ML20065A724

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Jan 1983
ML20065A724
Person / Time
Site: Salem 
Issue date: 02/10/1983
From: Miller L
Public Service Enterprise Group
To:
Shared Package
ML20065A705 List:
References
NUDOCS 8302220138
Download: ML20065A724 (11)


Text

<

4 OPERATING DATA REPORT Docket No. 50-311 Date Feb. 10, 1983 Telephone 935-6000 Completed by L.

K.

Miller Extension 4455 Operating Status 1.

Unit Name Salem No. 2 Notes 2.

Reporting Period January 1983 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 (Net MWe) 1106 8.

If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason 9.

Power Level to Which Restricted, if any (Not MWe) None

10. Reasons for Restrictions, if any N/A This Month Year to Date Cumulative
11. Hours in Reporting Period 744 744 11450
12. No. of Hrs. Reactor was Critical 470.3 470.3 10925.9
13. Reactor Reserve Shutdown Hrs.

3.3 3.3 38.9

14. Hours Generator On-Line 459.4 459.4 10796.6
15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1109383.2 1109383.2 31625932.2
17. Gross Elec. Energy Generated (mm) 257340 257340 10273590
18. Net Elec. Energy Generated (MWH) 236825 236825 9810472
19. Unit Service Factor 61.7 61.7 94.3
20. Unit Availability Factor 61.7 61.7 94.3
21. Unit Capacity Factor (using MDC Net) 28.8 28.8 77.5
22. Unit Capacity Factor (using DER Net) 28.5 28.5 76.8
23. Unit Forced Outage Rate 8.6 8.6 3.5
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

Refueling Outage, January 22, 1983, 18 weeks

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

May 9, 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 10/31/81 8-1-7.R2 Page 2 of 12 8302220138 830210 PDR ADOCK 05000311 R

PDR

AVERAGE DAILY UNIT POWER LEVSL Docket No.

50-311 Unit Name Salem # 2 Date Feb. _10, 1983 Completed by L. K. Miller Telephone 609-935-6000 Extension 4455 1

Month January 1983 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 628 16 496 2

587 17 548 3

588 18 486 4

257 19 518 5

64 20 492 6

312 21 437 7

279 22 0

8 442 23 0

9 536 24 0

10 569 25 0

11 534 26 0

12 565 27 0

13 525 28 0

14 542 29 0

15 525 30 0

31 0

Pg. 8,1-7 R1 Page 3 of 12

Docket No.

50-311 Unit Name Salem # 2 Rept. Month Feb. 1983 Page 2

Method of Shutting License System Component Cause and Corrective No.

Date Type Duration Reason Down Event Code Code Action to 1

Hours 2

Reactor Report 4

5 Prevent Recurrence 83-044 1/17 S

110.4 C

5 RC Vessel Core Coastdown Nuclear Generator Major Over-83-046 1/21 S

241.6 B

5 HA General haul (Gen'l Items)

Major Turbine Overhaul 83-046 1/21 S

241.6 B

5 Turbine General Overhaul Items Misc. Major Condensor 83-046 1/21 S

241.6 B

5 HC HT EXCH Overhaul Nuclear 83-046 1/21 S

241.6 C

5 CA FuelXX Normal Refueling 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

UNIT SHUTDOWN AND POWER REDUCTIONS Docket No. 50-311 REPORT MONTH January 1983 Unit Name Salem No.2 Date Feb. 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 RC Vessel Core Coastdown Nuclear 83-010 1/1 S

56.0 C

5 Traveling Screen / Trash 83-012 1/1 F

502.4 A

5 HF Filter Racks / Canal Screens RC Vessel Core Coastdown Nuclear 83-014 1/3 S

160.0 C

5 83-016 1/4 F

19.7 A

3 HA Turbine Turbine Trip Devices Other Nuclear Reactor 83-018 1/5 F

4.5 A

3 CA Vessel Problems Miscellaneous83-020 1/5 F

3.1 A

3 83-022 1/5 F

2.5 A

3 83-024 1/6 F

40.0 A

3 83-026 1/6 F

13.4 A

3 83-028 1/8 F

11.0 A

3 83-030 1/8 F

21.0 A

3 Traveling Screen / Trash HF Filter Racks / Canal Screens83-032 1/9 F

29.5 A

5 RC Vessel Core Coastdown Nuclear 83-034 1/10 S

160.0 C

5 Traveling Screen / Trash 83-036 1/10 F

29.0 A

5 HF Filter Racks / Canal Screens83-038 1/12 F

2.3 A

5 Condensor Tube Leaks, HC HT EXCH Inspection for Leaks83-039 1/12 F

227.9 A

5 Traveling Screen / Trash 83-040 1/13 F

14.2 A

5 HF Filter Racks / Canal Screens83-042 1/13 F

3.7 A

5 HF Filter Page 5 of 12

SORTFD Sy SaLFM GFNFG4TTNC 9TATTON DATF 01/17/A3 0FP45TuENT, WOEM ODOFR Nn.

SAFFTY del. ATFn FutilPMFNT BOOM nenFw lng - tlNIT 7 paGF 0001 t02K nIDEO NU^tCED nEPl EnUTP"ENT InEN T TF TC A T TOu FxPLANaTION OF wnRW PEOFnRMEn 700000 M

VALVE,2MM*15 nEMCDIPTTON nr Po pLFM, nURING MARwUP nF MAIN STFAM LINES. 214S15 n

SAFETY VALVE LIFTEn ann FATLFD in RESEAT.

P20706 to M2-173 LFR 87-059 CORGECTTVF arTInN, S/G PRFSSURE W AS RFO'8CFD TO A3n PSIG AND THF VALVr DESEalFD. 734$15 nAs GAGGED SHUT J

ann TRTP SFTPnTNTS RFDHCFO in mst.

.i Q16901 M

CONT FAN CONT UNIT,75 nESC#IDTTON OF POnRLFM, LEAN ON PRT4aWV COTL. 821171 IR a2-478 LER 42-135 CnRRECTivF ArTinN, RE*ATRFD LFAKACE WTTM RELZnNA. A71122 4177C4 u

PetMP,71 CHitLFR RFCTRC DESCRIPTTHN OF PRn LFM, PH"P RFARING LFAKS BADLT. A21210 a

CnRRECTTVT' arvinN,

  1. EPLACFO RFADINGS, OTL AND MFCHANICAL SfALS. 471719 417871 M

CnNT FAN COTL UNIT,73 pr Pe nLFM, 9ERvfCF WATED LEax in CONTAINMFNT FRnM DESC#IpTTON n

7 5 CONT AINWENT F AN COIL tfNT T.

221174 TR A7-429 IED A2-116 CDROFrTTVr ArYinN, THF LEANTNG COTL MAS HLANKFD nrF.

  1. 21C%b u

VALVE,27CVl99 Page 6 of 12

50)TFD By SALFM GFNFHATTN4 MTATTON oATF- 01/17/81 DEPAWTMENT, WOOK 000FR NO.

S AF FTv PEIATFn FQlf!DMFNT WOok ORDFW lng - ItNIT 7 PAGF On07 WO2K

0
nE#

NUM7,F3 nEPT EQUTPMENT InENTTFTCATinM FXPLANATTON nF wnRW PERFnRMEn DESC#IPTTnN OF PRnRLFM, VAlVF APPEAR 9 TO HAvF RLnhN DIAPHRAM, M21027 CnRRfrTIVF AcTInN, REPLACFD BnNNET ann n!APHRAM. 821128 449558 M

VALVE,27SW396 nESC'I*TTOM OF P#nALFM, VALVE IAMS Op AFTER FIVE TI'RNS EITHER DIRECTTON. 61063n CnpotrifvF AcTinN, REPLACFD VALVE. 421173 984C91 M

VALVE,2 MMS 171 nESCDIPTTON OF P9nRLFM, VALVF LFAMINC TH90ltGH.. v 7 090 8 i

CORDECTTVF ArTION, RE01ACFD PLOG AND MTFM A95V AND REPLACE 0 DIAPHWAM IN VAlVF OPFRATnW.

991079 4

VALVE.21M*46 nESC#IPTTON OF PpnRLEH, REPLACF DI9TnwTEn HAMGe?D??ADM. 821078 TR 87-407 CnHDEPTIVF ArTInN, RFplaCrn HANGFD awp.

I 991n7s M

VALVE,27SW177 po RLFM, val.VF alND9 MECHANICALLY. A2n602 DE S C R i o T T U*! np n

TR 87-479 COHOECTTVF a r f Inia, SEPLACFD CLAVITROL ftIBF RUNOLE IN V Al.VF.

821123 1 991203 M

CONT ago LOCK El 13n 4

1 i

. Page 7 of 12 i

90?TED BY SALFM GFNFWATINC MTATTOM Dalf 01/17/A9 OEPADTwfMT, MURK ODOF4 Nn.

.SAFFTV REL ATEn rNHIPWFNT WODM HRDFW LOG - ilN ] Y 7 PAGE On09 WORK 0%nE2 NUM;ED nEPT E ntl T P*E M T IDFWTTFTCATTOM FyptANATTOM OF mnNw PEDFORMEn nFMCRipTION np ppnALFM.

TNNER nOng Has LWCFSMIVE SFAI. LEAKAGF.

421t?! ID 92-480 LFR 82-14n CnHRECTTVF ACTION, TNNFR DOOR SF at WAM REPOSITInNFD IN TT9 RETATNTNG mRnOVE. A21171 703010 p

S/G STEAM FLOW CH 2,21 DE9CDIPTION OF PRORLFM, CHANNEL HICH TPIP SETPnINT EXCFEDS T/S LIMIT. M7072n TR-87-186 LER 82-066 rnR#FrTIVF ACTION, CAPACITHD FATLIIRFS IN CHANNEL N0nULF9 ATTRISHTFD in NATURAL DECRFDATTinM OF COMPONENTS. Al l CAPACITnR9 TN THE AFFErTFD MnDHLFS >FRF DEPLACED.

703012 A

RPC LOOP FLOW CH3,24 DE9COIPTTON nF PRnRLFM, CHANNEL TNDICATION ERRA7???TTC. R20724 IR 87-194 ItR M2-069 CnwoF CT T VF ACTInN, FATLFD FFRDITE Stun TN THE FLOW TRANMMTTTFD. WFPt. APED TWANMMTTTLR.

400545 P

ACCH 4HLATnR9,23 4 24 DE9CRIPTTON OF PenRLFM, ACCUMHIATop IEVEL nETEDMINFD in RE LFSM THAN T /S RFultIPEn. 870727 TR RP-180 lE# A2-060 CPROECTTvF ACTinN, A SIGHT CLASM LEVEL INDIFATOR WAM TN9TALLfn MITH RFADING9 RETNn TAKEM FVERY a HRS. CHANNFLM Mil l RF PALIPRATFD AT NEWT DUTAGk.

Page 8 of 12

SO2TFD BT SALFM GFNrRATTNC

  • T A T T 0*'

OATF 01/17/81 MEPARTMENT, WOOK ORDER Nn.

SAFFiv DFtATED FuMIPMFNT WOQK OROFR lng - UNIT 7 p A GF.

0004 WOIK ORDEC -

NUX8E3 nEPT EQUTPMENT TOENTTFTCATTON EXPLANATTON nr wnRF PERFORMED 916875 RMS 20178 OE9CRIPTTON nF POnoLFM, rHANNEL FATLFD FAR SFCnNn TTWE inDAY. SEF WO*916897 871n17 CORRECTTVF ACTinN, RESET unMIT00 ann CHFCWED METPnINTM MAT.

821018 916870 P

RMS,2RIPH nESCRipTION OF PDn4LFM, CHANNEL TS F AIL En.

CnRoFCTTvr ACTION, TRTED DEMETTTNG M0nULES, NO FFFECT. TURNFD POWER 90pPLY SWITCH AFF THEN ON. RESTORED METPOTNTS. VF#TFTED ALARM SAT.

916872 P

RMS,29198 OESCOTPTTOM nF Po pLrM, MpTKTNG HirH CAUMING BIOwnndN TSnLATTON nN n

72 S/G.

CnR*ECTTVF AcTinN, PEMET unNIT00 CHECKFD SFTPOTNTS SAT.

P AI. CHFCK MAT. IP R2-447 916817 p

RMS 2017H nESCpipTTOM nF pu PLEM, CHANNEL TN NO MCAN. 821017 10 42-445 n

CORRFrTTvr ArTinN, total uCNIT00 A L t. F'M.

RFSFT AND VERTFTED nPFRATinH. 871nI?

917393 P

Rus,2R12R nEMCDIPTTON nF P90RLFM, CHANNEL TN NO 9CAN. TR 87-44R Page 9 of 12

30?TED Oy s4Lrg GFNFRATTNG 9TATTON DATE 01/f7/83 nEPAWTMENT, Wook ORDFN N9 SAFriv REIATED FQHIpMFNT POON OpuTR lng - O'117 7 PAGF On09 COYM n:R(*

NUMBE2 DEPT EOUTPMENT IDENTTFTCATTON FXPLAf44TTON OF hqRK PERFnRMED CORDECTTVF AcTTON, REPLACFD RAD NF595 TTMER AND RHWNT 00T FATL LTGHT. TESTFD SAT.

(2130$

P R"S,2Ri?A nERC#IPTTON OF PDORLFM, CHANNEL FATLFn. A21107 ID R2-423 LED A2-143 CnRRECTTVF ACTION, CLFANEn AND REME4TFD MODHLFS. ADJUSTED DISCRIMTMATOR VOLTAGF. RFPLACED THREE MHORTED RATTFRIES IN RFMOTF POWER MupPLY.

PERFORMEO FliNCTInNAL SAT.

T213R7 P

RMS,2R12A DE9CRIPTTON OF PpnRLFM, CHANNEL _ FATLFD. 821107 IP A2-418 LER 82-133 CnR#ECTTVF ACTION, PHANNEL LOCKFD UP. RFSFT. OPFRATES SAT.

932@QS P

VALV00,73MW65 DESCRIPTTUN nF PRnRLFM, 9EDVTCF WATFD FLnW THROUGH 23CFCl3 LOW.

A2117A CDROErTTvF ArTION, F0tlNn VAtyF tot TO 19% CLOSED AND ACTUATnR/v4LVE CONNECTTNG LINN BRONEN.

OEPLACFD CONNECTTNG LINK, A21206 TOTAL LINES = 0n0106 TOTAL 4-RECS = nn0n21 LAST UPDATE A3nt14 n82347 FNTES C044ANnS FNn OF RilN SBIKPT P9INTS Page 10 of 12

SALEM UNIT 2 OPERATIONS

SUMMARY

REPORT JANUARY 1983 Unit 2 continued to coast down from a power level of 62%

at the first of the month.

There were five reactor trips during the month.

The first trip occured on January 4th due to low pressure in the auto-stop oil circuit during a maintenance activity on the turbine oil system.

The second trip occured from 56% power on January 5th during a surveillance test of the trip breakers.

The turbine tripped on an erroneous signal from the Bypass Reactor Trip breaker.

The next two trips occured due to steam generator Hi-Hi water level during the unit's return to service.

The fifth trip occured on January 6th due to steam generator Low-Low water level.

The loss of power.to the station air compressor resulted in loss of control air to the feedwater regulating valves.

The valves going closed resulted in the Low-Low trip.

The Unit was taken out of service on January 21st at 2222 hrs.

for an annual refueling outage.

1 Page 11 of 12 l

REFUELING INFORMATION Docket No.

50-311-Unit Name Salem #2 Date Feb. 10,-1983 Completed by L. K. Miller Telephone 609-935-6000 Extension 4455 Month January 1983

.l.

Refueling information has changed from last month:

YES X

NO 2.

Scheduled date of 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 NOT DETERMINED TO DATE X

B.

Has the reload fuel design been reveiwed 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 B.

In Spent Fuel Storage 0

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