PLA-2516, Monthly Operating Repts for Jul 1985

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Monthly Operating Repts for Jul 1985
ML20132G641
Person / Time
Site: Susquehanna  
Issue date: 07/31/1985
From: Keiser H, Kuczynski L
PENNSYLVANIA POWER & LIGHT CO.
To: Beebe M
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-2516, NUDOCS 8510010591
Download: ML20132G641 (24)
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Text

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1 3 DOCxET NO.

50-387 k,

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UNIT One

n e,' 'y Z _.T _ _ ~_ _ _ 3 L1. T C". J OPERATING DATA REPORT DOCKET NO. 50-387 T DATE 08/08/85 klC SY COMPLETED BY l A. Kuczynski TELEPHONE (717)S42-3759 OPERATING STATUS Unit 1 N"

1. Unit Name:

Susquehanna Steam Electric Station Ju1y, 1985

2. Reporting Penod:
3. Licensed Thermal Power (MWt p:

3293

4. Nameplate Rating (Gross MWe):

1152 1065

5. Design Electrical Rating (Net MWeL 1068
6. Maximum Dependable Capacity (Gross MWe):

1032

7. Masimum DependaMe Capacity (Net Mbel:
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Gise Reasons:

None None

9. Power Lesel To %hich Restricted,if Any (Net MWe):

None

10. Reawns For Restrictions,if Any:

This Month Yr. to.Date Cumulatise

11. Hours in Reporting Period 744 5.087 18,840
12. Number Of Hours Reactor Was Critical 744 2.148.5 12,541.2
13. Reactor Reserse Shutdown Hours 0

41.8 513.2

14. Hours Generator On-Line 744 2.068.5 12,215.4
15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 2.420.853 6.100.303 36.729.291 17 Gross Electrical Energy Generated (MWH) 784.216 1,976,036 11,966.566
18. Net Electrical Energy Generated (MWH) 756.234 1,862,412

-11,442,982

19. Unit Service Factor 100 40.7 64.8
20. Unit Availsbility Factor 100 40.7 64.8
21. Unit Capacity Factor (Using MDC Net) 98.5 35.5 58.8
22. Unit Capacity Factor (Using DER Net) 95.4 34.4 57.0__
23. Unit Forced Outage Rate 0

2.5 12.2

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Eacn r None j

i

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

N/A

26. Units in Test Status (Prior to Commercial Operation):

Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIA L OPER ATION (o /7 ? i d 4 ( I 9 / 7 N 7 SF .o ) SF e y.A c o f@E. hr g ec de l ud el N 'p d o .')' A n D I P a e t U e N e a s 8 N t 4 \\' 8I y, y @ 2 i - GFEDCBAR I 4o,- l - - - - - - - e OOAORRMEa tp dp e e aqsfiu o hemegl er i r u unin a e tp r at nt ail e ( i iot nnm j.T j s Eot r o ae xnr rg nn a Ty ct iRg pal a ir t a e l EviR F i ene oai nrr is f ) l o nt Tu r r g i e e r 553 &c i s t i t( E o E x Ln x pl e l j2 *- ci p a ni n a ) e ni U s psE ) 3 ~ N E 6 e}:L I x T a mi R H S n E U at P T i R [ o O D n eEi c R O p v e soe n T W n t t se M N a e S ON A 1 N 1 3 D 1 P c J O 95 4321 M E E u W - - - - e i fCAMMt 07,t v R E OR roua ah te nn o t hdon o eu m tm lu u d. R a a E 1 rc a l 9 D i pnt S t i c 8 U iruc f c._ 5 r o e a Sa n v tc m '?,e C 1 r 1 iia. oom 0 un. N s S mon t h 5 4 ( O P C M D r E 0EEfE e a T o v u E P U O x 1 vnr x h 6et h nae L L N C e s i 1 nr Pi E I ei P T T K ty r b dA E t b ) E i RSpt Rr ehaG eoC H E D N T t c o O D AA N 1 per ea - ut r NBTM ot r S t s ion e ' c t r oe EYEE.O r I r a m fns n i t ( o t e Lr c v or e e ( L 0 O 5 S ELfu 7 c 8 n 0 o RiDti 7 / e .A 1 c u I 0 3 eao rc Fnt n ) 8 8 e is a s l e S K / 7 e e 4 u 8 ( 2 c 5 N - z U 3 y R 7 n E 5 s G 9 k i UNIT 1 SUSQUEHANNA STEAM ELECTRIC STATION Docket No. 50-387 Date 08/08/85 Completed By L.A. Kuczynski Telephone (717)S42-3759 Challenges to Main Steam Safety Relief Valves None Changes to the Of f site Dose Calculation Manual See attached Major Changes to Radioactive Waste Treatment Systems None e hN A 4 g. AVERAGE DAILY UNIT POWER LEVEL ^ e .&, /I' \\ - t i X 3 DOCKET NO. .5.0. _3.8.8 (t) / k'

  • l UNIT Two

s---.,-..m e-.,, .,-,.-g-, n. m~---v.n-,m.e-----v,------a ,----wv.nvr-,-n-e,,--,m,,--,,--e.,.-,,n<.-.r-,.n-,m.~.--a, s For the noble gas setpoint, the cciculated whole body and skin dose rates via the plume pathway are subject to the 10CFR20-derived limita of 500 and 3000 mrem /yr, respectively. The whole body dose rate limit is usually most restrictive. For particulate's and for iodine-131, the maximum calculated organ dose via che inhalation pathway is subject to the limit of 1500 mrem /yr. 4. The limiting release rates are converted to limiting vent ~concentra-tions using high limit vent flow rates. Limiting Vent Concentration, uCi/cc = (Limiting Release Rate, Ci/vr) (10E6uci/Ci) (5.26E5 min /yr) (Vent Flow Rate, cc/ min) Sample calculations of liquid and gaseous cffluent 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 flev rates. The main condenser offgas pre-treatment monitor provides indication of offgas activity prior to input to the-holdup syste=.. Alarm setpoints are based on two times and three times the steady state full power offgas activity readings. i i l l APR 26 G6! 12 - ( SPECIFICATION 3.11.2.6 - THE CONCENTRATION OF HYDROGEN OR OXYCEN IN THE MAIN CONDENSER OFFGAS TREATMENT SYSTEM SHALL BE LIMITED TO LESS THAN.OR EQUAL TO 4% BY VOLUME. Hydrogen recombiners are used at SSES to maintain the relative concentration of components of potentially explosive gas mixtures outside the explosive envelope. The main condenser offgas treatment system explosive gas monitoring system (offgas hydrogen analyzers) have setpoints to alarm at 1% and 2% hydrogen. APR 2 0 USS l l l ) C the average concentration of radionuclide (i) in = undiluted liquid effluent during time period, 6t, for any liquid effluene batch release (pC1/ml). .F the discharge line dilution factor for C during any- = 3 I. liquid effluent batch release. Defined as the ratio of the average undiluted liquid radwaste effluent line l flow during release to the average flow from the plant discharge line to unrestricted receiving watera. 1 A, = the composite dose parameter for the total bcdy or any ^' organ (T) for each identified principal gamea and beta emitter (i) (mrem /hr per uCi/ml) (see Equation 11 Table 5). 4 g K, (U,/D,+ Uf BF ) DF, (11) A = 1 where: l 0 0 k conversion factor of 1.1 x 10 = (10 pCi/uci)(10 ml/kg) = 8760 hr/yr i 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; dilution factor is 321.) U, = a receptor person's fish consumption by age group fron Regulatory Guide 1.109. Table E-5. BF the bicaccumulation factor for nuclide (i) in fish = i (pC1/kg per pC1/1) from Regulatory Guide 1.109, Table A-1. DF the dose conversion factor for nuclide (i) in a = receptor person for pre-selected organ (t) (arem/pC1) from Regulatory Guide 1.109, Tables E-11, E-12 E-13, l and E-14 The projected quarterly dose contribution from batch releases for which radionuclide concentrations are determined by periodic compos-ice sample analysis, as stated in Table 4.11.1.1.1-1 of the SSES Technical Specificatien may be appro::imated by assuming an average concentration based on the previous monthly er cuarterly composite analysis. i. hw i l l L r-9.2 MONITORING PROGRAM SPECIFICATION J.12.1 - THE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM SHALL BE CONDUCTED AS SPECIFIED IN TABLE 3.12.1-1. Environmental samples shall be collected and analyzed according to Table 7 at locations shown in Figures 6 and 7. Analytical techniques used shall ensure that the detection capabilities in Table 8 are achieved. A dust loading study (RMC-TR-81-01) was conducted to assure that the proper transmission factor was used in calculating gross beta activity of air particulate samples. This study concluded that the sample collection frequency of once per week was sufficient and that the use of I for the transmission correction l factor for gross beta analysis of air particulate samples is valid. The charcoal sampler cartridges used in the airborne radiciodino sampling program (Science Applications, Inc., Model CP-100) are designed and tested by the manufacturer to assure a hw h quality of radiciodine capture'. A certificate from the manufactJrer iro supplied and retained eith each batch of cartridges certifying the percent retention of radiciodine versus air flow rate throust the cartridge. The results of the radiological environmental monitoring program are intended to supple =ent the results of the radiological efflu-ent monitoring by verifying that the measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and model-ing of the environmental exposure pathways. Thus, the specified environmental monitoring program provides measurements of radia-tion and of radioactive materials in those exposure pathways and for those radionuclides which lead to the highest potential radia-tion exposures of individuals resulting frem station operatior. The initial radiological environmental monitoring, program wil. HER 2 6 l$E ,39,, i. a ~ ~ ~. / . 1 k F g '..: 5-'. I M. ( /) j, ,.- s.g.c., rg. ......s., 1 7/- N3 >' .~.i f~}h l K,4.

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d' Gi; O 1 "-"N ~VFP' r wv-,--_,,y -. _ _ = APPENDIX.E i 4 METHODS USED TO GENERATE NSI-4.6 DOSE RATE CALCULATION WORKSHEETS 4 i I. BASED ON VENT MONITOR NOBLE GAS DATA (Form NSI-4.6A) A. WHOLE BODY DOSE RATE Equation 7 of the ODCM states that the whole body dose rate to unrestricted areas due to gaseous effluents is calculated as follows: "J((K)(X/Q)y (Q'gy) Dwb i 1 i i where: D,3 the annual whole body dose rate (mrem /yr). = the whole body rate conversion dose' factor due to i K = g gamma emissions for each identified noble gas 3 radionuclide (1) (mrem /yr per uCi/m ) from Table 2 of 1 the ODCM. Q' # the release rate of -radionuclide (i) from vent = (v) (uC1/sec). = (X/Q)y the highest calculated annual average relative = concentration for any area at or beyond the site boundary in an ugrestricted area from vent release i point (v) (sec/m ). The whole body dose race conversion constant of Form NSI-4.6A is calculated as follows: WB DOSE RATE CONV. FACTOR "(60JL 'gy) ('1 ( i)( Q (.67E-2) C n i where: i f f is the fraction of the total noble gas release which = nuclide (1) constitutes. ~ 1.67E-2 the number of minutes per second. = ~j The whole body dose rate conversion factor (5.88E-4) of Form NSI-4.6A, Rev. O, is based on the SSES Final Environmental Statement (FES) expected annual noble gas relgases and an annual average relative concentration of 4.1E-5 sec/m (ref. SSES 1982 Meteorological Summary). l 4 a E-1 l . _.. _ _ _. _ _.. _ _ _... _ _ _ _ ~,,. _ _,. _.. _.. _..,.,, _.. .,-,_.._.,_,,,..,__,m-_____,_,._....,,_._._.,m..,, l B. SKI.N DOSE RATE i Equation 8 of the ODCM states that the skin dose rate to unrestricted 1 areas due to gaseous effluents is calculated as follows: } D, ((Lg + 1.1 M ) (X/Q)y (Q'gy) = 1 i where: D, the annual skin dose rate (arem/yr). = L the skin dose rate conversion factor due to the beta = emissions for each ideg)tified noble gas radionuclide (1) (mrem /yr per uCi/m from Table 2 of the ODCM. 4 M the air dose factor due to gamma emissions for each - = g identified noble ggs radionuclide (1) (mrad /yr per uCi/m ) from Table 2 of the ODCM (conversion constant of 1.1 converts air dose.(mrad) to skin dos.t (mrem). t The skin dose rate conversion constant of Form NSI-4.6A is calculated as follows: l D SKIN DOSE RATE [ mrem /yr[,(601 Q' (f )(Li + 1.1M )(X/Q)(1.67E-2) CONV. FACTOR (uCi/minj g) i i i i i j The skin dose rate conversion factor (1.16E-3) of Form SI-4.6A, j Rev. O, is based _on the SSES-FES expected annual noble ggs releases and an annual average relative concentration of 4.1E-5 sec/m. l ) II. BASED ON VENT MONITOR DATA OTHER THAN NOBLE GASES Equation 9 of the ODCM states that'the dose rate from inhalation of j radionuclides other than~ noble gases is calculated as follows: i I(P ) (W ) (Q'g) D = g y i i f where: i i D the annual organ dose rate (mrem /yr). = e l~ P the dose parameter for radionuclides other than nobge = gases for the inhalation pathway (mrem /yr per uCi/m ). I W the highest annual average dispersion parameter.for = estimatingthedosetothg)criticalreceptor(relative concentration (X/Q, sec/m for the inhalation pathway). i Q' the release rate of radionuclide (1) from vent = (v) (uCi/sec). E-2 MP 0 l 1 Ths orgen doss rate conversion factors for particulates and I-131 of { Form NSI-4.6C are calculated as follows: ORGAN DOSE RATE CONV. FACTOR (60 h) i(i = 1 where: f the fraction of the total particulate release which = nuclide (1) constitutes (equals 1 for I-131 dose rate conversion factor). 1 .The organ dose rate conversion factors of Form NSI-4.6C (1.94 for particulates and 10.64 for 1-131) are based on SSES-FES expected releases 3 i i and an annual average relative concentration of 4.1E-5 sec/m i III. BASED CN NOBLE GAS LABORATORY ANALYSIS 4 f The whole body dose rate conversion constants of Form NSI-4.6B (Column M) i i are calculated as follows for each nuclide: WB DOSE RATE CONV. FACTOR .6 W 2) = 60 Q i i The skin dose rate conversion constants of Form NSI-4.6B (Column P) are calculated as follows for each nuclide: i i SKIN DOSE RATE CONV. FACTOR .6 L 2) = 60 i i g 3 An annual average relative concentration value of 4.1E-5 sec/m was used for calculation of the constants on Form NSI-4.6B, Rev. O. r IV. BASED ON LABORATORY ANALYSIS FOP. NON-NOBLE GASES f I The organ dose rate conversion constants' of Form NSI-4.6D (Column BB) are I i calculated as follows for each nuclide: ORGAN DOSE RATE CONV. FACTOR C " 60 '(i

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} ~ h l An annual average relative concentration value of 4.1E-5 sec/m3 was used for j calculation of the constants on Form NSI-4.6D, Rev. O. l Because different radionuclides result in maximum dose commitments to dif ferent age groups and/or organs, the methodology of Forms NSI-4.6C and D j is conservative because dose rate contributions from nuclides to differing organs are summed and compared to the dose rate limit which is applicable to l l any one organ. If an apparent noncompliance is calculated by this method, i then for each age group, an organ dose from each radionuclide should be cal-l culated to determine if an actual noncomn11ance exists. ( p 4 D 40 1 E-3

1..

[Q;p N Pennsylvania Power & Light Company Two North Ninth Street

  • Allentown, PA 18101 + 215 I 770 5151 Haro!d W. Keiser Vice President-Nuclear Operations 215/770-7502 AUG 121985 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 STEAM ELECTRIC STATION MONTHLY OPERATING REPORTS ER 100450 FILE 841 Docket Nos. 50-387/NPF-14 PLA-2516 50-386/NPF-22

Dear Mr. Beebe:

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

Very truly yours, b' 4 L:

3 H. W. Keiser Vice President-Nuclear Operations Attachment cc:

Dr. 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 Denk (12 copies)

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

-

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