PLA-2624, Monthly Operating Repts for Mar 1986

Monthly Operating Repts for Mar 1986

ML20206E089
Person / Time
Site:	Susquehanna
Issue date:	03/31/1986
From:	Keiser H, Kuczynski L PENNSYLVANIA POWER & LIGHT CO.
To:	Beebe M NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
PLA-2624, NUDOCS 8606230086
Download: ML20206E089 (10)

Text

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N y 4@ AVERAGE DAILY UNIT POWER LEVEL Y j D \ 50-387 U DOCKET NO.

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D 03/86 COMPLETED BYL.A. Kuczynski RfC 5 TELEPHONE (717) 542-3759 MOttyy March, 1986 9

DAY AVERAGE DAIL'. ?OWER LEVEL DAY AVERAGE DAILY PCWER LEVEL (MWe Net) ggwg 1 0 17 0 l 0

2 gg 0 0 g, 0 3 ,

4 0 20 0 5 0 0 21 0 o 6 u 0

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8 0 24 0 9

0 0 3

10 0 26 0 11 0 0 27 0 0 12 28 13 29 0 14 0 0 30

- 0 0 15 3, 16 0 INS'TRUCTIONS 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.

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tN. .R*, J OPERATING DATA REPORT 50-387 0 DOCKET NO.

O DATE 4/03/86 1 I

COMPLETED BY L. A. Kuczynski RfC s@4s TELEPHONE (7171 542-3759 OPERATING STATUS Unit 1 N 5

1. Unit Name: su - h - n monm vinceric m,e i m March, 1986

2. Reporting Period:

3293

3. Licensed Thermal Power (MWt):

1152

4. Nameplate Rating (Gross MWe):

1065

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe): ' rmn

7. Maximum Dependsble 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 Rcstricted. lf Any (Net MWe): None

10. Reasons For Restrictions,if Any: None This Month Yr..to Date Cumulative 744 2,160 24,E73

11. Hours in Reporting Period 0 1,081.8 17,073

12. Number Of Hours Reactor Was Criticai

13. Reactor Reserve Shutdawn Hours 0 0 710.6

14. Hours Generator On_Line 0 1,081 16,699.8

15. Unit Reserve Shutdown Hours 0 0 0 0 3,420,677 51,008,002

16. Gross Thermal Energy Generated (MWH)

U 1,118,896 16,617,888

17. Gross Electrical Energy Generated (MWH)

- 8,954 _1,u63,670 15,908,408

18. Net Electrical Energy Generated (MWH)

19. Unit Service Factor 0.0 9o.O s i 7_

20 Unit Availability Factor 0.0 50.0 67.7 -

21. Unit Capacity Factor (Using MDC Net) 0.0 47.7 62.5 0.0 46.2 60.5

22. Unit Capacity Factor (Using DER Net) 0.0 0.0 10.6

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each r None

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

May 9, 1986

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION to/77)

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UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-197 .

,, UNIT NAME nna h DATE 04/03/86 COMPLETED gy L.A. Kuczynski g

O?NIC gg REPORT MONTH March, 1986 TELEPHONE (717) 542-3759 i-n.

- E c No.

, !2 }q }_g g$3 Licensee [c-t, f, Caese & Corrective Date i 3g 5 Event  ;; 7 o-3 Action to H

$E' 5 e

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~ Report a rN U !O Prevent Recurrence

! O c5 3 860215 S 744 C 4 NA ZZ ZZZZZZ Manual scram to commence second refueling outage.

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)

E-Operator Training & License Examination from previous month F-Administrative i G-Operational Error (Explain) 5-Reduction Exhibit I . Same Source (9/77) Il-Oiher (E xplain) 9-0ther

, UNIT 1' SUSQUEHANNA STEAM ELECTRIC STATION

' Docket Number 50-387 Date 04/03/86 Completed by L.A. Kuczynski Telephone (717) 542-3759 Challenges to Main Steam Safety Relief Valves None Changes to the Offsite Dose Calculation Manual None Major Changes to Radioactive Waste Treatment Systems None l

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gN4 @7 n AVERAGE DAILY UNIT POWER LEVEL D }

50-388 DOCKET NO.

f d UNIT Two 6 g DATE 04/03/86 be COMPLETED sy L.A. Kuczynski klC Bi TELEPHONE (717) 542-3759 MONTH March, 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) l 1.050 17 1,050 2 1,050 gg 1,046 1,052 1,033 3 g, ,

4 1.051 20 1,037 3

1,050 1,035 21 6

1,050 918 7 1 047 23 1,043 3 734 1,050 24 9

999 1,047 3

10 1,046 1,036 26 gg 1,047 y 1,047 1,052 1,050 12 33 1,050 1,044 29 1,048 1,038 14 30 1,045 1,045 15 16 1,049 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 megawstt.

(9/77)

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CZJ OPERATING DATA REPORT Y Q N 50-388

[ DOCKET NO.

DATE 04/03/86 h'pRfCSih C COMPLETED BY L. A. Kuczynski TELEPHONE (7171 542-3759 OPERATING STATUS Unit 2 Susquehanna Steam Electric Station Notes

1. Unit Name:

2. Reporting Period: March, 1986 3293

3. Licensed Theimal Power (MWt):

1152

4. Nameplate Rat.:ng (Gross MWe):

065

5. Design Electrical Rating (Net MWe):

6. Maximu n Dependable Capacity (Gross MWe): 106A

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. lf Any (Net MWe): None

10. Reasons For Restrictio.1s If Any: None This Month Yr. to.Date Cumulative 744 2,160 9,912

11. Hours in Reporting Period 744 2,066.6 9,187.8

12. Number Of Hours Reactor Wss Critical

13. Reactor Reserve Shutdown Hours 0 133.6 717.9

. 14. Hours Generator On.Line 744 2,001.6 8,996.7

15. Unit Reserve Shutdown Hours 0 0 0 2,391,025 6,342,704 28,373,502

16. Gross Thermal Energy Generated (MWH)

/92,504 2,098,266 9,311,066

17. Gross Electrical Energy Generated (MWH)

18. Net Electrical Energy Generated (MWH) 766.473  ?.n?4.919 a.97s.529

19. Unit Service Factor 100.0 92.7 90.s

20. Unit Availability Factor 100.0 92.7 90.8 99.8 90.8 87.8

21. Unit Capacity Factor (Using MDC Net) 96.7 88 85.0

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 0.0 71 9.2

24. Shutdowns Scheduled Over Next 6 Months (Type.Date,and Duration of Each1:

Refunlina Outnane Aucunt 2. 19A6 A4 rinv n

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 CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION (o/77)

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K I DOCKET NO. 50-388 ,

UNIT SHUTDOWNS AND POWER REDUCTIONS U N

$@, @ UNIT NAME 04/03/86 DATE )

NIC M REPORT MONTH vm b - 14An COMPLETED BY L A- Kuczynski TELEPHONE (7171 54'>-17s4 e

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- E E 5E }; E3 No. Date g 3g }g5

_g Licensee Event

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gn, n-Cause & Corrective Action to F

$E 5 Report # <N C j5g c5 f'3 Prevent Recurrence 4 860308 S 0 F 5 NA ZZ ZZZZZZ Power reduction for control rod se-quence exchange, reactor recirculator pump motor generator set brush change-out and main turbine valve testing.

I 2 3 4 F: Forced Reason: Method:

S: Scheduled Exhibit G - Instructions A Equipment Failure (Explain) I-Manual for Preparation of Data B-Maintenance of Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automativ Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Continuation 0161)

E-Operator Training & License Examination from previous month F-Administ rative i G-Operational Error (Explain) 5-Reduction Exhibit 1 - Same Source (9/77) li-Ot her (Explain) 9-Other

. ' -' f UNIT 2 SUSQUEHANNA STEAM ELECTRIC STATION Docket Number 50-388 Date 04/03/86 Completed by L. A. Kuczynski Telephone (717) 542-3759 Challenges to Main Steam Safety Relief Valves None Changes to the Offsite Dose Calculation Manual None Major Changes to Radioactive Waste Treatment Systems None t'

4

REFUELING INFOR'fATION

1. Name of facility. Susquehanna SES - Unit 1

2. Scheduled date for next. refueling shutdown. 9-5-87

3. Scheduled date for restart following refueling. 11-20-87

4. Will refueling or resu=ption 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, MCPR Spec. , MAPLHGR Spec. , LHGR Spec. , New ' fuel bundle enrichment' andGadolinia design' __

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15 . Scheduled date(s) for submitting proposed licensing action and supporting information. 7-20-87

6. Important licensing considerations associated w'.th refueling, e.g.,

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

First Reload of Exxon 9x9 fuel in Unit 1.

Unit 2 will have received its first reload of 9x9 prior to Unit 1 in the f all of 1986.

7. The number of fuel asse=blies (a) in the core and (b) in the spent fuel storage pool. a)_ _ 764 b) 488

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 size 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: 2000*

• 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 ,(1/2 x 764) = 2458 available capacity per pool.

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

7-

.- PPat Pennsylvania Power & Light Company Two North Ninth Street

• Allentown, PA 18101 = 215 / 770 5151 Hanald VV. Keiser Vice President-Nuclear Operations 215/770-7502 APR 111986 Director, Data Automation &

Management Information Division Attention: Mr. M. n. 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-2624 FILE R41-2A 50-388/NPF-22

Dear Mr. Beebe:

The March 1986 monthly operating reports for Susquehanna SES Units 1 and 2 are attached. Updated refueling information is also provided for Unit 1.

Very truly yours, f

b M 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 Desk (12 copies)

Mr. R. H. Jacobs - NRC Ms. M. J. Campagnone - NRC 6

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