PLA-2195, Monthly Operating Repts for Apr 1984

From kanterella
Jump to navigation Jump to search
Monthly Operating Repts for Apr 1984
ML20091K741
Person / Time
Site: Susquehanna  Talen Energy icon.png
Issue date: 04/30/1984
From: Kenyon B, Kuczynski L
PENNSYLVANIA POWER & LIGHT CO.
To: Beebe M
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-2195, NUDOCS 8406070185
Download: ML20091K741 (18)
v • d • e


Text

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

[ AVERAGE DAILY UNIT POWER LEVEL D

g , , , , , 3 DOCKET NO. 50-387 L, "% UNIT one N/ O DATE May 9, 1984 Y

07 gi COMPLETED BY L.A. Kuczynski TELEPHONE (717)542-3759 MOPf!H April, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 980 37 924 1,057 gg 847 2

3 1,059 39 844 4 1,057 921 20 5 1.051 21 1.055 6 1.058 1,054 22 7 1,053 1,057 23 g 1,008 1,057 24 9 1,058 25 1,055 10 1,059 1,052 26 gg 1,057 1,048 27 12 1.055 28 1,046 13 1.053 29 983 14 601 30 1,043 15 817 31 _

16 1,023 INSTRUCIlONS 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) g6070185840430 R ADOCK 05000387 L/

PDR C.Ul

ANN 4

,v t +Y

\

s

= /s --- -

3 L Pt_L _ __HII1M J OPERATING DATA REPORT N PPat N 50-387 I DOCKET NO.

Q DATE Mav 9. 1984 COMPLETED BY L.A. Kuczynski RfC c6 '

TELEPHONE (717)542-3759 OPERATING STATUS Unit 1 Notes

1. Unit Name: Sumuchanna steam Electric Station
2. Reporting Period: April, 1984 3,293
3. Licensed Thermal Power (MWt):
4. Nameplate Rating (Gross MWe): 1.152 1,065
5. Design Electrical Rating (Net MWe):

1,068

6. Maximum Dependable Capacity (Gross MWe):

1,032

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 j This Month Yr. to-Date Cumulative 719 2,903 7,872
11. Hours In Reporting Period
12. Number Of Hours Reactor Was Critical 719 1.153 4,998.3
13. Reactor Reserve Shutdown Hours 0 0 156.7 719 1,075.8 4,844.I
14. Hours Generator On-Line
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 2.255.077 3,055,110
  • 14,316,771
  • 745,490 998,240 4,664,790
17. Gross Electrical Ecergy Generated (MWH) 719,795 960,716 4,497,089
18. Net Electrical Energy Generated (MWH)
19. Unit Service Factor 100 37.1 61.5
20. Unit Availability Factor 100 37.I 61.5
21. Unit Capacity Factor (Using MDC Net) 97.0 32.1 55.4
22. Unit Capacity Factor (Using DER Net) 94.0 31.1 53.6
23. Unit Forced Outage Rate 0 34.2 18.1
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: UA
26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIA L CRITICALITY 1 INITIAL ELECTRICITY COMMERCIAL OPERATION
  • Updated Figures Better data became available.

fNA O 7 -

x .

%f&f ,, g UNIT SHUTDOWNS AND POWER REDUC 110NS DOCKET NO. 50-387 UNITNAME One .

p(p 30 DATE May 9, 1984 pgIC COMPLETED BY L.A. Kuczynski REPORT MONTH April, 1984 TELEPHONE (717)542-3759 w.

- B E

-, .! ? }g .E 3 Licensee Eg {% Cause & Corrective

,55

[l No. Date g- E8 Event g? a Action to H $ mV v

$I jgg Report # Prevent Recurrence 3 84n413 S 0 11 4 N/A TC CONROD A power reduction from 100% to 60%

was initialized to change the control rod pattern. No corrective action is required for this power reduction.

It was a planned event.

l l

l l

l 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 Cestriction 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)

7:

L ,

UNIh1

~

SUSQUEHANNA STEAM ELECTRIC STATION Docket Number'50-387 Date May-9, 1984

, Completed.by L.A. Kuczynski. -Telephone (717)S42-3759 Challenges to Main Steam Safety Relief Valves

- None..

Changes to the Offsite Dose Calculation Manual 5 See = Attiachment.

~

n

' Major Cha'ges to Radioactive Waste Treatment Systems None.

s

ATTACHMENT TO UNIT ONE April, 1984, Monthly Operating Report Changes to the Offsite Dose Calculation Manual

c.

't These revised pages were made effective on January 20, 1984 upon signature by the Manager-Nuclear Support.

Changes have been denoted by revision bars in the right margin. The reasons

.for the changes are as follows:

1)' To include setpoints for Service Water and RHR Service Water.

'2). To include setpoint methodology for Vent Flow Rates and SPING Sample Flow Rates.

~ .

PENNSYLVANIA' POWER & LIGHT COMPANY SUSQUEHANNA STEAM ELECTRIC STATION OFFSITE DOSE CALCULATION MANUAL 4

i 4

i Prepared By , , n.#A Date / o!g Y Reviewed By Date / 26[8h PORC Review Requir d Yes No (d Date '

Approved Ey /

Wo Date 12o 8k Madger-NuclearjSupport

.. .~

r

TABLE OF CONTENTS Py 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 SETP01NTS..................................... 7 4/27/83 l~

2.1 LIQUID EFFLUENT M0NITORS.................. 7 4/27/83 8 10/25/83 8b 1/20/84 2.2 CASE 0US EFFLUENT MONITORS................. 9 1/20/84 10 1/20/84 11 1/20/84 12 5/11/82 13 1/20/84 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 GASES...... 17 10/25/83 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 GASES............................... 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 5/11/82 8.0 OPERABILITY OF WASTE TREATEMENT SYSTEMS....... 32 4/27/83 8.1 LIQUID WASTE TREATEMENT................... 32 4/27/83 8.2 GASEOUS WASTE TREATHENT................... 32 4/27/83 33 5/11/82 8.3 SOLID WASTE TREATMENT..................... 34 4/27/83 35 4/27/83

. 36 5/11/82 37 5/11/82 38 5/11/82 1

JAN 201984 i

. ,- w-y+f . T*(A) f MC where F + f = the setpoint dilution factor f

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

Y+(A) = MPCfF + f\

\f / .

Since, by definition, Y > X and Y(A) > X(A), then (c) = I(A) < MPC[F + f

( f a The setpoint concentration (c) can then be converted to a setpoint count rate value by use of the monitor calibration factor.

Setpoint (cpm) = "("i*} (3)

Cal. Factor (pCi/ml per cpm)

The setpoint for the dilution water flow (cooling tower blowdown) is 5000 gpm 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 A.l.1 of Appendix A.

The Service Water System provides screened water from the cooling tower basin for cooling plant systems and equipment.

The Residual Heat Removal (RHR) Service Water System provides water from the Engineered Safeguard Service Water (ESSW) spray pond to the RHR heat exchangers. In post-accident conditions, RHR Service Water can supply water for vessel and containment flooding. The Service Water and RHR Service Water Systems are not normal pathways for liquid effluents. Radiation monitors are in place on these systems to provide indication of leaks across heat exchangers into the service water. The high JAN 201984

- 8b -

~

radiation setpoints for these monitors are set at 2E-5 pCi/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/cc)

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.

2.2 CASEOUS EFFLUENT MONITORS SPECIFIC'ATION 3.3.7.11 - THE RADIOACTIVE CASE 0US EFFLUENT '

MONITORING INSTRUMENTATION CHANNELS SHOWN IN TABLE 3.3.7.11-1 SHALL BE OPERABLE WITH THEIR ALARM / TRIP SETPOINTS SET TO ENSURE THAT THE LIMITS OF SPECIFICATION 3.11.2.1 ARE NOT EXCEEDED. THE ALARM / TRIP SETPOINTS OF THESE CHANNELS SHALL BE DETERMINED IN ACCORDANCE WITH THE METHODOLOGY AND PARAMETERS IN THE ODCli.

Noble gas activity monitors. iodine samplers, and practiculate samplers are present on the reactor building ventilation system (Units 1 and 2), the turbine building ventilation system (Units 1 and 2), and the standby gas treatment system. Effluent system flow rate and sampler flow rate are measured on all of the systems allowing the vent monitor microgrocessor to calculate release rates based on measured flow rates. Precautions, limitations, and setpoints applicable to the operation of the SSES gaseous effluent monitors are provided in the applicable 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:

JAN 201984

o -
1. All expo,are 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 (pCi/sec) derived from site-specific meteorological

. dispersion conditions, vent flow rates, and expected radioiso-topic mixtures in the gaseous effluents. The vent release rate can then ,be converted to cpm depcoding upon the particular monitor's method of operation, sampling rate, and detection -

efficiency. It is not practical to apply alarn/ trip setpoints to integrating radiation monitors sensitive to radiciodines, radioactive materials in particulate form, or radionuclides other than noble gases. Therefore, only the noble gas activity monitors in the five ventilation systems at the SSES will have established setpoints.

The calculated alarm and trip action setpoints for each noble gas ventilation effluent monitor and flow measurement device must satisfy the following equation for whole body dose:

3 500 (4) q, i*

(K )(X/Q)y and by the following equation for skin dose:

- -- - 3000 q, f (5)

(Lg + 1.1 Mg)(X/Q)y JAN 201984 i

- . , l

s where

K g

=

the whole body dose factor due to gamma emissions for each identifieg) l (ares /yr per pCi/m noble gas radionuclide from Table 2 (i) '

Q'iv

=

the release rate of radionuclide (i) from vent

~

(v) which results in an annual dose rate of 500 arem to the whole body or 3000 mrem to the skin -

of the critical receptor.(pCi/sec). i (X/Q)* = the highest calculated annual average relative concentration for estimating the dose to the' critical offsite receptor in an ungestricted area from vent release point (v) (sec/m ).

500 =

the 10 CFR 20 annual whole body dose limit (arem/yr) to an individual in an unrestricted area.

L =

the skin dose factor due to beta emissions.for each identified nogle gas radionuclide (i)

(arem/yr per pCi/m ) from Table 2.

Mg =

the air dose fas.or due to gamma emissions for each identified nogle gas radionuclide .(i) ,.

, (arad/yr per pCi/m ) from Table 2 (conversion constant of 1.1 converts air dose-mrad to skin dose-mrem).

3000 =

the 10 CFR 20 annual skin dose limit (mrem /yr) to an individual in an unrestricted area.

~

Xenon-135 should be the principal noble gas radionuclide released l from the reactor building vents and the standby gas treatment system vent while Xenon-133 should be the principal noble gas

~

radionuclide released from the turbine building vent due to the L . 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 l 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-j ing vent concentration limits can be calculated based on normal i

t vent flow rates:

l Setpoint uCi = iv ('aci/sec) (6) l cc Flow rate (cc/sec)

JAN 201984 L -- A

~

. g Sample calculations for determining release limits for the whole body dose and the skin dose cre given in Section A.l.2 of Appendix A. Also, typical values for flow rates and calibration factor are given for determining the setpoint of the Unit 1 ,

turbine building vent gaseous effluent monitor.

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 rates.

9 e

~

, , *

  • 9 _w JAN 201984

AVERAGE DAILY UNIT POWER LEVEL Q )

E ft), .... 3 DOCKET NO. 50-388 L. .- u '

UNIT Two g d DAR May 9, 1984 k Ib CCMPLEED BY L.A. Kuczynski TELEPHONE (717)S42-3759 MONTH April, 1984 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1

0. g7 0 0 0 2 18 3 0 39 0 4 0 0 20 5 0 21 0

6 0 0 22 7 0 B 0 8 0 y 0 9 0 25 0 10 0 26 0

11 27 0 l

0 0 12 28 13 0 29 0

0 0 14 30 15 0 3, 16 U 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.

(9/*7)

kNN4 g g f+7 Q v

~ ~ ~ ~ ' <

Lht L - N o OPERATING DATA REPORT

DOCKET NO. 50-388 O

4 DATE May 9. 1984 O T. A . Kunzynski RIC $ COMPLETED BY TELEPHONE (7171542-3759 OPERATING STATUS Unit 2 Notes

1. Unit Name: Su scu nh ann n "rnnm F1nnerin 9tnrinn
2. Reporting Period: Antti, 1984
  • To be determined.

Fuel 'oad completed

3. Licensed Thermal Power (MWt): 3'.293 AP ril 13, 1984
4. Nameplate Rating (Gross MWe): 1 159
5. Design El .trical Rating (Net MWe): 1.065
  • 6. Maximum Dependable Capacity (Gross MWe):
  • 7. Maximum Dependable Capacity (Net MWe): -
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, uise Reasons:

None

9. Power Level To Which Restricted,if Any (Net MWe): 0
10. Reasons For Restrictions,If Any: License restriction to 5% full power (164.6-MWt).

Turbinn ennnrnent will nnt hn nynnbrnnivnd ne nr hni nu 5 5' n nun r .

(

This Month Yr..to-Dare Cumulative

11. Hours in Reporting Period 0 n 0
12. Number Of Hours Re:ctor Was Critical 0 0 0
13. Reactor Reserve Shutdown Hours 0 0 0
14. Hours Generator On-Line 0 0 0
15. Unit Reserve Shutdown Hours n 0 0 <
16. Gross Thermal Energy Generated (MWH) 0 0 0
17. Gross Electrical Energy Genersted (MWH) 0 0 0
18. Net Electrical Energy Generated (MWH) 0 0 0
19. Unit Service Factor N/A N/A N/A
20. Unit Availability Factor N/A N/A N/A
21. Unit Capacity Factor (Using MDC Net) N/A N/A N/A
22. Unit Capacity Factor (Using DER Net) N/A N/A N/A
23. Unit Forced Outage Rate N/A N/A N/A
24. Shutdowns Scheduled Over Next 6 Months (Type, Date,and Duration of Eacht:

Maintenance Outage, 10/27/84, 7 weeks

25. If Shut Down At End Of Report Period, Estimated Date of Startup:
26. Units in Test Status (Prior to Commercial Operation): Forecast Achiesed INITIAL CRITICALITY 05/09/84 05/OR/R4 INITIAL ELECTRICITY 06/07/84 COMMERCI AL OPERATION 12/31/84 (4/77)

-\

2 @

e

  • 3 s '

SU l ao

s. a 3

y

~]

5 E h Ken ,

%~ =,h 1 3'

7 - 4,

'd 3'04 g

= O 7' m C M P F Type l 6 > c.o

- 6 x xn E.m n ue- =

,5,,g. 21_;. oe 5..E. o 8 g g. [ { E Duration 4_ g ;; ya,E' ga y g (Hours) me

~e ==ac 2

m "E

> -. 33 -n Reason ,

.!'l CS T

~'

C E= Method ol' 5- H.-

- N = Shutting e 2

7

=

Down Reactor 3 q w

a. m 2 C

a m 1

- N x r

.a T g-3 5 i

= i caEgm w

  • g 2 n n o >

2 q Z w 2 C o

2 4 Y ':J-I System 3 6>EE2 Code 4 1

  • l GEg37 - N cc3 a c 8.

E. e. -

N m

m2m 3 0 4 n' Q Component

  • C E&3 Code 5 Q "E-=

o2 w.

vi 4 O m Ommpm

? O Q g  %*g .C 5 Ea$#5

-Ew ?s @>N rh Hg 30 s

= x ma = =a,2 E3 Cn M zy 4520 C )e h ZWMK 2 c2E' C u = g 5' 3*E m *4 m m .o 5

o =r" c, ,n n, 3 e *

^ M Z H tav w m *

  • N . m C O C Me U4C2 g -- w > A O t c ..  % i)
a. mm-8

= =- -

u x .e 2

% & V C

=

2 N o --

i N @

C W 4 %

M N 3 &

m V A '

Q @ M'

. +

Y e

e' s

y -.

g .,

. .s UNIT 2 SUSQUEHANNA STEAM ELECTRIC STATION

- Docket Number 50-388 ~ Date May 9, 1984

~

- Completed by L.A. Kuczynski Telephone (717)S42-3759 Challenges to Main Steam Safety Relief Valves None.

Changes-to the Offsite Dose Calculation Manual None.'

t

-Major Changes to' Radioactive Waste Treatment Systems

. None.-

e

+

=

1

- g -

..r... , -- w- g..p y- , -,.,-svv ,w,. -.,,,,,,,-,,,-,,.w.,n-, ,,c.,%-,emi,,_,_pemy,,-.~e vn -+ n,+-r.-e+,+,. - ww r<

2.- . , ,

PPaL Pennsylvania Power & Light Company Two North Ninth Street

  • Allentown, PA 18101
  • 215 I 770 5151 Bruce D. Kenyon Vice President-Nuclear Operations 215/770-7502 MAY l11984 Director, Data Automation &

Management Information Division Attention: Mr. M. R. Beebe Management Information Branch Office of Resource Management U.S. Nuclear Regulatcry Commission

-Washington,-D.C. 20555 SUSQUEHANNA STEAM ELECTRIC STATION MONTHLY OPERATING REPORT ER 100450 FILE 841 Docket Nos. 50-387 PLA-2195 50-388

Dear Mr. Beebe:

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

.Very truly yours, B. D. Ken Vice President-Nuclear Operations Attachment ec: 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 Environ.nental 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 S ' >, <

l

Retrieved from "https://kanterella.com/w/index.php?title=PLA-2195,_Monthly_Operating_Repts_for_Apr_1984&oldid=3493393"