PLA-2853, Monthly Operating Repts for Apr 1987

Monthly Operating Repts for Apr 1987

ML20214D701
Person / Time
Site:	Susquehanna
Issue date:	04/30/1987
From:	Hirt J, Keiser H PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC
References
PLA-2853, NUDOCS 8705210435
Download: ML20214D701 (12)

Text

^

f AVERAGE DAILY UNIT POWER LEVEL Q }

$ 50-187 rf). , , , _ _ DOCKET NO.

L UNIT One

< 0 DAir s/6/87

.A. IEd O?RIC SY C MPLETED BY

~

TELEPHONE MONDI April,1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net) (MWe-Net) g 1043 ,7 0 2

323 ,, o 3

0 l9 m

4 0 20 802 5 0 23 947 6 0 1028 22 0 1031 7 23 g 0 1031 9 0 25 1039 10 0 1040 26 0 1042 ll 27 305 1042 12 3 13 871 29 1039 34 900 30 1041 15 1022 3, 26

! 16 INSTRUC110NS 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) 8705210435 870430

~

{DR ADOCK 05000387 PDR N ll

ANy gN

>h s

t - - - - - ~mJ OPERATING DATA REPORT 50-387 C \ DOCKET NO.

k M DATE D /87 COMPLETED BY J.A. Hirt NIC fCN TELEPHONE '7171 942-3917 OPERATING STATUS Unit One i Suschehanna Steam Electric Station 50 t" l

1. Unit Name:

2. Reporting Penod:

April, 1987

3. Licensed Thermal Power IMWt p: 3293 -

1152

4. Nameplate Rating (Gross MWel:

1065 j

5. Design Electrical Rating (Net MWel:

6. Maximum Dependable Capacity (Gross MWe): 1n69 '.

7. Maximum Dependable Capacity (Net MWel: 1032 I

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

None None -

9. Power Level To which Restricted. lf Any INet MWep:

10. Reasons For Restrictions. If Any: N/A This Month Yr..to.Date Cumulaine

11. Hours In Reporting Period ~71 o 9;R70 la ,19?

12. Number Of Hours Reactor Was Critical 427.0 2.597 24.174.5

13. Reactor Reserve Shutdown Hours 0 0 812.7

14. Hours Generator On.Line 399.8 2,559.8 24,173.8 0 0 0

15. Unit Reserve Shutdown Hours 1,201,220 8,014,363 74,297,501

16. Gross Thermal Energy Generated (MWH p 391,626 2,622,874 24,210,412 17 Gross Electrical Energy Generated IMWH1

18. Net Electrical Energy Generated IMWH) 177.19? 9.99R.61a 91.?na.661 l 19. Unit Service Factor 99.6 R R () 70.8 l 20. Unit Availability Factor 55.6 _

88.9 70.8

21. Unit Capacity Factor IUsing MDC Net) 50.9 _

85.1 65.8

22. Unit Capacity Factor IUsing DER Nett 49.3 _

82.5 63.8 l 11.1 11.2

23. Unit Forced Outage Rate 44.4

24. Shutdowns Scheduled Over Next 6 MonthsITvoe. Date and Duration of Eaen

! A Refuelina Outaae is schMu1M to recin SentemMr 5,19.87 and end November 20, 1987. Expected duration is 76 days.

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

26. Units in Test Status aPrior to Commercial Operations: Forecast Achiesed INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION p-i e

q@NNA '

3 Pfi[8f[4 ,

I k UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. Sn-1R7 e UNIT NAME RW-Uni t Opg_

p DATE 9/6/R7 gIC gg REPORT MONTH April, 1987 COMPLETED BY d*^- Mt TELEPHONE (717) 542-3917

. "E -

e n .3 eo s Licensee

- g*

No. Date g

.2 _r 3g 8

gs4

,c gg Event c 't.,

ug go Cause & Corrective F

o.'E Action to

$5 5 j di g Report # <N 0 V Prevent Recurrence 5

2 870402 F 236.2 A 3 87-013-00 SK Cang On April 2,1987 an autanatic actua-tion of the reactor protection systen occurred. The reason for the Scram was high reactor water level caused by a near-instantaneous failure in the feedwater m ntrol circuitry. The failure caused the feedwater punps to increase resulting in the high level. The failed canponent was replaced.

3 870416 F 83.0 A 1 87-014-00 XX ISV On April 15, 1987 at 2315 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.808575e-4 months <br /> a controlled plant shutdown was initiated as required by Technical Specification 3.6.1.1. During the performance of a local Icak Rate Test (LLRP), plant personnel were unable to establish test pressure within the ILRP bourvbry. This 1 2 3 4 F: Forced Reason: Method:

S: Scheduled Exhibit G-Instructions 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-Administrative 5 G-Operational Error (Explain) 5-Reduction Exhibit I - Same Source W/77) IIOther (Explain) 9-Other

gANN4 .

4 2 F8h~\r N UNIT SHUTDOWNS AND POWER REDUCTIONS '

-unit une N E (f. DATE 5/6/87 I4fC N REPORT MONTH Acril . 19R7 C HDW LA. h TELEPHONE (717) 542-3917 e.

• w B E No.

c.

.! E }n I5 Licensee Et,, ,, Cause & Corrective Date 5g ,c s 5 Event g? {*3 c- Action to F

$5 5 }<> $ g Report # mO

[U Prevent Recurrence S

3 (Continued frcxn previous page) resulted in primary contairment integrity being in question. The unit cxxnpleted the shutdown at 0245 hours0.00284 days <br />0.0681 hours <br />4.050926e-4 weeks <br />9.32225e-5 months <br /> on April 16th. Plant personnel reworked the affected valve and reduced the leakage to within accep-table limits.

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-Administrative 5 G-Operational Error (Explain) 5-Reduction Exhibit I - Same Source 19/77) llother(Explain) 9-Other 1

p.

-e. -s . s s

c SUSQUEWuta STEAM ELBCTRIC STATION-i DOCKET NLNBER 50-387~ Date 5-6-87'-

Capleted by J.A. HirtiTelephone -(717) ~ 542-3917-

Challenges to Main Steam Safety Relief Valves-See attached Sheet.

Changes to the Offsite Dose Calculation Manual None.:

Major Changes to Radioactive waste Treatment System None..

l y

L In response to the April 2,1987 scram frcan 100% power four safety relief valves (SWs): lifted and reseated successfully. Listed below are the times

- and pressures at which the SWs opened and closed.

TIME PRESSURE SW OPEN CIOSE OPEN GDSE (Hrs: Min: Sec:) (Hrs: Min: Sec:) (PSIG) (PSIG)-

E 07:26:17 07:26:23 1047 984 B- 07:26:15 07:26:23 1070 984 A 07:26:15 07:26:19 1070 1030 H 07:26:15 07:26:17 1070 1047

_ ___ _ _____ _ ___________________. _______ ___l

[ g AVERAGE DAILY UNIT POWER LEVEL (t) .... 3 DOCKET NO.

50-388 L "J -

UNIT 0 5/6/87 f+ # DATE

-_J.A. Hirt

?RIC SY COMPLETED BY TELEPHONE (717) 542-3917 April,1987 Mo m DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

I 1056 37 0-2 1055 18 0 3 1056 g, 0 4 1051 0 20 1053 0 5 ,,

1054 0 6 22 7 1053 23 0 8 1052 24 0

9 1052 6 25 to 00 26 1047 764 11 27 12 1049 28 922 13 1049 1043 29 g4 1048 30 15 1048 33 16 365

INSTRUCTIONS On this format, list the average daily umt power levelin MWe Net for each day in the reportine month. Compute to the nearest whole megawatt.

~

(9/77)

• 6 Atwv4

'y 07 f . .; s t C- - - -,J OPERATING DATA REPORT so

\ DOCxET NO. so-ass DATE 6/87 COMPLETED BY . . Hirt

1. fC @ TELEPHONE (717) 547-3917 OPERATING STATUS Unit 'IWo Susquehanna Stean Electric Station Notes

1. Unit Nm-

2. Reporting Period: U ll' * #

3. Licensed Thermal Power (MWt).

3293  ;

4. Nameplate Rating (Gross MWei:

1152

5. Design Electrual Rating (Net MWe1: 1m ~

IngA

4. Maximum Dependable Capacity qGross MWel: '

7. Maximum Dependable Capacity (Net MWe): 1017

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

None None

9. Power Level To Which Restricted. lf Any (Net MWe):

10. Reasons For Restrictions. If Any: M/A This Month Yr..to-Date Cumulatise 719 2,879 19,391 i1. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 9nA_n 7.An1 19.711

13. Reactor Reserve Shutdown Hours 0 0 717.9

14. Hours Generator On.Line 489.3 2.550.6 15,279.9

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 1,536,086 8,146,772 47,539,657

17. Gross Electrical Energy Generated (MWH) 504,218 2,688,830 15,593,124 487,305 2,596,469 14,998,998

18. Net Electrical Energy Generated (MWH)

D *' O *D *

19. Unit Service Factor

20. Unit Availability Factor 69.1 ,,

AR.6 7R.R

21. Unit Capacity Factor IUsing MDC Net) 65.7 87.4 75.0

22. Unit Capacity FactoriUsing DER Net) 63.6 _

84.7 72.6

23. Unit Forced Outage Rate 31.9 11.4 12.3

24. Shutdowns Scheduled Over Next 6' Months tType. Date.and Duration of Eseh r There are no scheduled shutdowns over the next six nonths.

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

26. Units in Test Status aPrior to Commercial Operation): Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION g.->

D

4gANN4 .

3 F8hf N '

I 50-388

• UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. Sht.s-Unit Two R

Y g UNIT NAME M DATE 5/6/87

1. 4fC N REPORT MONTH Acril,1987 NTED W Mh TELEPHONE (7171 9 d '>-%17

~.

• E

- c

- E ":: 3'j *I5 Licensee Ev E% Cause & Corrective

%. Date

{

I-fl y: 5 3gE Event N

mo h U Action to j di g Report a g Prevent Recurrence

. S 4 870416 F 229,7 H 3 87-006-00 JM ZZZZZZ On April 16, 1987 at 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br /> an autmatic actuation of the reactor protection system occurred due to the spurious closure of the Main Stean Isolation Valves (MSIV) .

Althotgh the cause of the MSIV isola-tion could not be determined, the main stean line low pressure switches are highly suspect due to their proven sensitivity..to external

, disturbances. Protective barriers were installed around the switches to prevent personnel fran inadvertent-ly caning in contact with the switches ,

associated sensor tubing and their structural supports.

i 1 2 3 4 F: Forced Reason: Method:

S: Scheduled Exhibit G-Instructions 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 Administrative S G-Operational Error (Explain) 5-Reduction Exhibit I - Same Source (9/77) IIOther(Explain) 9-Other

, io.. _

SUSQUEHANNA STEAM ELECTRIC STATICN DOCFLT NUMBER 50-388 Date 5-6-87 Capleted by J.A. Hirt Telephone (717) 542-3917 Challenges to Main Steam Safety Relief Valves See attached Sheet..

Changes to the Offsite Dose Calculation Manual None.

Major Changes to Radioactive waste Treatment Systen None.

..e

'Due to the April 16, 1987 scram frca 100% power one safety relief valve (SRV) opened three times._ Listed below are the times and the pressures the SRV lifted and reseated.

TIME PRESSURE OPEN C[OSE OPEN CIOSE (Hrs: Min Secs) (Hrs: Mins: Secs) (PSIG) (PSIG) 08:26:28 08:32:45 1006 723 08:25:25 08:26:11 1067 996 08:23:29 08:24:17 1067 991 e

i i-i-

l'

p e ., .. e Q Pennsylvania Pow r & Light Comp:ny Two North Ninth Street

• Allentown, PA 18101 e 2151T106151 Submitted pursuant to Technical Specifications i Harold W. Keiser Section 6.9.1.6 Vice President-Nucleer Operations 215/770-7502 MAY 151987 5

. 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 Docket Nos. 50-387/NPF-14 PLA-2853 FILE R41-2A 50-388/NPF-22

Dear Mr. Beebe:

The April 1987 monthly operating reports for Susquehanna SES Units 1 and 2 are attached.

Very truly yours, h

2

.H. W. Keiser Vice President-Nuclear Operations Attachment cct Document Control Desk (Original)

NRC Region I Mr. L. R. Plisco - NRC Resident l Mr. M. C. Thadani - NRC Project Manager i

(

l 9Y 9 elt