ML20005G810

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Monthly Operating Rept for Dec 1989 for Salem Unit 2
ML20005G810
Person / Time
Site: Salem PSEG icon.png
Issue date: 12/31/1989
From: Miller L, Orticelle A
Public Service Enterprise Group
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9001230125
Download: ML20005G810 (9)
v • d • e


Text

'

1. O PSEG Public Sorvice Electric arid Gas Cornpany P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station January,12, 1990 U.S. Nuclear Regulatory' Commission Document Control Desk Washington, DC 20555

Dear. Sir:

HONTHLY OPERATING 1 REPORT SALEM NO. 2 DOCKET NO. 50-311 In' compliance with Section 6.9.1.6, Reporting Requirements for the Salem Technical Specifications, the original copy of the monthly operating reports.for the month of December 1989 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Safety Related Maintenance Major Plant Hodifications operating Summary Refueling Information Sincerely yours,

- (

L.

K. Miller General Manager -

Salem Operations RH:pe ec:

Mr. William T. Russell Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, l' A 19046 900

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Enclosures V.2 DbbN?$f,ffg1 8-1-7.R4 y

The Energy People Ws 21 M6 (11 h4: 12 64

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AVERAGE DAILY' UNIT POWER' LEVEL Docket No. 50-311-Unit Namei-Salem # 2 DateL 01-10-90

' Art O'ticelle Telephone

'6[09-935-6000 J

Completed:byi r

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Extension

_4722

.! onthi N DECEMBER ~1989 M

-Day. Average Daily. Power Level

. Day l Average Daily Power Level

_ MWe-NET):

(MWe-NET)

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1097 17 1078-

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-1095 18 1109' 3;

-1105 19-1110 g

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1102 20 1107

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1104 21 1115

- 6:

'1110 22 1115 7-1116 23 1072

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'8 :

1108 24 1106 9

1108_

25 1111 11 0.

'1102 26-1111 11-1094 27 1100 12-1114 28 1221-1

13 -

__ill10 29 1100 14-1063 30 1110 15 1106 31 1109 16 1111

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~ OPERATING DATA' REPORT d

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  • LJg Docket No. 50-311-v<

Date.

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Telephone-935_-60,0_0_

. C.ompleted l by s Art' Orticelle_

. Extension

'4722 1

_ Operating Status ~

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Unit' Name-Salem No. 2 Notes 2.

~ Reporting Period.

.Deiiember 1989 Licensed Thermal Power (MWt) 3411 f( 3.4.Nameplate Rating. (Gross MWe) 1170

{5.. - Design Electrical Rating (Net MWe) 11'1 5 6.

Maximum Dependable. Capacity (Gross MWe)TT45

17.. Maximum-Dependable Capacity (Net MWe) f1E

(.

8.

If< Changes Occur _in' Capacity _ Ratings (items 3 through 7) since Last L

Rep, ort, Give Reason _

.N/A h

9.

Power Level to WhTch Restricted, if any lifet MWe)

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'10, Reasons.for Restrictions, if any _ N/A_

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. _ -. - -. ~.

6 This Month Year to Date Cumulative --

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.11., Hours in Reporting Period 744 8760 72049 I

112. No. of Hrs. Reactor was Critical ~~~14'4

' ~7T 5 6~~-

'46DT5.8 13.1 Reactor-Reserve' Shutdown llrs.

0 0'

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'14. Hours Generator ~ On-Line

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~ T4Y2~6

~4T5 4 5. 2 4

'15.-Unit Reserve Shutdown Hours

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0 0

0

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16. Gross Thermal Energy Generated (MWH) 2524596 24386642.4 117. Gross Elec.. Energy. Generated 89_051739.4 (MWH) 875080

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218. Net Elec.. Energy-Generated (MWH)

BT2T2'7'~

~8162752 46047052 7824601 43799906

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'19. Unit Service-Factor 100 84.7 61.8 s

l20.-Unit Availability Factor 100 84.7 61.8

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21. Unit' Capacity Factor (using MDC Net)'

100

22. Unit Capacity Factor 80.8 54.9 (using DER Net) 100 80.1 54.5 23.-Unit Forced Outage Rate

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0 9.7 26.0

~ 2 4 '. Shutdowns scheduled over next 6 months (type, date and duration of each)

REFUELING OUTAGE 3-31-_9_0 SCHEDULED TO LAST 45 DA_YS T25. IT shutdown at end o'T Report PerTod, Estimated Date ol Startup:

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N/A 8-1-7.R2

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Docketi Noa J50'-311' 3

.UlIIT SHUTDOWN AND) POWER REDUCTIONS.

REPORT' MONTH. DECEMBER 1989-

' Unit Name Salem NoT2

[

~ Date-01-10-90

- 44 Completed by Art Orticelle-

. Telephone; 609-935-6000-

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Extension. 4722_

Method of

-Duration

. Shut ting License

- Cause'and: Corrective Action <to:

Mo.

Date Type Hours Reason Down Event System Component-

' Prevent Recurrence 1

2 Rea ctor Report Code 4 Code.5 1

2 Reason 3 Method 4 Exhibit G 5' Exhibit 1

+

F: Forced A-Equipment Failure-explain 1-Manual Instructions ' Salem as" S: Scheduled B-Maintenance or Test 2-Manual Scram.

for Prepara- - Source C-Refueling 3-Automatic Scram.-tion of Data D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam

-Previous Outage for Licensee.

F-Administrative 5-Load Reduction

- Event Report G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161) -

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V cSAFETYERELATEDlMAINTENANCE.

DOCKET'NO:" 50-311 I,

MONTH: J-bDECEMBER 1989:

UNIT--NAME: -SALEML2

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=DATE:

JANUARY-10, 1990 r

COMPLETED-BY:

P. WHITEt

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-TELEPHONE:. -(609)-339-4455' p

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- UNIT EQUIPMENT IDENTIFICATION fu m

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- 2CA301 EMERGENCY COMPRESSOR-INLET '

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(680401326 is FAILURE DESCRIPTION:

REBUILD VALVE: ACTUATOR' h

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'880421201 2

VHT2808 - AF STORAGE TANK' LEVEL-J.',,

_ FAILURE DESCRIPTION:

  1. 2 AUX. FEED STORAGE TANK LEVEL HEAT TRACE. CHECK:

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Li: 890926084

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'2LI529

.22-S/G LEVEL INDICATION beU

. FAILURE. DESCRIPTION:

22 S/G LEVEL CONTROLLING HIGH/L TROUBLESHOOT p: '

s' fi 891229078.

2 2RA10153 - 2R41A p,

FAILURE DESCRIPTION: -NO COMMUNICATION BETWEEN LOCAL &

REMOTE /' TROUBLESHOOT-910122006 2

22SW57 -122 CFCU SW INLET FAILURF DESCRIPTION:

22.CFCU SW INLET VALVE / CALIBRATE POSITIONER p

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W :'MAJORLPLANTz MODIFICATIONS ~

DOCKET NO: 311:

L fMONTH:L - DECEMBER ^ 1989:

UNIT NAME:' SALEM 2-E..<

"DATE:, JANUARYT10;-1990'-

COMPLETED BY:

P;-WHITE-

-TELEPHONE: l(609)'339-4455 p

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PRINCIPAL SYSTEM DESCRIPTION-c.

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RER Controls This-design change relocated RHRiRoom.

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2SC-01608:

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Cooler damper controls!to provide separation:as per. Appendix R requirements.

2SM-00228;

. Aux..LFeedwater This design change" installed'an:.

overspeed test device'and new cover:

'on theLwoodward governor.on 23-Aux.--

Feedwater Pump.

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i DCR'- Design Change Request

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1 MAJOR PLANT MODIFICATIONS DOCKET NO:

50-311 s

-MONTH:

DECEMBER 1989 UNIT NAME:

SALEM 2 DATE:

JANUARY 10, 1990 COMPLETED.BY:

P. WHITE TELEPHONE:

(609) 339-4455

/

2SC-01608 This design change relocated RHR Room Cooler damper

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controls to provide separation as per Appendix R.

requirements.

There was no change,to any plant process or 4

discharge or to the environmental impact of;the plant.- No unreviewed safety or environmental questions are involved.

'2SM-00228 This design change' installed an overspeed test device and new cover on the woodward governor on 23' Aux. Feedwater-Pump.

This allows testing of the overspeed trip mechanism on the Terry Turbine.

There was no change to any plant l

process or discharge or to the environmental impact.of the-plant.

No.unreviewed safety or environmental questions are-involved.

DCR - Design Change Request

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'A-SALEM: GENERATING STATION' MONTHLY OPERATING

SUMMARY

- UNIT 2 DECEMBER 1989 SALEM UNIT'NO. 21

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. e The-Unit began the period operating at full power and, with.the. --

exception of several minor-load reductions for: turbine valve testing,-

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_ continued to operate at full power throughout the entire period..

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l SAFbTY1RELATED MAINTENANCE; DOCKET NO:

50-311 E

' HONTH:?- DECEMBER 1989 UNIT NAME:- SALEM'2 4

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DATE:

JANUARYJ10, 1990-COMPLETED BY: :P. WHITE iI f TELEPHONE:. ~(609)-339-4455 s

- MONTHLDECEMBER 1989 j.

. 1.. ;. Refueling [information.has changed from last month:

.YES NO x

L 2f.

Scheduled date for next refueling:

March 31, 1990-E. -

3L,

-Scheduled date for restart following refueling:

-May 24. 1990

~4 '. Ja)L Will Technical Specification changes or other. license amendments.

E

be required?

YES NO NOT DETERMINED TO DATE.

x b); Has:the' reload fuel design been reviewed by the Station Operating-Review Committee?:

'YES-NO x

If no, when is it scheduled?:

February 1990 5 ;- Scheduled"date(s)-for submitting proposed licensing action:

January 1990

' 6. : Important11icensing considerations associated with refueling:

7.

' Number of Fuel Assemblies:

a.

Incore 193 b.

In Spent Fuel Storage 224

'8.

Present licensed spent fuel storage capacity:

1370 Future spent fuel storage capacity:

1170 g

9.

Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

March 2003 8-1-7.R4 1

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