PLA-2442, Monthly Operating Repts for Mar 1985

Monthly Operating Repts for Mar 1985

ML20129H964
Person / Time
Site:	Susquehanna
Issue date:	03/31/1985
From:	Kenyon B, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-2442, NUDOCS 8506070702
Download: ML20129H964 (11)

Text

n .

N4 AVERAGE DAILY UNIT POWER LEVEL 4

D )

M .--- I DOCKET NO. 50-387 L: "4 UNIT One j T4 DATE April 9, 1985

?gg gi COMPLETED BY L.A. Kuczynski TELEPHONE 7 7-542-3759 MON'!H March, 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe. Net) (MWe Net) 1 0 0 37 2

0 gg 0 0 g, 0 3 _

4 0 0 20 5

0 0 21 6

0 y 0 7 D 0 -

8 0 0 3

9 0 y 0 10 0 0 26 0 0 11 27 12 0 0 28 13 0 0 29 0 0 14 30 -.

0 0 15 3g 0

16 IN51RUC110NS 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.

(9/77) 8506070702 850331 1 PDR ADOCK 05000387 O 1

R PDil 3 (L Vy

pg%  %

i !D Q

/ 7 m .____ K L S-. - ~ MJ OPERATING DATA REPORT DOCKET NO. 50-387 DATE Aoril 9. 1985 COMPLETED BY L.A. Kuczynski IC TELEPHONE 717-542-3759 OPERATING STATUS Unit 1 Susquehanna Steam Electric Station Notes

1. Unit Name:

2. Reporting Period: March. 1985

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 1065

6. Maximum Dependable Capacity (Gross MWe): 1068

7. Maximum Dependable Capacity (Net MWe): 1032 .

8. If Changes Occur in Capscity 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.lf Any: None This Month Yr..to.Date Cumulative

11. Hours In Reporting Period 744 2,160 15,913

12. Number Of Hours Reactor Was Critical 0 896 11,288.7

13. Reactor Reserve Shutdown Hours 0 41.8 513 2

14. Hours Generator On-Line 0 883.9 11,030.8

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 2.529.543 33.158.531

17. Gross Electrical Energy Generated (MWH) 0 823,150 10,813,680

18. Net Electrical Energy Generated (MWH) - 5.682 774,140 10,354,710

19. Unit Service Factor 0 40.9 69 3

20. Unit Availability Factor 0 40.9 69 3

21. Unit Capacity Factor (Using MDC Net) 0 34.7 63.0

22. Unit Capacity Factor (Using DER Net) 0 33.6 61.1

23. Unit Forced Outage Rate 0 5.8 13.4

24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Eacht:

None

25. If Shut Down At End Of Report Period. Estimated Date of Startup: June 13. 1985

26. Units in Test Status (Prior to Commercial Operation). Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPER ATION (9/77)

4 r > .

-f -h I, y t UNIT SHUTDOWNS AND POWER REDUCI10NS DOCKET NO. 50-387 g UNIT NAME One DATE April 9. 1985 f COMPLETED BY L.A. Kuczynski I43C N REPORTMONTH March. 1985 TELEPHONE 717-542-3759 n.

- E c

, 3? 3 yI5 Licensee E-r, gn, Cause & Corrective No. Ihte t 3g s .g 5 5 Event p Action to H

$2 5 j;gg Report a mu g{ Prevent Recurrence d

2 850209 5 744 C 4 NA NA NA Manual scram to commence first refueling outage.

I 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Da'a 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 Examinatio'n from previous month F-Administrative 5-Reduction 5

- G-Operational Error (Explain) Exhibit I- Same Source (9/77) II-Other (Explain) 9-Other P

REFUELING INFORMATION l 1.. Name of facility. Susquehanna SES - Unit 1

2. Scheduled date for next refueling shutdown. 2-15-86

3. Scheduled date for restart following refueling. 5-9-86

4. Will refueling or resumption of operation thereafter require a L

technical specification change or other license amendment?

l If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design and core configuration

. been . reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

~ Yes. MCPR Soec. . MAPLHGR Spec. , New ' fuel bundle enrichment' and

'Cadolinia design'.

5. Scheduled date(s) for submitting proposed licensing action and supporting information. 1-9-86

6. Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design,.

new operating procedures.

None

'7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 764* b) 192*

• following current refueling outage

- 8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

present 2840 increase sise by 0

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

DATE: 2001**

• • based on: 1) both pools (Units 1 & 2) are available for both units and capable of being shared.

2) must be able to offload one full core between both pools -

i.e. 2840 $/2 x 764)s 2458 available capacity per pool.

3) assumes use of high burnup fuel designs in 18 month cycles.

UNIT 1

~

SUSQUEHANNA STEAM ELECTRIC STATION Docket Number 50-387 Date April 9,1985

-Completed by L.A. Kuczynski Telephone 717-542-3759 Challenges to Main Steam Safety Relief Valves None Changes to the Offsite Dose Calculations Manual None Major Changes to Radioactive Waste Treatment Systems

.None

N4 4 AVERAGE DAILY UNIT POWER LEVEL

/ l

@ .--- E DOCKET NO. 50-388 l Tm L' '

UNIT Two

< 0 gg73 April 9, 1985

?gg efTh COMPLETED BY L.A. Kuczynski TELEPHONE 717-542-3759 MON 11g March. 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MW'-Net) (MWe-Neo I 1057 17 1057 2 1057 Is 1057 3 1059 19 1055 _

4 1058 20 1006 5 1059 21 132 6 1059 0 22 7 1059 23 0 g 1055 24 0 9 1058 25 0 to 1056 26 648

1057 27 941 12 1056 1041 28 13 1056 29 1040 34 1057 30 818 15 1059 3, 835 16 1058 INSTRUC110NS On this format.11st the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole rnegawatt.

(4/77)

A% -

D hl v /

D Y

Z T_T" 3 A -. C ".n j OPERATING DATA REPORT b Q DOCKET NO. 50-388 DATE April 9. 1985 p kgg [ M COMPLETED BY L.A. KuczynskI TELEPHONE 717-542-3759 OPERATING STATUS Unit 2 Notes

1. Unit Name: Susquehanna Steam Electric Station

2. Reporting Period: March. 1985

3. Licensed Thermal Power (MWt): 3293

4. Nameplate Rating (Gross MWe): 1152

5. Design Electrical Rating (Net MWe): 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 %hich Restricted.lf Any (Net MWe): None

10. Reasons For Restrictions.If Any: None This Month Yr. to Date Cumulatise

11. Hours In Reporting Period 744 1.152 1.152

12. Number Of Hours Reactor Was Critical 661.9 1.069.9 1.069 9

13. Reactor Reserve Shutdown Hours 82.1 82.1 82.1

14. Hours Generator On Line 640.1 1.048.1 1.048.1

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 2.005.496 3.299.245 3.299.245

17. Gross Electrical Energy Generated (MWH) 659.968 1.087.414 1.087.414

18. Net Electrical Energy Generated (MWH) 636.089 1.049.147 1.049.147

19. Unit Service Factor 86.0 91 91

20. Unit Availability Factor 86.0 91 91

21. Unit Capacity Factor (Using MDC Net) 82.8 88.2 88.2

22. Unit Capacity Factor (Using DER Net) 80.3 85.5 85.5

23. Unit Forced Outage Rate 14.0 9.0 9.0

24. Shutdowns Scheduled Over Next 6 Months tType. Date,and Duration of Each t:

None

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

26. Units in Test Status (Prior to Commercial Operationi: Forecast Achie$ed INITIAL CRITICALITY INITIAL ELECTRICITY CO\tMERCIAL OPER ATION (51/ 7 7 )

7 4

, I %8 t ,

Lh it UNIT SHUTDOWNS AND POWER REDUCTIONS DOCET NO. 50-388 g R UNIT NAME Two DATE Apri1 9. 1985 COMPLETED BY L.A. Kuczynski I4fC 5 REPORT MONTH Ma rch , 1985 TELEPHONE 717-542-3759 e.

- E E jE "g Date g 3g (

jY3 jg5 Licensee Event E-r, g'2

% ~ Cause & Corrective Action to pO

$= 5 j di g Report a mO g Prevent Recurrence c5 6 850321 F 103.9 A 2 85-013-00 HA/HH PIPEXX The reactor was scrammed (following a

• power reduction to 14% to repair a stator cooling water leak) to f acili-tate repairs of a leak in the conden-sate system. The stator cooling water leak was reduced to approximately 2 drops / minute af ter the application of a special epoxy to the cooling water line to the generator neutral phase bushing. The condensate system leak was repaired and the Unit returned to service.

7 850329 F 0 A 5 NA CH INSTRU Power reduction for Reactor Feed Pump

'C' flow element flange leak repair.

I 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) I-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 Goperational Errur IExplain) Exhibit I- Same Source tyn) Il-Other (Explain) 9-Other

p .

REFUELING INFORMATION

1. Name of facility. Susquehanna SES - Unit 2

2. Scheduled date for nexc refueling shutdown. 8-2-86

3. Scheduled date for restart following refueling. 11-14-86

4. Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?

Yes, Possibly Safety Limit MCPR, Reactivity Anomaly Spec.' MCPR Spec.,

MAPLHCR Faec. , APRM Setpoints Spec. . LHGR Spec. , EOC RPT Instrumentation Snec. Snent Fuel Pool Criticality Reanalysis. Possible channes to Tech Spec. Design features section also.

~

5. Scheduled date(s) for submitting proposed licensing action and supporting information. 7-17-86

6. Important licensing considerations associated with refueling, e.g. ,

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

Use of Exxon's new 9 x 9 fuel desinn. Will involve sienificant changes in fuel bundle mechanical & nuclear design.

7. The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool. a) 764 b) 0 l S. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies.

2840 increase size by 0 present

9. The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed espacity.

DATE: 2001*

• based on: 1) both pools (Units 1 & 2) are available for both units and capable of being shared.

2) must be able to of fload one full core between both pools -

.' i.e. 2840 - 1/2 x 764)= 2458 availabic capacity per pool.

3) assumes use o high burnup fuel designs in 18 month cycles.

. . . r. ' *

[ , ,

T +

UNIT 2

'SUSQUEHANNA STEAM ELECTRIC STATION

~ Docket Number 50-388 Date April 9,1985 Completed by L. A. - Kuczynski' Telephone 717-542-3759 t .

Challenges to Main Steam Safety Relief Valves None

-Changes to' the Of f site Dose Calculation Manual None

' Major Changes to Radioactive Waste Treatment Systems None t

i i

ty PPat Pennsylvania Power & Light Company Two North Ninth Street

• Allentown, PA 18101

• 215 / 770'5151

' Bruce D. Kenyon

Vice President-Nuclear Operations 215/770-7502 APR 151985 Director, Data Automatitan &

Management Information Division Attention: Mr. M. R. Beebe Management Information Branch Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20553 SUSQUEHANNA STEAM ELECTRIC STATION MONTHLY OPERATING REPORTS ER 100450 FILE 841 Docket Nos. 50-387/NPF-14 PLA-2442 50-388/NPF-22 '

Dear Mr. Beebe:

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

This month's reportn include updated refueling information.

Very truly yours, mB. D. Kenyo Vice President-Nuclear Operations Attachment cc: Dr. Thomas E. Murley Regional Adsinistrator-Region 1

! U.S.' Nuclear Regulatory Commissica 631 Park Avonue King of Prussia, PA 19406 Director Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C. 20555

' Attnt- Document: Control Desk (12 copfes)

Mr. R. H. Jacobs - NRC Ms. M. J. Campagnone - NRC /[ '

-t I l

!