ML20137C199

Monthly Operating Repts for Feb 1997 for San Onofre Nuclear Generating Station,Units 2 & 3

ML20137C199
Person / Time
Site:	San Onofre
Issue date:	02/28/1997
From:	Gibson G, Williams C SOUTHERN CALIFORNIA EDISON CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9703240176
Download: ML20137C199 (13)

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March 14, 1997 U. S. Nuclear Regulatory Commission l Attention: Document Control Desk i Washington, D. C. 20555 Gentlemen:

Subject:

Docket Nos.-50-361 and 50-362 )

Monthly Operating Reports for February 1997  ;

San Onofre Nuclear Generating Station, Units 2 and 3 )

Technical Specification 5.7.1.4 of Facility Operating Licenses NPF-10 and NPF-15 for the San Onofre Nuclear Generating Station, Units 2 and 3, respectively, requires Edison to provide a Monthly Operating Report of operating statistics and shutdown experience, including documentation of all challenges to pressurizer safety i valves,_for each unit. Enclosures 1 and 2 provide the February )

1997 Monthly Operating Reports for Units 2 and 3, respectively. l There were no challenges to the pressurizer safety valves during '

February 1997. ]

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If you have any questions, please contact Mr. C. E. Williams at (714) 368-6707.

Sincerely, Pgf u < a I

/ Gre y T. Gibson Manager, Compliance Enclosures

-cc: E. W. Merschoff, Regional Administrator, NRC Region IV K. E. Perkins, Jr., Director, Walnut Creek Field Office, NRC Region IV A. T. Howell, III, Director, Division of Reactor Projects, NRC Region IV J. A. Sloan, NRC Senior Resident Inspector, San Onofre Units 2 & 3 M. B. Fields, NRC Project Manager, San Onofre Units 2 & 3 9703240176 970228 , if PDR- ADOCK=05000361 7V R PDR a

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NRC Monthly Operating Report, February 1997 l

. San Onofre Nuclear Generating Station, Unit 2 i

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USNRC MONTHLY OPERATING REPORT Docket No: 50-361 1 i

, SAN ONOFRE NUCLEAR GENERATING STATION Ur.it Name: SONGS-2 UNIT 2 Date: March 14,1997 February 1997 Completed by: C. E. Williams l

Telephone: (714)368-6707 I Unit Name San Onofre Nuclear Generating Station. Unit 2 2 Reporting Period February 1997 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 3 througli 7) since last report, give reason. NA 9 Power level to which restricted, if any (Net MWe) NA Reason for restriction,if any. NA

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This Month Yr-to-Date Cumulative I 11 Hours in Period 672 1416 118,657- )

12 No. of Hours Reactor Critical 0.0 0.0 91,404.9 13 Reactor Resene Shutdown Hours 0.0 0.0 0.0 14 Hours Generator On-line 0.0 0.0 89,847.0 15 ' Unit Reserve Shutdown Hours 0.0 0.0 0.0 i 16 Gross Thermal Energy Generated (MWh) 0.0 0. 294,246,764.

17. Gross Electrical Energy Generated (MWh) 0.0 - 0. -99,682,774, 18 Net Electrical Energy Generated (MWh) (16,567.9) (23,153.3) 94,567,930.

19 Unit Service Factor 0.0% 0.0% 75.7 %

20 Unit Availability Factor 0.0% 0.0% 75.7 %

21 Unit Capacity Factor (Using MDC Net) 0.0% 0.0% 74.5 %

22 Unit Capacity Factor (Using DER Net) 0.0% 0.0% 74.5 %

23 Unit Forced Outage Rate 0.0% 00% 48%

24. Shutdowns scheduled over the next 6 months (type, date, and duration of each):

Cycle 9 refueling outage commenced November 30,1997. No other outages scheduled.

j 25. If shutdown at end of report period, estimated date of startup: March 20,1997

26. Units in test status (prior to commercial operation): Forecast Achiesed l

Initial criticality NA NA Initial electricity NA NA Commercial operation NA NA l 1

USNRC MONTHLY OPERATING REPORT Docket No: 50-361 SONGS-2

, SAN ONOFRE NUCLEAR GENERATING STATION Unit Name:

UNIT 2 Date: March 14,1997 February 1997 Completed by: C. E. Williams Telephone: (714)368-6707 AVERAGE DAILY UNIT POWER LEVEL Ave. Daily Power Level Ave. Daily Power Level Day (MWe Net) Day (MWe Net) 1 .0 17 ~ 0 2 0 18 0

-3 0 19 0 4 0 20 0 5 0- 21 0-6 0 22 0

-7 0- 23 .0 8 0 24 0 9 0 .25 0 10 0 26 0 11 0 '27 ~0 12 0 28 0  !

1 13 -0 ,

i 14 0 15 0 j 16 0 1

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• USNRC MONTHLY OPERATING REPORT Docket No: 50 361 SAN ONOFRE NUCLEAR GENERATING STATION Unit Name: SONGS-2 UNIT 2 Date: March 14,1997 February 1997 Completed by: C. E. Williams Telephone: (714)368-6707 UNIT SHUTDOWNS AND POWER REDUCrlONS Number 101 i Date i1/30/96 Type (1) _ S Duration (Hours) 672.0 Reason (2) C Method of shutting down reactor (3) 2 LER No. - NA '

System Code (4) NA Component Code (5) NA '

l Cause and corrective action to Cycle 9 refueling outage prevent recurrence

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(1) F. Forced S-Scheduled l (2) Reason: A Equipment Failure (Explain) ,

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other(Explain)

(3) Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction in the Average Daily Power Level of more than 20% from the previous day 6-Other(Explain)

(4)IEEE Std 805-1984 (5)IEEE Std 803A-1983 3

. l USNRC MONTHLY OPERATING REPORT Docket No: 50-361 SAN ONOFRE NUCLEAR GENERATING STATION Unit Name: SONGS-2 l UNIT 2 Date: March 14,1997 February 1997 Completed by: C. E. Williams  !

Telephone: (714)368-6707 ,

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SUMMARY

OF OPERATING EXPERIENCE FOR TIIE MONTII Date Time Event j 2/1/97- 0001 Mode 5, Cycle 9 refueling outage in progress,' day 63 of scheduled 70 day outage.

2/2/97 1405 Initiated integrated Engineered Safety Features Refueling interval sun eillance.

I 2/13/97 1552- Completed RCS fill and vent activities and formed a pressurizer bubble. Started Mode 4 preparations.

4 2/18/97 1754 Unit 2 entered Mode 4, 2/19/97 0337 RCS at 2250 PSIA.

0510 Entered RCS leak AOI SO23-13-14, indications of primary to secondary leakage in S/G blowdown sample radiation monitor for E-089.

0545 Entered Tech. Spec. 3.4.13.e RCS primary to secondary leakage > 720 GPD. Leakrate estimated to be

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~ 3 gpm in S/G E-089.

0940 Started RCP P001 to check seal staging. Seals did not stage correctly. Middle stage appeared failed.

0943- Commenced RCS depressurization to 350 psi.

1800 Commenced cooling down with SDC.

2004 Entered Mode 5. Exited action for LCO 3.4.13.e.

2315 RCS at 125 F.

2/20/97 .I130 Pressurizer bubble collapsed.~

2/21/97 1636 RCS drained to midloop for steam generator tube leak repair and replacement of 2P001 seal cartridge.

2/27/97- 0400 RCS fi!!cd to 51.8% pressurizer level following midloop work.

2/28/97 2345 Suspended drawing a bubble in the pressurizer upon report that CEDM #19 stack leaking.

2400 Unit 2 in Mode 5, RCS Temp. 340 F,350 PSIA. Preparing to depressurize RCS to seal weld CEDM #19 stack. Outage day 90.

Note: There were no challenges to the pressurizer or main steam system safety valves during the month.

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USNRC MONTHLY OPERATING REPORT Docket No: 50-361

, SAN.ONOFRE NUCLEAR GENERATING STATION Unit Name: SONGS-2 UNIT 2 Date: March 14,1997 February 1997 Completed by: C. E. Williams Telephone: (714) 368-6707 REFUELING INFORMATION

1. Scheduled date for next refueling shutdown:

Cycle 9 refueling outage commenced November 30,1996. Cycle 10 refueling outage is forecast to begin in l October,1998.

2. Scheduled date for restart following refueling:

Restart from Cycle 9 refueling outage is forecast for March 20,1997. Restart from Cycle 10 refueling outage is forecast for December,1998.

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

No for Cycle 9. Unknown at this time for Cycle 10.

What will these be?

NA

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

NA

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.

Increase in fuel enrichment (for Cycle 9).

6. The number of fuel assemblies.

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A. In 'the core L 217 B. In the spent fuel storage pool: 870 Unit 2 Spent Fuel Assemblies 800 Unit 2 New Fuel Assemblies 0 Unit 1 Spent Fuel Assemblies 70 C. In the New Fuel Storage Rack 0

7. Licensed spent fuel storage capacity: 1542 Intended change in spent fuel storage capacity: None

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

January 2006 (assuming 22 month fuel cycles for all future cycles, and Unit I fuel remains where it is currently located).

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i Enclosure 2 NRC Monthly Operating Report, February.1997 San Onofre Nuclear Generating Station, Unit 3 .j l'

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USNRC MONTHLY OPERATING REPORT Docket No: 50-362 i

, SAN .ONOFRE NUCLEAR GENERATING STATION Unit Name: SONGS-3 l UNIT 3 Date: March 14,1997 February 1997 Completed by: C. E. Williams Telephone: (714) 368-6707 i

1 Unit Name San Onofre Nuclear Generating Station. Unit 3 1 2 Reporting Period Februarv 1997 3 Licensed Thermal Power (MWt) 3390 4 Nameplate Rating (Gross MWe) 1127 5 Design Electrical Rating (Net MWe) . 1080 j 6 Maximum Dependable Capacity (Gross MWe) 1127 7 Maximum Dependable Capacity (Net MWe) 1080 8 If changes occur in capacity ratings NA (Items 3 through 7) since last report, give reason.

9 Power level to which restricted, if any 1 (Net MWe) NA )

l 10 Reason for restriction,if any. NA l This Month Yr-to-Date Cumulative  ;

1I Hours in Period 672 1416 113,208 l

12 No. of Hours Reactor Critical 672 1416.0 91,708.2 l 13 Reactor Reserve Shutdown Hours 0.0 0.0 0.0 14 Hours Generator On-line 672 1416.0 89,950.3 l 15 Unit Reserve Shutdown Hours 0.0 0.0 0.0 16 Gross Thermal Energy Generated (MWh) 2,258,153. 4,740,226. 290,879,708.

17 Gross Electrical Energy Generated (MWh) 765,716. 1,605,345. 98,686,552.1 18 Net Electrical Energy Generated (MWh) 727,205. 1,524,119. 93,302,130.

19 Unit Senice Factor 100.0 % 100.0 % 79.5 %

20 Unit Availability Factor 100.0 % 100.0 % 79.5 %

21 Unit Capacity Factor (Using MDC Net) 100.2 % 99.7 % 76.3 %

22 Unit Capacity Factor (Using DER Net) 100.2 % 99.7 % 76.3 %

23 Unit Forced Outage Rate 0.0% 0.0% 5.0%

24. Shutdowns scheduled over the next 6 months (type, date, and duration of each):

Refueling shutdown, April 12,1997, 75 days

25. If shutdown at end of report period, estimated date of startup: NA

26. Units in test status (prior to commercial operation): Forecast Achieved Initial criticality NA NA Initial electricity NA NA Commercial operation NA NA l

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USNRC MONTHLY OPERATINO REPORT Docket No: 50-362

, SAN,0NOFRE NUCLEAR GENERATING STATION Unit Name: SONGS-3 UNIT 3 Date: March 14,1997 February 1997 Completed by: C. E. Williams Telephone: (714) 368-6707 AVERAGE DAILY UNIT POWER LEVEL l

Ave. Daily Power Level Ave. Daily Power Level j Day (MWe Net) Day (MWe Net) l 1 1084, 17 '1082.

2 1086. 18 1083.

3 1083. 19 1083.

l 4 1079. 20 1083.

5 '1079. 21- 1081.  !

6 1078. 22 1082. j 7 '1078.- 23 1081.

8 1081. 24 1081.

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9 '1085. 25 1081.

10 1085. 26 1081.

11 1085. 27 .1081.

12 1084. 28 1081.

13- 1082 14 1085.

15' '1084.

16 1083. ,

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USNRC MONTHLY OPERATING REPORT Docket No: 50-362 SAN,0NOFRE NUCLEAR GENERATING STATION Unit Name: SONGS-3 a UNIT 3 Date: March 14,1997 February 1997 Completed by: C. E. Williams Telephone: (714) 368-6707 UNIT SHUTDOWNS AND POWER REDUCTIONS i

Number None Date NA I Type (1) NA-Duration (Hours) NA

)

Reason (2) NA' l l

Method of shutting down reactor (3) NA J l

LER No. NA J System Code (4) NA l Component Code (5)' NA I Cause and corrective action to NA j prevent recurrence (1)F Forced S-Scheduled (2) Reason: A-Equipment Failure (Explain)  ;

B-Maintenance or Test C-Refueling D-Regulatory Restriction E-Operator Training & License Examination F-Administrative G-Operational Error (Explain)

H-Other (Explain)

(3) Method: 1-Manual 2-Manual Scram 3-Automatic Scram 4-Continuation from Previous Month 5-Reduction in the Average Daily Power Level of more than 20% from the previous day 6-Other(Explain)

(4)IEEE Std 8051984

'5)IEEE Std 803A-1983 3

i USNRC MONTHLY OPERATING REPORT Docket No: 50-362

, SAN ONOFRE NUCLEAR GENERATING STATION Unit Name: SONGS-3 UNIT 3 Date: March 14,1997 February 1997 Completed by: C. E. Williams Telephone: (714) 368-6707

SUMMARY

OF OPERATING EXPERIENCE FOR THE MONTH I

Date Time Event j 2/1/97 0001 Mode l,99.2% reactor power, ll30 MWe,489.7 EFPD. ,

l 2/14/97 1300 SR 3.0.3 entered for not fully satisfying SR 3.3.5.6 ESF response time. Subgroup relay response time itself not directly measured. Had used bounding value of 300 milliseconds.

2/14/97-- :1615- SR 3.0.3 entered for not fully testing the entire LOVS channel response time. Only loss of voltage relay 127F timed.

2/15/97 1205 Exited SR 3.0.3 for SR 3.3.7.4 after reset of LOVS relay time delays and retiming channel.

1238: Exited SR 3.0.3 for SR 3.3.5.6 after NRC granted the requested enforcement discretion.

2/28/97 1500 SR 3.0.3 entered for SR 3.8.1.11 and 3.8.1.19 LOVS trip test. Not satisfied for dome air cire fans 3MA071 and 3MA072. Fans are indirectly tripped (by aux relays when LOVS, SDVS or DGVSS occurs) and not included in the surveillance procedure.

2011' Exited SR 3.0.3 for SR 3.8.1.11 and 3.8.1.19 after verification of dome air circ fan trip testing.

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2400 Unit 3 at 99.6% reactor power,1133 MWe,490.6 EFPD.

Note: There were no challenges to the pressurizer or main steam system safety valves during the month.

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USNRC MONTHLY OPERATING REPORT Docket No: 50-362 SAN.ONOFRE NUCLEAR GENERATING STATION Unit Name: SONGS-3 UNIT 3 Date: March 14,1997 February 1997 Completed by: C. E. Williams Telephone: (714) 368-6707-REFUELING INFORMATION

1. Scheduled date for next refueling shutdown:

Cycle 9 refueling outage is forecast for April 12,1997.

2. Scheduled date for restart following refueling:

Restart from Cycle 9 refueling outage is forecast for June 26,1997.

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

Yes. ,

What will these be?

1. Revision to test interval ofload sequencing relays.

2. Appendix J Option B Technical Specification.

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

1. PCN 454 Load Sequencing Relays Submitted 5/29/96

2. PCN 361 Appendix J Option B Submitted 5/30/96

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.

Increase in fuel enrichment.

6. The number of fuel assemblies.

A. In the core 217 B. In the spent fuel storage pool: 858 Unit 2 Spent Fuel Assemblies 700 Unit 2 New Fuel Assemblies 40 Unit 1 Spent Fuel Assemblies 118 0 1 C. In the New FuelStorage Rack

7. Licensed spent fuel storage capacity: 1542 Intended change in spent fuel storage capacity: None

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

May 2006 (full off-load capability assuming 22 month fuel cycles for all future cycles, and Unit I fuel remains where it is currentlylocated).

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