ML20076H749

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Monthly Operating Rept for May 1983
ML20076H749
Person / Time
Site: Salem PSEG icon.png
Issue date: 06/10/1983
From: Miller L, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8306200132
Download: ML20076H749 (12)
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AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-311 Unit Name Salem # 2 Date June 10, 1983 Completed by L.K. Miller Telephone 609-935-6000 Extension 4455 Month May 1983 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe-NET) 1 0 16 0 2 0 17 0 3 0 18 0 4 0 19 0 5 0 20 0 6 0 21 0 7 0 22 0 8 0 23 0 9 0 . 24 0 10 0 25 0 11 0 26 0 12 0 27 0 13 0 28 0 14 0 29 0 15 0 30 0 31 0 L

P. 8,1-7 R1 p ([h I I I B306200132 030610 PDR ADOCK 05000311 R pm

OPERATING DATA REPORT Docket No. 50-311 Date June 10, 1983 Telephone 935-6000 Completed by L. K. Miller Extension 4455 Operating Status

1. Unit Name Salem No. 2 Notes
2. Reporting Period May 1983 l
3. Licensed Thermal Power (MWt) 3411
4. Nameplate Rating- (Gross MWe) 1162
5. Design Electrical Rating (Net MWe) 1115
6. Maximum Dependable Capacity (Gross MWe)1149
7. Maximum Dependable Capacity (Not MWe) 1106
8. If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A
9. Power Level to Which Restricted, if any (Net MWe) O
10. Reasons for Restrictions, if any REFUELING OUTAGE This Month Year to Date Cumulative
11. Hours in Reporting Period 744 3623 14329
12. No. of Hrs. Reactor was Critical 0 470.3 10925.9
13. Reactor Reserve Shutdown Hrs. 0 3.3 38.9 14.-Hours Generator On-Line 0 459.4 10796.6
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 0 1109383.2 31625932.2 17.' Gross Elec. Energy Generated (MWH) 0 257340 10273590
18. Net Elec. Energy Generated (MWH) (2248) 227030 9800677
19. Unit Service Factor 0 12.7 75.3

.20. Unit Availability Factor 0 12.7 75.3

21. Unit Capacity Factor (using MDC Net) 0 5.7 61.8
22. Unit Capacity Factor (using DER Net) 0 5.6 61.3
23. Unit Forced Outage Rate 0 8.6 3.5
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

N/A

25. If shutdown at end of Report Period, Estimated Date of Startup:

July 2, 1983 26.-Units _in Test Status (Prior to Commercial Operation) :.

Forecast Achieved Initial Criticality 6/30/80 8/2/80 Initial Electricity 9/1/80 6/3/81 Commercial Operation 9/24/81 10/13/81 8-1-7.R2 Page 3 of 12

UNIT SHUTDOWN AND POWER REDUCTIONS Dockat No. 50-311 '-

REPORT MONTH May 1983 Unit Name Salem No.2 Date June 10, 1983 Completed by L.K. Miller Telephone 609-935-6000 Extension 4455 Method of Duration Shutting License Cause and Corrective No. Date Type Hours Reason Down Event System Component Action to 1 2 Reactor Report Code 4 Code 5 Prevent Recurrence Nuclear 3-046 1/21 S 3121.6 C 4 ---

HA GENERA Normal Refueling Misc Major 83-046 1/21 S 3121.6 C 4 ---

HA TURBIN Condenser Overhaul Major Turnine Overhaul 83-046 1/21 S 3121.6 C 4 ---

HC HTEXCH Gen Overhaul Items Generator Major Over-83-046 1/21 S 3121.6 C 4 ---

CA FUELXX haul (Gen Overhaul Item) 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)

Page 4 of 12

. MAJOR PLANT MODIFICATIONS DOCKET NOs 50-311 REPORT MONTH MAY 1983 UNIT NAME: SALEM 2 DATE: June 10, 1983 ,

COMPLETED BY: L. K. Miller TELEPHONE: 609/935-6000 Ext. 4455

  • DCR NO. PRINCIPLE SYSTEM SUBJECT 2EC-1096 Electrical Add a fuse in series with primary device on each electrical penetration circuit.

2EC-1104 Control Room Overhead Replace existing annunciator windows with Annunciators (X240) temporary "Dymo" labels attached with new permanently engraved annunciator windows.

2EC-1457 Heating Water Reroute heating water piping to alleviate condenser retubing interferences.

2EC-1494 N, H , CO and Turbine Reroute N , H , CO and turbine oil vent 2 2 2 2 2 2 Oil Vents piping discharge side of No. 23 Main Condenser shell.

2EC-1570 Turbine Auxiliary Cooling Replace valves TC-120,129,138 and 147 with plug valves of similar construction.

2EC-1599 Pressurizer Overpressure Perform modifications to valves 2PR47 and Protection 2PR48.

2EC-1609 Reactor Coolant Install in-line orifice on Barksdale pressure switch in #21, 22, 23 Reactor Coolant Pump Lift Oil Systems. The orifice is to be .008" in diameter.

2SC-0454 Reactor Coolant / Reactor Install new coupling, Part #C119D31 in Vessel Head place of existing Marman clamps, Part

  1. H 1002306 during reassembly of all five incore instrument conoseal joints in accordance with Station Maintenance Procedure M8C-1.

l 2SC-0503 Steam Generator Feedwater Replace 21A&B/22A&B steam generator feed pump turbine lube oil coolers with plate type heat exchangers of alternate material.

2SC-0907 Turbine Generator Change overspeed trip setting on the l

Unit 2 turbine generator to 1854 rpm or 3%.

2SC-0933 Main Turbines Install grounding braids on the shaft of #2 Main Turbine L.P.

2SC-1033 Turbine Low Vacuum Trip Provide a suitable replacement for 2PD-188.

l and Alarm 2SC-1063 Structural Design or fabricate reinforcement to radiation shield beams on El. 151',

  1. 2 Unit containment access hatch.
  • DESIGN CHANGE-REOUEST 8-1-7.R1 Page 5 of 12

i MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH- MAY UNIT NAME: Salem 2 ,

DATE: June 10, 1983

- COMPLETED BY
L.K. Miller
TELEPHONE: 609/935-6000 X4455 1-
  • DC R NO . . 10CFR50.59 SAFETY EVALUATION 2EC-1096 The change provides extra protection in the event of short

. circuits in the electrical penetrations. No unreviewed safety or environmental questions are involved.

I 2EC-1104 This change improves _the presentation of alarm information and does not alter any function. No unreviewed safety or E environmental questions are involved.

! 2EC-1457 This change to'the heating system does not affect.

presently performed safety analysis nor does it create any new hazards. No unreviewed safety or environmental questions are involved.

l.

.2EC-1494 These changes do not affect presently performed safety analysis nor does it create:any new hazards. No unreviewed safety or environmental questions are involved.

2EC-1570 This system does not affect the safe shutdown of the-plant, accident mitigation, or1 radioactivity release, nor 1- does it affect'the plant discharge. No unreviewed safety or environmental questions are involved.

2EC-1599 The valve internals modification'is'to improve their performance.. This-modification will not affect any plant process or discharge. No unreviewed safety or _

i environmental questions are involved.

l2EC-1609 This system does not affect the safe shutdown of the

! plant.- The design change has no effect on the plant l discharge. No unreviewed safety or envir.onmental'

! questions are involved.

2SC-0454 This new style coupling has been in service in Unit No.. l'

since 1980'with no adverse effects. No unreviewed safety

! or environmental questions are involved.

2SC-0503 These; replacements will upgrade the heat exchangers with  ;

more erosion resistant material. No unreviewed. safety or environmental questions are involved.

J

  • Design Change Request Page 6 of 12 i

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MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-311 REPORT MONTH MAY UNIT NAME: Salem 2 DATE: June 10, 1983 COMPLETED BY: L.K. Miller TELEPHONE: 609/935-6000 X4455 x

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still remain within the standard Westinghouse

. s recotunendations. No unreviewed safety or environmental questi.ons are involved.

_ _ 2SC-0933 This change does not affect the safe shutdown of the plant

-nor does it alter any plant process or discharge. No unreviewed safety or environmental questions are involved.

2,SC-1033 'There is no change in the function of the switches. This Y- \ '

modification will not alter any plant process or discharge. No unreviewed safety or environmental

\ questions are involved.

a 2SC-1063 Pdovision of a rigid setting surface for the concrete sh'ield blocks in front of the equipment hatch will not affect safe shutdown of the- reactor or any plant process or dispharge. No unreviewed safety or environmental

, questions are involved.

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PSE&G SALEM GENERATING STATION SAFEIY RE[ATED WORK ORDER IOG SALEM UNIT NO. 2 .

WO NO DEPT UNIT EQUIPMEIR IDENTIFICATIm 909767 MD 2 22 CC HT EXCHANGER FAILURE DESCRIPTIm: SERVICE WATER IN HEAT EXCHANGER. C21112.

Cutc<rt:nVE ICTION: FIXED BAD 'IUBE ROW 16 'IUBE 47. 821122.

909845 MD 2 22 GILLER CmPRESS FAIIURE DESCRIPTIW: SUPPORT 'IHERMAC IN REPIIDEMENT & 22 CHTTIER CmPRESSOR. 821122.

CORR W 1VE ICTIm: INSTAT.T.m 22 GILLER ONPRESSOR. 821201.

910227 MD 2 VALVE, 230C293 FAILURE DESCRIPTIW: LEAKS BY SEAT. 830104.

CORRECTIVE JCfION: MTCHINED PICK SEAT, IAPPIO Z: bDY SEAT, SKIM CUT DISC, BLUE CHEIZED 100X.

922099 MD 2 21 CWP COOLING PUMP FAIIURE DESCRIPTIm: EXCESSIVE OIL LEAK m OUIBOARD PUMP BEARING. 830118.

CORRECPIVE ACTION: REPINTD CUlTOARD OIL SFAL AND GASKET ON BEARING !INSING. 830323.

922775 MD 2 COTE AIR IOCK EL 130 FAIIURE DESCRIPTIm: REPAIR AIR IOCK INNER DOOR. 830319.

COlo(EL:nVE ACTION: REPIN'FD POIJER BEARING. 830320.

922777 MD 2 VALVE, 2RH20 FAILURE DESCRIPTIm : 2HI20 LEAKING APPROX 1 GPM AT BCDY TO BCNNET FLANGE. 830220.

Cutu<tI;nVE ICTION: F00ND ALL SIUDS IDOSE (HAND TIGHT) . SIDGGED UP ON NUTS AND TIGfrENED IDOSE PICKING GLAND. 830324.

Page 8 of 12

.P S E E'G SALEM GENERM'ING SDLTIN

.a SAFETY REUGED WCRK CEDER IOG ~

S5IR1 UNIT NO. 2 e

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WO NO DEPT LNIT EQUIPMENT IDENTIFICATICN a

923787 2 2 VALVE, 2SJ4 3

FAIIURE DESCRIPTICN: VALVE SFAT SEEMS 'IO BE IEAKING 'IHROUGH. 830321.

! CORRBCTIVE AcrION: RESET Tuy1E SWTICH 'IO 2 AS PER ENG IEITER. 830331.

! 922794 m 2 21 CHARGING IUIP FAIIURE DESCRIPTIW: AUX OIL IU4P D S N0f STARr MIEN 21 CEARGING RMP TAKEN OUT CF SERVICE. 830322.

CNRECTIVE ACTION: PEREMMED M31 m 2PD-8488 AND 2AIH6-762. 830322.

922795 FD 2 CONr AIR IOCK EL 100 FAIIURE DESCRIPTIN: AIR IOCK CIMER DOOR DNS N0f SHUT PROPERLY. 830322.

CORRBCTIVE ICIICE: BOLTS CN BEARING HOUSING IOOSE AIO SWE WERE OUT. RETIGf1 DIED AND RE30RQUED.

830322.

922803 MD 2 VALVE, 22SW20 ,

FAIIURE DESCRIPTICN: VALVE WILL N0f TERATE ELECTRICALLY. 830323.

CmRECTIVE ACTION: REPIACED MUNR OPERA 10R AND HEATER OVERIODS. TESTED SAT. 830324. .

i i 922815 E 2 CONr AIR IOCK EL 100 i I

FAIIURE DESCRIPfICN: C1HER DOOR NDP CIDSING RIGHr. 830327.

CORRECTIVE ACTION: REPIACED BROKEN BCLT N HAND WHEEL. 830328. t t

924696 MD 2 EUEL TRANSFER SYSTEM t i

d FAIIDRE DESCRIFf1CE: UPDDER DTS N0f TERATE PROPERLY. 830321.

i CORRECTIVE ACTICN: UPDOER FATTm OPEN CN 'IHE BRAKE SCKENDID. REPIACED SCLENOID WITH CNE FRCM UNIT 1. 830322.  ;

i Page 9 of 12 i

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PSE&G SAIJM GENERATING STATICN

. i SAFEHT REIATED WWK ORDER IOG SAI2M UNIT NO. 2 4 WO NO DEPT WIT BQUIIMNP IDENTIFICATIN 924726 E 2 CWP AIR IOCK EL 130

, FAIIURE DESCRIPfICN: IA'IDI anTIER W IttiER DOOR BBOKEN. 830324.

CORRECTIVE ACf1N: REPIACED Bf7JFR AND CCTIER PINS. 830324.

t 993018 m 2 21 STEAM GENERA'IOR FAIIURE DESCRIPTIW: PERE 0RM EEDY CURRENT EXAM IAW T/S 4.6.6,0. 820606.

CORRECTIVE ACTION: 100% T '!UBES WERE EXAMINED IN IK7f AND CGD IJES. NO 'IUBES PIDGGED. 830325.

993019 m 2 22 STEAM GENERA'10R FAIIERE DESCRJTIW: PERE 0RM EDDY CURRENP EXAM IAW T/S 4.4.6.0. 820606.

, CORRBCTIVE ACTIW: 100% T 'IUBES WERE EXAMINED IN BCDI HOP AND CGD IES. 'IWO (2) 'IUBES WERE l PLUGGED. 830325. .

I j 993020 MD 2 23 STEAM GENERMOR i

FAIIDRE DESCRIPTIW: PEREORM EIEY CIJRRE!ff EXAM IAW T/S 4.4.6.0. 820606.

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CORRECTIVE ACTION: 100% T 'IUBES WERE EXAMINED IN BUITI HOT AND CGD LEGS. NO 'IUBES WERE PIDGGED.

830325.

993021 MD 2 24 STEAM GENERMER FAILINE DESCRIPTICN: PEREORM EEDY CURRENT E'.AM IAW T/S 4.4.6.0. 820606.

l CNRECTIVE ACTION: 100% T 'IUBES WERE EXAMINED IN BJrH hor Am CGD LEGS. NO 'IUBES PIDGGED. 830325 1

Page 10 of 12 1

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4 SALEM UNIT 2 r

OPERATIONS

SUMMARY

REPORT  !

MAY 1983 i.

The First Refueling Outage of Salem Unit No. 2 commenced on January ,

l 21, 1983, and has continued through the month of May.

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REFUELING INFORMATION DOCKET NO.: 50-311 COMPLETED BY: L.K. Miller UNIT NAME: Salem 2 DATE: June 10, 1983 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month' May 1983

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: March 31, 1984
3. Scheduled date for restart following refueling: June 10, 1984
4. A) Will Technical Specification changes or other license amendments be required?

YES NO X NOT DETERMINED TO DATE 6/1/83 B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X If no, when is it scheduled? February 1984

5. Scheduled date (s) for submitting proposed licensing action:

March 1984 (if required)

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A) Incore 193 i B) In Spent Fuel Storage 72

8. Present licensed spent fuel storage capacity: 1170 Future spent fuel storage capacity: 1170
9. Date of last refueling that can be discharged
to spent fuel pool assuming the present licensed capacity
March 2000
8-1-7.R4 Page 12 of 12

O >SEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station June 10, 1983 Director, Office of Inspection and Enforcement U .~ S . Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In Compliance with Section 6.9, Reporting Requirements for the Salem

. Technical Specifications, 10 copies of the following monthly operating reports for the month of May 1983 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Summary of Safety Related Maintenance 6 Operating Summary Refueling Information Sincerely yours, J. . pko, Jr.

General Manager - Salem Operations LKM:sbh cc: Mr. J. Allan Acting Regional Administrator USNRC Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission l

Washington, DC 20555

! -Enclosures y ,

l Page l of l2 8-1-7.R4

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l The Energy People 95 21fd (20W '181

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