ML20138P792

Monthly Operating Repts for Nov 1985

ML20138P792
Person / Time
Site:	San Onofre
Issue date:	11/30/1985
From:	Maisel R, Morgan H SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
NUDOCS 8512260260
Download: ML20138P792 (12)

Text

NRC MONTHLY OPERATING REPORT DOCKET N0. 50-361 UNIT SONGS - 2 DATE 12-16-1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 2

2. Reporting Period: November 1985

3. Licensed Thermal Power (MWt): 3390

4. Nameplate Rating (Gross MWe): 1127

5. Design Electrical Rating (Net MWe): 1070

6. Maximum Dependable Capacity (Gross MWe): 1127

7. Maximum Dependable Capacity (Net MWe): 1070

8. If Changes Occur In Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons:

NA

9. Power Level To Which Restricted, If Any (Net MWe): NA

10. Reasons For Restrictions, If Any: NA This Month Yr.-to-Date Cumulative

~11. Hours In Reporting Period 720.00 8,016.00 20,065.00

12. Number Of Hours Reactor Was Critical 195.02 4,601.80 12,247.02

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 194.98 4,497.02 11,989.49

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 619,131.85 14,403,983.13 38,676,686.43

17. Gross Electrical Energy Generated (MWH) 207,060.50 4,815,115.50 13,025,424.00

18. Net Electrical Energy Generated (MWH) 187,475.00 4,525,080.00 12,290,028.00

19. Unit Service Factor 27.08% 56.10% 59.75%

20. Unit Availability Factor 27.08% 56.10% 59.75%

21. Unit Capacity Factor (Using MDC Net) 24.33% 52.76% 57.24%

22. Unit Capacity Factor (Using DER Net) 24.33% 52.76% 57.24%

23. Unit Forced Outage Rate 0.00% 8.25% 5.62%

24. SF *. downs Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling Outage, March 15, 1986, 90 days duration

25. If Shut Down At End Of Report Period, Estimated Date of Startup: 12/4/85

26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY ~

NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA I

7630u

/

8512260260 851130 gDR ADOCK 05000361 PDR

. [ sg l

4 AVERAGE DAILY UNIT POWER LEVEL DOCKET N0. 50-361 UNIT SONGS - 2 DATE 12-16-1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 MONTH November 1985 DAY -~ AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1069.96 17 0.00 2 874.85 -

18 0.00 ,

3 883.42 19 0.00 4 956.08 20 0.00 5 1092.42 21 0.00 6 1098.23 22 0.00 7 1115.10 23 0.00 8 1065.25 __

24 0.00 9 30.15 25 0.00 10 0.00 26 0.00 11 0.00 27 0.00 _

12 0.00 28 0.00 13 0.00 29 0.00 __

'14 0.00 30 0.00 15 0.00

16. 0.00 7630u ,

i

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET No. 50-361 UNIT NAME SONGS - 2 __

REPORT MONTH NOVEMBER 1985' -

DATE 12-10-1VU3 COMPLETED BY R. J. Maiset TELEPHONE (714) 368-6657 Method of Shutting .

Dura t ion Down LER System Component Cause & Corrective 1 2. '3 .4 4 Action to No .' Dato Type (Hours) Reason Reactor No. Code. Code Prevent Recurrence 21 851109' 15 525.02 B 3 85-060 AB PSF Scheduled unit shutdown to repa i r sma l l leak f rom the sea t controt bleed-off line of Reactor Coolant Pump P003.

During the shutdown the reactor tripped at 10% power due to an Axia l Shape Index (ASI) Coro Protection Calculator (CPC) auxi l ia ry trip. Seve ra l alternatives are currently being pursued to minimize ASI events, including utilizing an additional group of control rods, and/or relaxed ASI limitations at reduced power.

The scheduled outage was extended to raplace seal cartridges on all four Raactor Coolant Pumps.

1 2 3 4 F-Fo rced Reason: Method: .lEEE Std 803-1983 S-Scheduled A-Equipment fa ilure (Expla in) 1-Manual B-Ma intenance or Test 2-Manual Sc ra m.

C-Refueling 3-Automatic Scram.

D-Regula tory Restriction 4-Continuation f rom E-Operator Training & Licenso Examination Previous Month F-Admi n i st ra t i ve 5-Reduction of 20%

C-Ope ra t iona l Error (Expla in) or greater in the H-Other ( Expla in) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6-Other ( Expla in) 7630u

_.__.s _ __

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-361 UNIT SONGS - 2 DATE 12-16-1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 Date Time Event November 1 0001 Unit is in Mode 1 at 100% reactor power. Full power operations are planned.

2200 Commenced power reduction to 85% due to saltwater leak indications in the southwest quadrant of main condenser.

November 2 0130 Unit at 85% reactor power.

November a 2045 Unit returned to 100% reactor power following repairs of tube leaks found in the southeast and southwest quadrants of main condenser.

November 8 2202 Commenced unit shutdown to Mode 3 to repair Reactor Coolant System leak from control bleed-off line of Reactor Coolant Pump (RCP) seal P003.

November 9 0259 Generator off line.

November 9 0301 Reactor tripped on Axial Shape Index (ASI) Core Protection Calculator (CPC) auxiliary trip.

November 13' 1647 Commenced cooldown to Mode 5 to replace all 4 Reactor Coolant Pump seals which were found to be degraded, and to inspect RCP Seal Heat Exchanger studs.

November 14 0458 Entered Mode 4.

November 15 0405 Entered Mode 5.

November 30 2359 Unit is in Mode 5. Mode 4 preparations are in progress.

7630u

~

REFUELING INFORMATION

~

. DOCKET NO. 50-361 UNIT SONGS - 2 12-16-1985 DATE COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657

1. Scheduled date for next refueling shutdown.

March 15, 1986

2. Scheduled date for restart following refueling.

June 15, 1986 l

3. -Will refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Yes.

What will these be?

Proposed Technical Specification changes are as follows:

+

Proposed Change Number (PCN 200) revises Refueling Water Storage Tank (RWST), Safety Injection Tank (SIT), and Boric Acid Makeup (BAMU) Tank required concentrations and required volumes.

Proposed Change Number (PCN 201) revises Departure froin Nucleate Boiling Ratio (DNBR)

Proposed Change Number (PCN 202) changes Moderator Temperature Coefficient (MTC)

Proposed Change Number (PCN 203) changes Resistance Temperature Detector (RTD) response time limits Proposed Change Number (PCN 204) raises Local Power Density (LPD) high trip setpoint Proposed Change Numler (PCN 206) deletes the Core. Protection Calculator (CPC) addressable constant table 4;

Scheduled date for submitting proposed licensing action and supporting information.

Proposed Technical Specification Changes (Proposed Change Numbers  !

PCN 200, 201, 202, 203, 204 and 206) were submitted on '

October 9, 1985.

l

REFUELING INFORMATION

,- (Continued)

5. 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

6. The number of fuel assemblies.

a) In the core. 217 b) In the spent fuel storage pool. 72

7. Licensed spent fuel storage capacity. 800 Intended change in spent fuel storage capacity. NA

8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

Approximately 1997.

l 7630u

}

NRC MONTHLY OPERATING REPORT DOCKET NO. 50-362 UNIT NAME SONGS - 3 DATE 12-16-85 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 OPERATING STATUS

1. Unit Name: San Onofre Nuclear Generating Station, Unit 3

2. Reporting Period: November 1985 ,

3. Licensed Thermal Power (MWt): 3390

4. Nameplate Rating (Gross MWe): 1127

5. Design Electrical Rating (Net MWe): 1080

6. Maximum Dependable Capacity (Gross MWe): 1127

7. Maximum Dependable Capacity (Net MWe): 1080

- 8. If. Changes Occur In Capacity Ratings (Items Number 3 Through 7)

Since Last Report, Give Reasons:

NA

9. Power Level To Which Restricted, If Any (Net MWe): NA

10. Reasons For Restrictions, If Any: NA This Month Yr.-to-Date Cumulative

11. Hours In Reporting Period 720.00 ,,8,016.00 14,616.00

12. Number Of Hours Reactor Was Critical 0 4,789.92 9,210.09

13. Reactor Reserve Shutdown Hours 0 0 0 4

14. Hours Generator On-Line 0 4,709.50 8,815.45

. 15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 0 12,083,598.90 25,145,187.34

17. Gross Electrical Energy Generated (MWH) 0 4,004,573.50 8,371,405.00

18. . Net Electrical Energy Generated (MWH) (3,130.53) 3,722,072.57 7,822,442.57

19. Unit Service Factor 0.00% 58.75% 60.31%

20. Unit Availability Factor 0.00% 58.75% 60.31%

21. Unit Capacity Factor (Using MDC Net) 0.00% 42.99% 49.56%

22. Unit Capacity Factor (Using DER Net) 0.00% 42.99% 49.56%

23. Unit Forced Outage Rate 0.00% 22.48% 14.12%

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

Refueling, September 14, 1985, 98 day duration (now in progress)

25. If Shut Down At End Of Report Period, Estimated Date of Startup: 12/21/85

26. Units In Test Status (Prior To Commercial Operation): Forecast Achieved INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIAL OPERATION NA NA 1

7630u

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-362 UNIT SONGS - 3 DATE 12-16-1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 MONTH -November 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0.00 17 0.00 2 0.00 18 0.00 3 0.00 19 0.00 4 0.00 20 0.00 5 0.00 21 0.00 6 0.00 22 0.00 7 0.00 23 0.00 8 0.00 24 0.00 9 0.00 25 0.00 10 0.00- 26 0.00 11 0.00 27 0.00 12 0.00 28 0.00 13 0.00 29 0.00 14 0.00 30 0.00 15 0.00 16 0.00 4

4 7630u

~ UNIT' SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-362 UHIT NAME SONCS - 3._

REPORT MONTH NOVEMBER 1985 .

DATE 14-10 L'JU3

. COMPLETED BY R. J. Maisei TELEPHONE t7141 368-6657-Method of Shutting Du ra t ion . Down- ' LER System Component- Cause & Corrective 1 '2 3 4 4 Action to No. Date Type (Hou rs) Reason Reactor No. Code Code Prevent Recurrence 22' 850914 S 720.00- C 4 N/A .N/A N/A Refueling 1 2 3 4 -l F- Fo rced Reason: Method; IEEE Std 803-1983 S-Scheduled' A-Equipment fa i l u re ( Exp l a in ) ~ 1-Manual B-Maintenance or Test . 2-Ma nua l Sc ram.

C-Refueling 3-Automat ic Scram.

D-Regulatory Restriction 4-Continuation from E-Operator Training & License Examination Previous Month F- Admin i st ra t ive 5-Reduction of 20%

C-Ope ra t iona l Error (Explain). or greater in the H-Other ( Explain) past 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 6-Other ( Expla in) 7630u 6

4

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO. 50-362 UNIT SONGS - 3 DATE 12-16-1985 COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657 Date Time Event

. . November 1 0001 Unit is in Mode 6, Cycle 1, of refueling

outage.

November 7 '1803 Reactor vessel head set into place on reactor vessel.

November 10 1245 Completed reactor head tensioning. Unit entered Mode 5.

. November 30 2359 Unit is in Mode 5 and day 77 of refueling outage. Fill and vent of reactor coolant system and containment integrated leak rate test have been completed. -Integrated engineered safety features testing is in progress.

7630u

REFUELING INFORMATION DOCKET N0. 50-362 UNIT SONGS - 3 12-16-i m DATE COMPLETED BY R. J. Maisel TELEPHONE (714) 368-6657

1. Scheduled date for next refueling shutdown.

. September 1986

'2. Scheduled date for restart following refueling.

November 1986

3. Wil'1 refueling or resumption of operation thereafter require a Technical Specification change or other license amendment?

Not yet determined What will'these be?

Not yet determined

4. Scheduled date for submitting proposed licensing' action and supporting information.

Not yet determined

5. 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.

Not yet determined

6. The number of fuel assemblies.

a) In the core. 217 b) In the spent fuel storage pool. 72

7. Licensed spent fuel-storage capacity. 800 Intended change in spent fuel storage capacity. NA

8. Projected date of last refueling that can be discharged to spent fuel storage pool assuming present capacity.

Approximately 1994 1

7630u '

f [$

Southern California Edison Company SAN ONOFRE NOCLEAR GENERATING iTATION P. O. BOX 128 SAN CLEMENTE CALIFORNIA 92672 H.E. MORGAN TELEPHONE STATION MANAGER (714) 368 6249 December 16, 1985 Director Office of Resource Management U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Subject:

Docket Nos. 50-361/50-362 Monthly Operating Reports for November 1985 San Onofre Nuclear Generating Station, Units 2 and 3 i

Enclosed are the Monthly Operating Reports as required by Section 6.9.1.10 of Appendix A, Technical Specifications to Facility Operating Licenses NPF-10 and NPF-15 for San Onofre Nuclear Generating Station, Units 2 and 3, respectively.

Please contact us if we can be of further assistance.

Sincerely, MbM Enclosures cc: J. B. Martin (Regional Administrator, USNRC Region V)

F. R. Huey (USNRC Senior Resident Inspector, Units 1, 2 and 3)

Institute of Nuclear Power Operations (INPO) 5/ 6

\\