ML20128M072

Monthly Operating Repts for Jan 1993 for San Onofre Units 2 & 3

ML20128M072
Person / Time
Site:	San Onofre
Issue date:	01/31/1993
From:	Darling J SOUTHERN CALIFORNIA EDISON CO.
To:
Shared Package
ML20128M068	List: ML20128M065 ML20128M072
References
NUDOCS 9302220081
Download: ML20128M072 (12)

Text

.

Documer'it Control Desk NRC MONTHLY OPERATING REPORT DOCKET NO: _5Q351 UNIT NAME: _SS1GJL-2 DATE: 2/ 6/93 COMPLETED BY:

J. L 03rlina-TELEPHONE:. (714).Jhe:6223 OPERATING SJATUS, 1.

Unit Name: _S_an Onofre Nuclear Generatina. Station. Unit 2 2.

Reporting Period: Jal.ur y 1993 j

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): __LL2J 7.

Maximum Dependable Capacity (Net MWe):

3070 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 i

11.

Hours In Reporting Period 744.00. _

774.00 82.921.CT 12.

Number Of Hours Reactor Was Critical 744.qQ 774.00 61.47_8.36 13.

Reactor Reserve Shutdown Hours

.00 0.00 0.00 -

0 14.

Hours Generator Oa Line 744.00 744.00 60.401.27 15.

Unit Reserve Shutdown Hours 0.00 qu Q 0.00_

o 16.

Gross Thermal Energy Generated (MWH)

L.5_lldE l. 41 _ 2. 511. 527. 41 197. 331. 375. ZL -

17.

-Gross Electrical Energy Generated (MWH) andlqJQ _._SH28.dQ _qQ.dQQ.788.50' 18.

Net Electrical Energy Generated (MWH)

1. 11474.0n _

814.874.00 _63.422.3&9 0L t 2

19.

Unit Service Factor 100.q0J 100.00%

72 84%

2 20.

Unit Avallability factor.

_ _ 100,00%

100.00'4._ _

7.LH43 21.

Unit Capacity Factor (Using MDC Net)-

LQ2. 36%

IQL 3h5 71.48%.

22.

Unit Capacity Factor (Using DER Net)

LQL1fs 102.36%_

71.48%-

23.

Unit Forced Outage Rate _

Q.00%

0.00% -

6.79%

24.

Shutdowns Scheduled Over N3xt.6 Months (Type, Date, and Duration of Each):

Refuelina shutdowni June 5.1993. Duration (77 days)

- NAL 25.

If Shutdown At End.0f Report Period, Estimated Date-0f Startup: _

Achieved-26.

Units In Test Status (Prior To Commercial Operation):

Forecast INITIAL CRITICALITY-NA

_ NA '

INITIAL ELECTRICITY NA NA-COMMERCIAL OPERATION

-NA -

NA mor.jan/2

-9302220001 930216 DR ADOCK 0500 1

l Document Control Desk AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 361 UNIT NAME: A0t1GS-2

'/16/93 DATE: _

Col 4PLETED BY: J. L. Darlino TELEP}iONE: _LLL4) 368 6223 MONTH:.lapuary U93 DAY AVERAGE DAILY POWER LEVEL DAY AVERACE DAILY POWER LEVEL (MWe-Net)

.(MWe Net) 1 1096.08 16 1995.39 2

19.94. ?B 17 1095.13 3

1097.88 18 1093.96 4

1100.63 19 1093.63-l 5

__LQ97.8.8 20 1096;46 6

1021.79 21 1097.79 7

1097 88 22

___. _1001,_13 8

1095.38 23-1094.50 9

107h50 24 1096.29 10 LO96.79' 25 1095.54 11 1095.71 26 1097.79 12 1097.38 27 1099.25 l

13 1097_.29 28 1097.21 14 1096J8 29 1089.75 15 1090.54 30

-1097.25 31 1196.dQ l'

mor.jan/3

. ~ -

.. - ~...

Document Control Desk y

UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO: 50-361-UNIT NAME: SONGS - 2 REPORT MONTH:

January 1993 DATE:

2/16/93 j

COMPLETED BY:

J. L. Darlino t

TELEPHONE: ___(714) 368-6223 Method of Shutting Cause & Corrective t

Duration Down LER System Component Action to 2

2 3

_ No.

Date Type (liours) f.eason Reactor No.

Code' Code' Prevent Recurrence e

There were no power reductions or_ shutdowns this reporting period.

b

)

i 4

?

-2F-Forced

' Reason:

' Method:

"IEEE Std 805-1984 i

S-Scheduled-A-Equipment Failure _(Explain) 1-Manual S

B-Maintenance or Test

,2-Manual Scram.

IEEE Std 803A-1983 L.

C-Refueling.

3-Auttmatic Scram.-

F D-Regulatory Restriction 4-Continuation from-E-Operator Training & License Examination-Previous Month

'F-Administrative-5-Reduction in the Average G-Operational Error -(Explain)

Daily Power Level of more H-Other (Explain) than 20% from.the previous day 2

6-Other (Explain)-

' ' mor.jan/4 e

+6 y

N

'~r 4

W

?

T 9'

9 M-'

T*-

TTei e

=f-4-P 4

4 Document Control Desk Sl'MMARY OF OPERATING EXPERIENCE FOR THE MONTH DOCKET NO:

50-151 UNIT NAME: 1/]fCS-2 SQ $/93 DATE:

COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368 6223 Date Time Event January 1 0001 Unit is in Mode 1, 100% reactor power,-1148 MWe.

January 31 2400 Unit is in Mode 1, 100% reactor power, 1146 MWo.

T mor.jan/s

-~

~

. j Document Control Desk REFUELING INFORMATION DOCKET NO:

50-361 UNIT NAME:

10NGS - 2 DA1E:

2/16/93 COMPLETED BY: - _d. L. Datl.ina TELEPHONE:

_ (714) 3681E123 MONTH:

. January 1993

1. Scheduled date for next refueling shutdown.

Cycle 7 refueling outage is forecast for June 51993.

2. Scheduled date for restart following refueling.

Restart from. Cycle 7 refueling outage is forecast for August 1993.

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

Yes.

What will these be?

The following Technical Specification changes are desired-in support-of work being performed during the Unit 2 Cycle 7 refueling outage.

A.

A change to Technical Specification 3.9.7 has been requested to permit use of the cask pool cover to support refueling activities.

This cover had previously been used to support the spent fuel pool reracking project. NRC approval of this change will-be-required prior to the start of the outage to support use of. the cover during-the-outage.

B.

A change has been-requested to Technical Specification 4.4.5;2.1 to-allow a delay in performing-an RCS inventory balance during. plant transients. -Although not required, NRC approval of this change is desired prior to startup from the. Unit 2 Cycle 7 outage.

C.

A change will be requested to Technical Specification 3.7.1.1 to allow-a tolerance on the main steam safety. valves for the purpose of-determining valve operability. Although not required, NRC approval of this change is desired to support the surveillance testing

- scheduled to be performed during the Unit'2 Cycle 7 outage.

P d

mor.jan/6-

'y,y

~--r y,w-

---

4.-,.

,,p--

-,c..

y

1 i

Document Control Desk j

REFUELING INFORMATION-DOCKET N0: _10-361 UNIT NAME:

SONGS - 2 DATE:.

2/16/93 COMPLETED BY:

J. L. Darlina TELEPHONE:

(714) 368-6223 f

MONTH:

danuary 1993 D.

A license Amendment and Technical Specification changes has been requested to permit implementation _of a design change.to use the containment spray pumps for shutdown-cooling and spent fuel-pool cooling.

NRC approval-of this change will be requested to permit. use of the spray pumps for-spent fuel pool cooling during the Unit 2-cycle 7 outage.

4.

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

1 A.

Proposed Change on Cask Pool Cover Submitted December 24,-1992 1

B.

Proposed Change on RCS Leakrate Submitted November-20, 1992-C.

Proposed Change on ilSSVs February 16, 1993 O.

Proposed Change on Spray Pumps submitted December 24, 1992

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.

554 (484 Unit 2 Spent Fuel-Assemblies.- 70 Unit 1 Spent Fuel Assemblies)-

7. Licensed spent fuel storage capacity.

1542 Intended change in spent fuel storage capacity.

None

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

Approximately 2001 (full off load capability) mor.jan/7 f

J

<e

- - - - n c

t.w.vm-n.

~w--------eN

L Document Control Desk NRC MONTHLY OPEP.ATING REPORT DOCKET N0:

50-36t__

UNIT NAME:

SONGS - 3 DATE:

2/16/93 COMPLETED BY:_ _.L714) 368-6 J. L. Darlina TELEPHONE:

DPERATING STA1QS 1.

Unit Name:

San Onofre Nuclear Generatina Station. Unit 3-2.

Reporting Period: _danuary 1993 l

3.

Licensed Thermal. Power (MWt): _

3310 4.

Nameplate Rating (Gross MWe):

1127 5.

Design Electrical Rating (Net MWe):

1030 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.

Hcurs in Reporting Period 744.00 774.00 77.472.00__

12.

Number Of Hours keactor Was Critical 687.97 687.97 59.887.73 13.

Reactor Reserve Shutdown Hours

- 0. 03 0.00 0.00 14.

Hours Generator On-Line 664 59 664.50 58.270.56 2

15.

Unit Reserve Shutdown Hours 0.00 0.00 0.00 16.

Gross Thermal Energy Generated (MWH) [.205.836.93 2.195.836.91 186.829.911.17_

17.

Gross Electrical Energy Generated (MWH) 753.520.0Q 753.520.00 63.380.380.00-18.

Net Electrical Energy _ Generated (MWH) 712.802.00 712.802.00 59.858.472.361 19.

Unit Service Factor -

89.31%.

89 11%

75.21%-

20.

Unit Availability Factor 89.31%

89.31%

75.21%

e 21.

Unit Capacity Factor (Using MDC Net) 88.71%

88.71%.

71.54%'

22.

Unit Capacity Factor (Using DER Net) 88.71%

88.71%

71.54%

23, Unit Forced Outage Rate 10.69%

10.69%

7.46%-

24.

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

None

^

25.

If Shutdown At End Of Report Period, Estimated Date of Startup:

NA-26.

Units In Test F+atus (Prior To Commercial Operation):

Forecast-Achieved INITIAL CRITICALITY NA _

NA INITIAL ELECTRICITY Ni( __

NA COMMERCIAL OPERATION NA NA=

mor.jan/8

~

. ~

.. g e

a: :

DocumebtControl-Desk

^

AVERAGE DAILY UNIT POWER LEVEL.

DOCKET N6::.50 36.J

. UNIT NAME:

SONGS _- 3

'1'

-DATE:: 2/16493

- COMPLEi tD BY :. J.,__L. __ Darl i nq TELEPHONE: J 714) 356.8-6223 = _

a 1

MONTH: J3aE.q_y 1993

~

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAl! Y POWER LEVEL (MWe Net)

(MWe-Net)'-

1 1106.25 16 545.67' 2

11) (96_

17 0.00.

., }

I 3

1111'13

_18 0.00 1

4 1113.13 19 0.0)

-5 J111J2 20 60.1.25 6

ll]0. 2 L 21 1096.21 7

1112.8%

22 1095.88 l

'1074;17-lr 8

1104.54 23 r

1111.50 24 1101.75 10

';11.63 25-

_}10Lh, _

11

'1100,58 26 1104d9-I T.

11Ll.33 27 1104.38 l.-;

13 1110.71

-28

_1104.79' LI 14 1111.21 29 1100.29' 1-15

.1055.21.

30 1091.21 31 1104.42 a

mor,jan/9 s

('

.3 j.

'I O f

m.

.c

.g g

p

. Document Control Desk w-

~

UNIT SHUTDOWNS AND POWER hr +fl0HS DOCKET WO:.50"362-UNIT NAME: 50NGS,

REPORT MONTl!:

Janbary 1993-DATE '2/16/93 COMPLETED BY:

J. L. Darline TELEPHONE:

(714) 368-6223'

' Method of

.Shutt ing.'

Cause &-Currective..

Duration Down LER System 'Ccmponent Action to..

l 8

3 No.

L.Date Type (Hours)

Reason Reactor N o.-

Code' Code' Prevent Recurrence 71

.150193 0.0~

8 5

NA KE COND Load reduction to perform-

^

circulating water system !

heat treat.

72 160193 F

79.5 B

3 3-93-001 EL GEN See note below' Note: Turbine generator trip was actuated on a Main Generator stator ground protection signal which in turn caused.a Reactor, trip on a ' loss of load signal. The ground was located on the B phase of the generator output conductor.- Thetground cccurred when water :frc:t.a heavy rain' leaked into the enclosure housing th.e generator output conductors. 'fhe. Main Generator terminal enclosure was resealed:to' prevent future rain water intrusion. The Unit was returned to service 1on-January'20th.

il s

2 3

F-Forced Reason:

Method:.

- *IEEE Std 805-19841

+

5-Scheduled A-Equipment Failure (Explain) 1-Manual S

B-Maintenance'or Test' '

2-Manual' Scram; IEEE Std. 803A-1983 -

.C-Refuel ing 3-Automatic' Scram.

D-Regulatory Restriction 4-Continuation from, E;0perator. Training & License Examination Previous Month...

F-Administrative

5-ReductionLin the: Average-G-Operational Errori(Explain)'-

Daily Power Levelief.more:.

~

~~

. than 20% from the; previous day-H-Other (Explain)-

s

~'

.6-Otherl(Explain)f e

sm#ijan/10-

~

~

7

6

..,. 7 4

. ;r ;,,i:

, ~

+

Document Control Desk

~

SUMHARY OF OPERATING EXPERIENCE FOR THE NONTH DOCKET NO:

50-362=

d UNIT NAME:

SONGS - 3'

-DATE:_ 2/ITT93

'l COMPLETED BY:

J. L Qarlino _ _,_._<

TELEPHONE: _(IL4L35.8_ _5123,

l pate Jime Eyzn.t

)

January 1

0001-Unit-is in Mode 1 at 100% reactor power, 1159 MWe.

,.f'; l January 15 1600 Commenced Unit load reduction to 80% reactor power -

'R to. perforal circulating-water -heat treat.

2055 Unit at 80'l reactorzpower.

January 16 0710 Commenced Unit load reduction 10-75% to clean condenser water boxes following con,pletion of circulating water heat treat.

0800 Unit at 75% reactor power.

1640 Reactor trip on loss of Load ~due.to Main Generator trip on Stator ground.

Unit-in Mode 3.

L January 18 2303 cominenced reactor ;tartup.

Cause of Main Generator L

stator ground was identified and corrected.

2345 Entered llade 2.

P January 19 0042 Reactor-critical.

ll ^

0237 Reactor power at 1% and holding'for Mein Feedwater pump testing.

2030 Commenced increasing reactor power.following completion x

i of Main Feedwater pump-testing.

L 2110 Entered Mode 1.

l January 20 0010 Unit syachronized to the Grict. Commenced increasing.

load to 100% power.

L-2315-Unit at'97.5%' power 1133 MWe. Turbine. control valves i

fu'll oper..

p January 31 2400 Unit is in-Mode 1, 100% reactor power 1150 Mk'e.

{-

mur.jan/Il a-m

~

t-

-,.w

v...

+

.A

j.f

. '.*.i Documeht Control Desk-

~

REFUELING INFORMATION DOCKET N0:1 50-362^

UNIT NAME:.

2/16/93--

10jlGS ~~ 3-

=

eDATE:

- c COMPLETED BY.:

A L. Darlina '

-TELEPHONE:

-(7141 369-6223>

MONTH:

_ h_nitarv 1993 _

i

1. Scheduled date for next refueling shutdown.

Cycle 7 refueling outage is forecast for October 1,'1993.

2. Scheduled date for restart following refueling.

Restart from Cycle 7 refueling outage is forecast for December 1993.:

3. Will refueling or resumptio_n of operation.thereaf ter require aLTechnical Specification change or other license amendment?--

Yes.

What will these be?

The following Technical Specification changes are desired in support of work being performed during the Unit 3 Cycle 7 refueling outage.

A.

A ch.ge to Technical Specification 3.9.7 has been requested to permit use of the cask pool cover to support refueling activities.-

This cover had previously been used to support' the spentafuel, pool. ;

rcracking project..-NRC approval of this change will bez requiredt prior to the start of the outage to supporciuse of.the cover;during-L the outage.

J 8.

A change has been requested to lechnical Specificationc4.4.5.2.1 to allow a delay in performing an RCS inventory balance during plant transients. Although not required, NRC approval of this change lis desired prior to startup from the Unit ~3 Cycle'7 cutage.

C.

A change will be rcquested to Technical Specification 3.7.1.1 to allow a tolerance en the main steam safety valves for the. purpose of determining valve operability. - Although not required,1NRC

a. proval-of this change is desired to support the surveillance testing' scheduled to be performed during the Unit 3 Cycle 7.. outage.

- mor.jan/12 v

,;y s

r v

.w x

+

~

C, :

r

'Documeht Control Desk t

TEFUE1ING lNFORMATION 00CKET N0:3 _50-36Rc UNITL NAME: ~~ SONGS - 3 DATE:=

7714/93' COMPLETED BY:

_J.,_L._QE}10.g _

TELEPHONE:-' (714).368-62?l_ 1 MONTH:

Januaty__l993 D.

A license Amendment and Technical Specification changes has been:-

requested to permit implementation of.a desion-change:to use the-containment spray pumps for shutdown cooling and spent fuelf pool-cooling. NRC approval of this change will be requested to permit use i

of the spray pumps for spent fuel pool cooling during theiUnit 3?

cycle 7 outage.

4

4. Scheduled date for submitting proposed licensing actionsand supporting-information.

A.

Proposed. Change.on Cask Pool Cover Submitted December 24; 1992 B.

Proposed' Change on RCS Leakrate.

Submitted November 20,-1992:

C.

Proposed Change on MSSVs

' February 16, 1993-D.

Proposed Change on Spray Pumps Submitted December 24,L1992

5. Important licensing considerations associated with refueling, e.g. new.or.

different feel design or ' supplier, unreviewed design' or performance analysis '

f methods, significant changes in: fuel design, new operating procedures.

J None.

6. The number of fuel tassemblies.

a)- In the core.

R11___

b)

In.the spent fuel storage pool.

'574 (484 Unit 3 Spent

._ Luel A nemblies. 90 a

s

__ Unit I Spent-Fuel Assembljfqs)

7. Licensed spent fuel storage capacity.

1542 Intended-change in spent' fuel storage capacity..__None

-8. Projected date of last refueling that can be discharged to spent fuel' storage pool assuming present capacity, Approximately 2003 (full off lead capability) i

.mor.jan/13 y

p p

. 2'.

'