Jacobs - NRC Ms. M. J. Campagnone - NRC 7 J

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