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| issue date = 01/10/1979
| issue date = 01/10/1979
| title = Monthly Operating Rept for Dec 1978
| title = Monthly Operating Rept for Dec 1978
| author name = MILLER L K
| author name = Miller L
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| author affiliation = PUBLIC SERVICE ELECTRIC & GAS CO. OF NEW JERSEY
| addressee name =  
| addressee name =  
Line 17: Line 17:


=Text=
=Text=
{{#Wiki_filter:e AVERA.GE DAILY lliE Lt.1 1'EL MONTH December 1978 DAY AVERAGE DAILY POWER LEVEL (MWe-NET) 1 950 2 1,005 3 1,100 4 1,051 5 1,115 6 1,074 7 1,132 8 1,104 9 1,031 10 752 11 986 12 1,099 13 562 14 0 15. 0 16 0 Pg. 2 of 15 8.1-7.PJ.
{{#Wiki_filter:e AVERA.GE DAILY lliE   ?Oi'i"E~ Lt. 1'EL 1
DJCKET NO. 50-272 UNIT Salem #1 nA:u: January 10, COMPLETED BY L. K . Miller TELEPHONE . 609-365-7000 DAY AVERAGE DAILY POl'iER LEVEL (MWE-NET) 17 0 18 0 19 0 . 20 0 21 . 5 22 551 23 186 24 259 25 956 26 1,110 27 1,104 28 1,101 29 1,105 30 866 31 1,110 1979 X507 CAn:: January la, 1979 L. K. Miller 6a9_.365-70aa X5a7 l. Onit:Nane:.
DJCKET NO. 50-272 UNIT Salem #1 nA:u: January 10, 1979 COMPLETED BY L. K . Miller TELEPHONE . 609-365-7000 X507 MONTH    December 1978 DAY AVERAGE DAILY POWER LEVEL                    DAY AVERAGE DAILY POl'iER LEVEL (MWe-NET)                                            (MWE-NET) 1            950                                17                       0 2          1,005                                18                       0 3          1,100                                19                       0 4          1,051                              . 20                       0 5          1,115                                21 .                     5 6          1,074                                22                     551 7          1,132                                23                     186 8          1,104                                24                     259 9          1,031                                25                     956 10            752                                26                   1,110 11            986                                27                   1,104 12          1,099                                28                   1,101 13            562                                29                   1,105 14              0                                30                     866
Salem #1* 2. P.epJr1:inq Per.i.c:d:
: 15.              0                                31                   1,110 16              0 Pg. 2 of 15 8.1-7.PJ.
D c ember 19 7 8 3. Licensed Poller* (M<it): ___ 3 __ 3 __ 3 __ 8 ______ _ 4. _ Naueplate Rat:inq (Gross me): __
 
: 5. Design El.ectrical.. (Net : 1 a 9 a -------6.. . Maximlm Cependabl.e.
CAn::           January la, 1979
Cailac::i:ey . : . 112 4 7. MaXimllm:*
                                                                                                      ~BY:                L. K. Miller
OP{>eodabl
                                                                                                        ~::            6a9_.365-70aa X5a7
: e. capa.ci ty* (Net Kie) : 1 a 7 9
: l. Onit:Nane:.             Salem #1*
* a. If Changes Occur ill capacity Ratings' (Itell'S NIJlli:ler 3 'lln:cugh
: 2. P.epJr1:inq   Per.i.c:d:         D ~ c ember 19 7 8
: 7) S.ince Last Report.,.
: 3. Licensed     ~              Poller* (M<it): ___3  __3__3__8_______
Give Reason: NONE 9. J?cwer I.evel. To Which* Fest::ricted, If l!rr:f: (Net Kie") :. __ __..N_o-.N_E"------------......;,----
: 4. _ Naueplate Rat:inq (Gross me): _ _1_1_3_5_~----
: 10. lleascrls For* Restrictions,.
: 5. Design El.ectrical.. Ra.t:inq~ (Net ~) :                     a a 1 9 6.. . Maximlm Cependabl.e. Cailac::i:ey .(Gross:*~) : .             112 4
If };rrrfr ___ N_O_N_E ___ ._. --------------------
: 7. MaXimllm:* OP{>eodabl e. capa.city* (Net Kie) :                   1 a7 9 *
u.. Jblr.3* In. Period. u. Nl.lnD!r.
: a. If Changes Occur ill capacity Ratings' (Itell'S NIJlli:ler 3 'lln:cugh 7) S.ince Last Report.,. Give Reason:
Of. acurs was-Critical.
NONE
: 9. J?cwer I.evel. To Which* Fest::ricted, If l!rr:f: (Net Kie") :. _ ___..N_o-.N_E"------------......;,----
: 10. lleascrls For* Restrictions,. I f };rrrfr ___             N_O_N_E___._.- - - - - - - - - - - - - - - - - - - -
Cumulative 744            8 ,".760 *..          13,2al.
u.. Jblr.3* In. ~q Period.
: u. Nl.lnD!r. Of. acurs     ~ctor      was- Critical.                               556.7          5,113.7                7,656.9
: 13.
: 13.
* Reactor Re.serve Shutdown 744 556.7 a.a 14. liours Generator on-Lina 523. 4 lS. Unit Reserve" Shutdown HOm:s . a. a 1.6. Gress 'Jllel:inal.
* Reactor Re.serve Shutdown               ~urs-.                                        a.a                o.a                  a.a
Energ:{ Generated CMiH> L 5 7 4 , 9 2 6 17.. *Gl::OSS.
: 14. liours Generator on-Lina                                                           523. 4         4,867.4                7,298.a lS. Unit Reserve" Shutdown             HOm:s .                                            a. a                a.o                  a.o 1.6. Gress   'Jllel:inal. Energ:{ Generated CMiH>                             L 5 7 4 , 9 26      14,289,516              2a,984,736 17.. *Gl::OSS. Eleetrical. Energy Galera.te:i ~) .                                 535, 37a          4,786,5ao              6,972,810
Eleetrical.
: 18. Net El.ect:rical. Energy Generated(Mim)                                     5a8, 621         - 4,528, 762            6,586,980
Energy Galera.te:i . 535, 3 7a 18. Net El.ect:rical.
: 70. 4 .             55.6                  55.3 19.
Energy Generated(Mim) 5a8, 621 19. Onit Service Factor 70. 4 . 20. Unit Availability.
20.
Fact:cr ,7a. 4 . . . 21. Unit capacity Factor (Usinq MOC Net) 6 3. 4 22:.. Unit capacity Factor (Usinq DER Net) . 62. 7 23. Unit.Forced:
Onit Service Factor Unit Availability. Fact:cr                                                         ,7a. 4
outage Rate* . 29. 7 8 ,".760 *.. 5,113.7 o.a 4,867.4 a.o 14,289,516 4,786,5ao
                                                                                                      ------      55.6                  55.3 6 3. 4              47.9                  46.2 21.
-4,528, 762 55.6 ------Cumulative 13,2al. 7,656.9 a.a 7,298.a a.o 2a,984,736 6,972,810 6,586,980 55.3 55.6 55.3 47.9 46.2 --------47.4 45.8 44.a 36.E 24. * 'Shutdowns Next 6 M:nths. (Type, Date, and Duration of Ea.ch): . . Unit Refueling 3/31/79 -6/23/79 . . 25. If. Shut:eown At End of. Report l'eri.cid!
22:..
Est:imate!d-Da.te o&#xa3;"Sta,rtup:  
Unit capacity Factor (Usinq MOC Net)
--..;;.N...::.::A.._
Unit capacity Factor (Usinq DER Net) .                                               62. 7               47.4     --------     45.8
_____ ..;._ _____ _ *26. Units In* Test.Status(Prior to* cammcial-Cperaticn):
: 23. Unit.Forced: outage Rate*                                                          . 29. 7              44.a                 36.E
S-l-7.R2 Pg. 3 of 15 INITIAL CRITICALIT'I INIT:rAL
: 24. * 'Shutdowns ScbedUled'~- Next 6 M:nths. (Type, Date,                     and Duration of Ea.ch):
... .
                  .. Unit Refueling 3/31/79 - 6/23/79                             .       .
* a::MME:R:!AI.
: 25. If. Shut:eown At End of. Report l'eri.cid! Est:imate!d-Da.te o&#xa3;"Sta,rtup: --..;;.N...::.::A..__ _ _ _ _..;.__ _ _ _ __
OPERATION Forecast 9/3a/76 11/al/76 12/20/76 Achieved 12/JJ /76 12/25/76 6/3a/77 tn. Dl\TE 78-297 12/09/78 78-305 12/13/78 78-306 12/13/78 78-308 12/14/78 78-309 12/20/78 78-310 12/23/78 78-312 12/30/78 1 F: Forced S: Scheduled 8-l-7.R2 Pg. 4 -15 TYPE 1 F F F' F F F F 2 UNIT SllU'.lin'INS l\NO PCWER REDUCfIONS REPORT MJ!-,m1 December 1978 MIITllOD OF OOR/\TION REl\ooif SHUITING !ilOURS) lXMN RE1\CI'OR 0.0 B 4A 1.04 A 3 33.98 A 4B 144 A 4B 19.58 B 4B 22 A 2 0.0 B 4B Peason: 1\-EquipiEnt Failure(Explain)
*26. Units In* Test.Status(Prior to* cammcial-Cperaticn):
B--Maintenance or Test C-Refueling 0-Regulatory Restdction LICENSE EVEN!' REPOIU t ---------i i ------------E-Operator
Forecast              Achieved INITIAL CRITICALIT'I                                              9/3a/76            12/JJ /76 INIT:rAL EllX:'l'RICI'I"-                                        11/al/76            12/25/76 S-l-7.R2 Pg. 3 of 15             ... .
& License EKamination F-1\dmlnistrative G-operational Error(Explai11)
* a::MME:R:!AI. OPERATION                                           12/20/76               6/3a/77
II-Other (Explain) 3 SYSTEM <Il1PCNENl' moE" CXJOE5 HC FIL'IER HI H'IEXCH HI H'IEXCH HJ HTEXCH HA WRBIN WG zzzzzz HG HTEXCH M3thod: I-Manual 2-Manuai Scram. 3-Autanatic Scram. 4-0ther (Explain) 50-272 DOCKET NO. :
 
UN 11' :Nl\ME: *Sal em #1 ! D/\TE: January 10, 19 79 COMPI,ETF.D DY: L. K. Miller TELEPllONE:
UNIT SllU'.lin'INS l\NO PCWER REDUCfIONS DOCKET NO. :
609-365-7000 X507
50-272            ~
* Cl\USE /\ND amru:cnvr.  
                                                                                                                                      ~~~~--~~~~-
/\CrIOO 'IU PREVENI' RFUJRPJ'NCE Cleaning strainers on 12 Condensate Pump & Steam Gen. Feed Pumps Low-IDw Level, 13 Steam Generator 13 Auxilia:r:y Steam Generator Feed Pump Control Malfunction Repair 13 & 14 Steam  
REPORT MJ!-,m1  December 1978                          UN 11' :Nl\ME:     *Sal em #1 D/\TE:     January 10, 19 79 COMPI,ETF.D DY:       L. K. Miller
.:Leaks #1 Low Pressure Turbine Inspection Volurre Control Tank Relief Valve Flange Leak Oil Change On 11 Condensate Pump & 11 Heater Drain Pump, IDwer Motor Bearing 4 5 Exhibit G -Instructions for Preparation of Data Entry Sheets for Lkensee Event Peport (LEn) File (NUHID--0161)
                                                                                                                                        ~~~~~~~~
Exhibit 1-SLlllE Source A. LOAD REDUCT!ON B. CONTINUATION OF PREVIOUS OUTAGE /
TELEPllONE:       609-365-7000 X507 MIITllOD
MAJOR PLANT REPORT MONTH December 1978 *DCR NO. PRINCIPLE IBC-0430 Solid State.Prat.
* OF OOR/\TION                SHUITING      LICENSE        SYSTEM  <Il1PCNENl'                Cl\USE /\ND amru:cnvr.
SYSTEM System IBC-0444 Main Turbine Lube Oil lEC-0448 Radiation Monitoring System lOD-0037 eves
1 tn.        Dl\TE  TYPE    !ilOURS)    REl\ooif    lXMN          EVEN!'      moE"        CXJOE5                        /\CrIOO 'IU RE1\CI'OR    REPOIU    t                                        PREVENI' RFUJRPJ'NCE 78-297    12/09/78  F          0.0      B          4A          - - -          HC    FIL'IER      Cleaning strainers on 12 Condensate Pump & Steam Gen. Feed Pumps 78-305    12/13/78  F          1.04      A          3          - - -          HI      H'IEXCH      Low-IDw Level, 13 Steam Generator 78-306    12/13/78  F'        33.98      A          4B          - - -i          HI    H'IEXCH      13 Auxilia:r:y Steam Generator Feed i                          Pump Control Malfunction 78-308    12/14/78  F      144            A          4B          - - -          HJ      HTEXCH      Repair 13 & 14 Steam           Gen~ ~llanway .:Leaks 78-309    12/20/78  F        19.58        B          4B          - - -          HA      WRBIN        #1 Low Pressure Turbine Inspection 78-310    12/23/78  F        22          A          2          - - -          WG      zzzzzz      Volurre Control Tank Relief Valve Flange Leak 78-312    12/30/78  F          0.0        B          4B          - - -          HG      HTEXCH      Oil Change On 11 Condensate Pump &
* DESIGN CHANGE REQUEST 8-1-7 .Rl DOCKET NO.: 50-272 UN I. E: Salem #1 DATE: January 10, 1979 COMPLETED BY: L. K. Miller TELEPHONE:
11 Heater Drain Pump, IDwer Motor Bearing 1                    2                                                    3                        4                                 5 F: Forced            Peason:                                              M3thod:                    Exhibit G - Instructions       Exhibit 1-SLlllE S: Scheduled        1\-EquipiEnt Failure(Explain)                        I-Manual                  for Preparation of Data         Source B--Maintenance or Test                              2-Manuai Scram.            Entry Sheets for Lkensee C-Refueling                                          3-Autanatic Scram.        Event Peport (LEn) File 0-Regulatory Restdction                              4-0ther (Explain)          (NUHID--0161)
609-365-7000 X507 SUBJECT Modify Circuit to Assure Closure bf Containment Vent Valves on Safety Injection Modify Level Indicator, Deduc.to:r:
E-Operator Trainin~ & License EKamination F-1\dmlnistrative 8-l-7.R2                    G-operational Error(Explai11)                                                    A. LOAD REDUCT!ON II-Other (Explain)
and Suction Line Check Valve Delete Automatic Fan Coil Unit High Activity Interlock Change Letdown Heat Exchanger Temperature Controller Setpoint from 115&deg; F. to 100&deg; F. Page 5 of 15 DOCKET NO. : 50-272 0 MAJOR PLANT REPORT MONTH December 1978 UN I irtt AME:
Pg. 4 - 15 B. CONTINUATION OF PREVIOUS OUTAGE
__ #_l __________
                                                                                                                                                              /
_ DATE: January 10, 1979 *DCR NO. lEC-0430 lEC-0444 lEC-0448 lOD-0037 10CFR50.59.
 
COMPLETED BY: L. K. Miller TELEPHONE:
DOCKET NO.:   50-272 MAJOR PLANT MODIFICA~NS
609-365-7000 X507 SAFETY EVALUATION This design change will assure that an SI trip will cause the SSPS to trip the Containment Isolation Valves, without regard to the state or histm:y of the Containment Radiation Alarms. This change does not constitu_te an unreviewed safety qUestion.
                                                          ~~~~~~~~~-
Functional operation is unchanged.
UN I .E:       Salem #1
This design change is not Safety Related, nor does it affect the operation of any Safety Related systems. This change eliminates a non-safety grade trip function which could otherwise affect the performance of a safety system. The trip circuitry to be eliminated was originally considered to be reqUired due to assumptions regarding service water pressure versus peak containrrent pressure.
                                                          ~~~~~~~~~~
Recent investigation has determined that the trip function is not reqUired for safety. Tech. Spec. margiris and safety. analysis *are : not affected.
REPORT MONTH    December 1978 DATE:   January 10, 1979 COMPLETED BY:     L. K. Miller TELEPHONE:   609-365-7000 X507
This design change does not affect any safety related funtions, nor does it create any new safety hazards. \_
  *DCR NO.        PRINCIPLE SYSTEM                    SUBJECT IBC-0430  Solid State.Prat. System    Modify Circuit to Assure Closure bf Containment Vent Valves on Safety Injection IBC-0444  Main Turbine Lube Oil      Modify Level Indicator, Deduc.to:r:
* DESIGN CHANGE REQUEST Page 6 of J;,5&deg; I DOCKET NO * : _5,,,_0-_,2.._.7._.2.._
and Suction Line Check Valve lEC-0448  Radiation Monitoring System Delete Automatic Fan Coil Unit High Activity Interlock lOD-0037  eves                        Change Letdown Heat Exchanger Temperature Controller Setpoint from 115&deg; F. to 100&deg; F.
_______ _ SUMJ0.:ARY OF SAFETY RELATED DEPAR'I'MENT Performance UNIT NW:. Salem #1 January 10, 1979 CO!v1_FLETED BY: L. K. Miller P.EPORT MONTH December 1978 -------------
* DESIGN CHANGE REQUEST                             Page 5 of 15 8-1-7 .Rl
WORK ORDER NO. OD-11123 OD-11050 OP-0461 PD-4283 PD-900358 Pb-5244 OD-10804 PD-900359 PD-5202 OD-900514 OD-900582 OD-900614 Page 7 of 15 8-1-7.Rl EQUIPMENT 1LT528. 1FA3542Z-l 1FA3542Z-2 lFA3172Z-2 14SW223. Valves lOVCOOl, 10VC002, 10VC003, 10VC004, 10VC005, 10VC006. 1FT128. lLT-537." ll.C-549A/B 1Rl7B. All Stearn Generator Transmitters.
1FT414. 1LT459A. 10VC006. Valves llSW039 & 13SW039. T :S :SEP HONE: 609-365-7000 X507 FAILURE DESC:K.!:PTION CORRECTIVE ACTION Mismatched Readings From Blewdown Feeder Lines & Cali-I i Other Channels.
brated Transmitter.
l Flow Transmitters Out of Calibrated Transmitters
& Freed Spec. , Frozen Hand.wheel
& Hand.wheel
& Repaired Reach Rod. Failed Reach Rod. Modify SSPS I.A.W. OCR JEC-Completed.
0430. Last Calibration Perforrred Recalibrated. . With Out-Of-Cal.
Test Equip . -Channel Readings Mismatched Blewdown Feeler Lines. Unstable Output No. 1. Replaced Faulty-Capacitors.
-.. Channel Spiking. Replaced Faulty Bistable Printed Circuit Board. Repeated Discovery of Completed Blowdowns.
I Sludge In Feeler Lines. I Channel Readings Mismatched calibrated.-
I Channel Readings Mismatched Calibrated.
No Open Indication On Con-1 Limit SWitch Adjusted.
trol Bezel. Stuck Open. Repaired Control Air Solenoid Valves.
DOCKET. i\10. : 50-272 OF SAFETY RELATED DEPARTY..ENT Performance UNIT
_s_a._l_em
__ #_l ________ _ DA'J.E: January 10, 1979 COMPLETED BY: L. K. Miller l EEPOR!I' MONTH December 1978 WORK ORDER NO. OD-900652 OD-11194 OD-11071 OD-9043 PD-5238 PD-900336 . PD-5235 OD-11125 OD-11132 OD-11133 OD-11184 Page 8 of 15 8-1-7.Rl I EQUIPMENT I I N32 Source Range Detectors.
llA5424. 10CV172. l Batch_ Tank Temp. 1LT460. 11TE411AB.
11PM474B.
tlFT521. 14MS018. 1FT532. 11 Waste Gas Corrp:. . __ TELEP BONE: 609-:-365-7000 X507 FAILURE DESCRIPTION I CORH..ECTIVE ACTION I l I ! i I Channel Readings Mismatched.!
Repaired Loose Connection.
I I Channel Readings Mismatched.I Blewdown Feeler Line. I ! Valve Does Not Remain Open j Replaced Control Air Solenoid When In "Auto" * : Valve. I Does Not Increase Temp. To Calibrated Operating Band. Normal From Cold Condition.
Channel Readings Mismatched.I Replaced Strain Gauge & Re-I Calibrated.
I -Out of Spec. . I Calibrated.
I I --Out of* Spec . Calibrated.
Feeler Line Blown Out. I Reinstalled.
i Diaphragm Ruptured.
I Replaced Diaphragm.
I I I i I Flow Reads Zero. I Recalibrated.
I l Breaker Will Not Close. l Replaced Brush Assigrurent
& I Tightened.


OF SAFETY I DEPART1'IBNT RELATED Maintenance DOC KE January 10, 1979 UNIT N.: D.A: .r:.. : Salem #1 CO.V!PLETED BY: L. K. Miller MONTH December 1978 WORK ORDER NO. MD-3276 MD-3274 MD-3290 OD-11203 OD-11108 I l-MD-3277 OD-900553 OD-10464 MD-1490 OD-900525 OD-900592
DOCKET NO. :    50-272 MAJOR PLANT MODIFICA~NS                                              ~------------------
-OD-900564 MD-900947 Page 9 of 15 8-1-7.Rl TELEPHONE:
0 UN I irttAME: ~-s_a_l_em__#_l___________
609-365-7000 X507 EQUIPMENT FAILURE DESCRIPTION ACTION 12 Service Water Hole in Pipe Between 12SW24 Temporarily patched. Strainer Discharge  
REPORT MONTH December 1978                                  DATE:    January 10, 1979 COMPLETED BY:      L. K. Miller TELEPHONE:      609-365-7000 X507
& 12SW25 Valves. Line ! ' 13 Service Water Hole in Pipe on Discharge Temporarily patched. Strainer Discharge Side of 13SW25 Valve. Line. Service Water Lines Hole in Pipe on Discharge Temporarily patched. Side of 11SW122 Valve. 14 Service Water Packing Gland Leaking. Repacked Valve. Purrp. 11 Waste Gas Comp. Inspect & Repair. Replaced Rotor, Shaft & Bearings.  
    *DCR NO.      10CFR50.59.                     SAFETY EVALUATION lEC-0430  This design change will assure that an SI trip will cause the SSPS to trip the Containment Isolation Valves, without regard to the state or histm:y of the Containment Radiation Alarms. This change does not constitu_te an unreviewed safety qUestion.
----Boric Acid Evapor-Replace Rupture Disc. Replaced Disc. ator. ----14 Fan Coil Unit. Trips While Atterrptihg To Inspected  
lEC-0444  Functional operation is unchanged. This design change is not Safety Related, nor does it affect the operation of any Safety Related systems.
& Cleaned 1B7X 440V Start. Brkr. 11 Seal Water Inj. Hi !iP. Replaced Filter. Filter. 13, 14, & 15 Heater Install Drain Line Supports Completed ED-0076. Vents & Drains. as per ED-0076. -11 Service Water Strainer Runs With Purrp Replaced PD-285 & Calibrated.
lEC-0448  This change eliminates a non-safety grade trip function which could otherwise affect the performance of a safety system. The trip circuitry to be eliminated was originally considered to be reqUired due to assumptions regarding service water pressure versus peak containrrent pressure. Recent investigation has determined that the trip function is not reqUired for safety. Tech. Spec. margiris and safety. analysis *are :
Purrp Strainer.
not affected.
Shutdown & Strainer on Auto. le Diesel. Audible Alarm Not Working. Replaced Hom. lB Diesel. Lube Oil Heater Terrp. *Alarm. Lube Oil Heater Temperature Controller Recalibrated.  
lOD-0037  This design change does not affect any safety related funtions, nor does it create any new safety hazards.
----lB Diesel. Invalid Alarm. ,Recalibrated TD-7211.
                                              \_
1-DOCKET NO.: 50-272 SUMMI>..cRY OF SAFETY RELATED .INTENANCE DEPARTMENT Maintenance UNIT.
* DESIGN CHANGE REQUEST                                        Page 6 of J;,5&deg;
DATE: January 10, 1979 ; REPORT MONTH December 1978 COMPLETED BY: L. K. Miller WORK ORDER NO. OD-11067 OD-11024 JYID-900960 OD-900662 MD-900952 OD-11148 JYID-3251 JYID-3273B OD-11054 OD-11097 PD-5194 OD-900677 OD-900742 Page 10 of 15 8-1-7.Rl EQUIPMENT 12 Waste Gas Comp. 13 Roddrive Vent Fan. Kl 125VDC Battery Charger. #1 Errergency Air Compressor.
 
100' Elev. Con-tainrrent Air Lock. .. . . .
DOCKET NO * : _5,,,_0-_,2.._.7._.2..__ _ _ _ _ _ __
* Fire Pumps. *-* Valve 10MS095. 130' Elev. Con-tainrrent Air Lock Door. 13 Charging Purrp. 13 Service Water Pump Strainer.
SUMJ0.:ARY OF SAFETY RELATED ~NTENANCE                            UNIT      NW:. Salem #1 DJ:.~: January 10, 1979 DEPAR'I'MENT    Performance CO!v1_FLETED BY: L. K. Miller P.EPORT MONTH     December 1978                                       -------------
1Rl4. RC 12-6 Position No. 7 C.B. 14 Service Water Pump. TELEPHONE:
T :S:SEP HONE: 609-365-7000 X507 WORK ORDER         EQUIPMENT              FAILURE DESC:K.!:PTION          CORRECTIVE ACTION NO.
609-365-7000 X507 FAILURE DESCRIPTION CORRECTIVE ACTION Excessive Seal Leakage. Replaced Seal. Trips Breaker. Replaced Fan. Does Not Accept Loading. Replaced Faulty Receiver Diode. Trips on Low Press When Calibrated PD-3819. Started In Manual. Inner Door Broken Bearing. Replaced Bearing. . . -Pump Failed To Start. Reset Timers To Proper Settings Valve leaks. Replaced Valve. *-. --Repair Inner Door. Replaced Inner Door Carn Roller. Piston Packing Leaks. Repacked, Installed Two New Plungers.
OD-11123      1LT528.                Mismatched Readings From        Blewdown Feeder Lines & Cali-I Other Channels.                  brated Transmitter.                        i OD-11050      1FA3542Z-l              Flow Transmitters Out of l
Packing leaks. Repacked.
Calibrated Transmitters & Freed 1FA3542Z-2              Spec. , Frozen Hand.wheel &      Hand.wheel & Repaired Reach Rod.
Channel Failed. Replaced Bistable Card. Ground In Circuit. Replaced Push Button. Vibration.
lFA3172Z-2              Failed Reach Rod.
Repacked Gland.
14SW223.
12-1 12-2 12-3 12-4 12-5 12-6 12-7 12-8 SALEM UNIT I OPERATING  
OP-0461      Valves lOVCOOl,          Modify SSPS I.A.W. OCR JEC- Completed.
10VC002, 10VC003,      0430.
10VC004, 10VC005, 10VC006.
PD-4283      1FT128.                  Last Calibration Perforrred Recalibrated.
                                          .With Out-Of-Cal. Test Equip PD-900358    lLT-537."                Channel Readings Mismatched Blewdown Feeler Lines.
I Pb-5244      ll.C-549A/B              Unstable Output No. 1.          Replaced Faulty-Capacitors.
OD-10804      1Rl7B.                  Channel Spiking.                Replaced Faulty Bistable Printed Circuit Board.
PD-900359    All Stearn Generator    Repeated Discovery of            Completed Blowdowns.
Transmitters.            Sludge In Feeler Lines.                                                    I I
PD-5202      1FT414.                  Channel Readings Mismatched calibrated.-
I OD-900514    1LT459A.                Channel Readings Mismatched Calibrated.
OD-900582    10VC006.                No Open Indication On Con-    1 Limit SWitch Adjusted.
trol Bezel.
OD-900614    Valves llSW039          Stuck Open.                      Repaired Control Air Solenoid
                    & 13SW039.                                              Valves.
Page    7 of 15 8-1-7.Rl
 
50-272 DOCKET. i\10. : ___.;~...=..;-=-~--~----~
UNIT    N~*:    _s_a._l_em
__#_l_ _ _ _ _ _ _ __
SU~-~...RY OF SAFETY RELATED ~NTENANCE DA'J.E:  January 10, 1979 DEPARTY..ENT        Performance EEPOR!I'    MONTH    December 1978                  COMPLETED BY:            L. K. Miller
                                                                                      -----~--~------~
TELEP BONE:        609-:-365-7000 X507 WORK ORDER            EQUIPMENT                                                                                    I NO.        II FAILURE DESCRIPTION Il  CORH..ECTIVE ACTION I
i II OD-900652        N32 Source Range        Channel Readings Mismatched.! Repaired Loose Connection.                I I
Detectors.
OD-11194        llA5424.                Channel Readings Mismatched.I Blewdown Feeler Line.
I OD-11071        10CV172.                Valve Does Not Remain Open j Replaced Control Air Solenoid When In "Auto" *              : Valve.
I OD-9043          l Batch_ Tank Temp.      Does Not Increase Temp. To      Calibrated Operating Band.
Normal From Cold Condition.
PD-5238        1LT460.                  Channel Readings Mismatched.I Replaced Strain Gauge & Re-I Calibrated.
I PD-900336      11TE411AB.              - Out of Spec.                .ICalibrated.
II
  . PD-5235        11PM474B.                  Out of* Spec .                  Calibrated.
OD-11125        tlFT521.                  Feeler Line Blown Out.        I Reinstalled.
i OD-11132        14MS018.                  Diaphragm Ruptured.          IReplaced Diaphragm.
II I
l    OD-11133        1FT532.                  Flow Reads Zero.            IRecalibrated.
I I
i l
OD-11184        11 Waste Gas Corrp:. .__ Breaker Will Not Close.      l Replaced Brush Assigrurent      &
I Tightened.
i Page     8 of 15 8-1-7.Rl
 
~UMMARY DOC KE I
OF SAFETY DEPART1'IBNT RELATED    eNTENP.~NCE Maintenance UNIT  N.:
D.A: .r:.. :
Salem #1 January 10, 1979
            ~PORT  MONTH    December 1978                    CO.V!PLETED BY:        L. K. Miller
                                                                                      ~~~~~~~~~~~~~
TELEPHONE:         609-365-7000 X507 WORK  ORDER      EQUIPMENT                 FAILURE DESCRIPTION         COR....~ECTIVE    ACTION NO.
MD-3276      12 Service Water         Hole in Pipe Between 12SW24   Temporarily patched.
Strainer Discharge       & 12SW25 Valves.
Line                                                                                       !
MD-3274      13 Service Water         Hole in Pipe on Discharge     Temporarily patched.
Strainer Discharge       Side of 13SW25 Valve.
Line.
MD-3290      Service Water Lines Hole in Pipe on Discharge           Temporarily patched.
Side of 11SW122 Valve.
OD-11203    14 Service Water         Packing Gland Leaking.         Repacked Valve.
Purrp.
OD-11108    11 Waste Gas Comp.       Inspect & Repair.             Replaced Rotor, Shaft & Bearings.
I l-   MD-3277      Boric Acid Evapor-       Replace Rupture Disc.         Replaced Disc.
ator.                                                                           --   - -
OD-900553    14 Fan Coil Unit.       Trips While Atterrptihg To     Inspected & Cleaned 1B7X 440V Start.                         Brkr.
OD-10464    11 Seal Water Inj.       Hi !iP.                       Replaced Filter.
Filter.
MD-1490      13, 14, & 15 Heater Install Drain Line Supports         Completed ED-0076.
Vents & Drains.         as per ED-0076.
OD-900525  -11 Service Water       Strainer Runs With Purrp       Replaced PD-285 & Calibrated.
Purrp Strainer.         Shutdown & Strainer on Auto.
OD-900592 le Diesel.             Audible Alarm Not Working.     Replaced Hom.
OD-900564    lB Diesel.             Lube Oil Heater Terrp. *Alarm. Lube Oil Heater Temperature Controller Recalibrated.
MD-900947  lB Diesel.             Invalid Alarm.                   ,Recalibrated TD-7211.
Page 9 of 15 8-1-7.Rl
 
1-                                                                 DOCKET NO.: 50-272 UNIT. ~:-S_a_l_ern---#1--------------~-
SUMMI>..cRY OF SAFETY RELATED .INTENANCE DEPARTMENT     Maintenance                                   DATE: January 10, 1979 COMPLETED BY: L. K. Miller REPORT MONTH December 1978                                          ~~~~~~~~~~~~~
TELEPHONE: 609-365-7000 X507 WORK ORDER        EQUIPMENT                  FAILURE DESCRIPTION       CORRECTIVE ACTION NO.
OD-11067      12 Waste Gas Comp.        Excessive Seal Leakage.       Replaced Seal.
OD-11024      13 Roddrive Vent          Trips Breaker.               Replaced Fan.
Fan.
JYID-900960    Kl 125VDC Battery        Does Not Accept Loading.     Replaced Faulty Receiver Charger.                                                Diode.
OD-900662      #1 Errergency Air        Trips on Low Press When       Calibrated PD-3819.
Compressor.              Started In Manual.
MD-900952      100' Elev. Con-          Inner Door Broken Bearing. Replaced Bearing.
tainrrent Air Lock.
OD-11148
* Fire Pumps.         *-* - Pump Failed To Start.         Reset Timers To Proper Settings JYID-3251      Valve 10MS095.            Valve leaks.                 Replaced Valve.     *-       . - -
JYID-3273B    130' Elev. Con-          Repair Inner Door.           Replaced Inner Door Carn Roller.
tainrrent Air Lock Door.
OD-11054      13 Charging Purrp.        Piston Packing Leaks.         Repacked, Installed Two New Plungers.
OD-11097      13 Service Water          Packing leaks.               Repacked.
Pump Strainer.
PD-5194        1Rl4.                    Channel Failed.               Replaced Bistable Card.
OD-900677      RC 12-6 Position        Ground In Circuit.             Replaced Push Button.
No. 7 C.B.
OD-900742    14 Service Water        Vibration.                     Repacked Gland.
Pump.
Page 10 of 15 8-1-7.Rl
 
SALEM UNIT I OPERATING  


==SUMMARY==
==SUMMARY==
DECEMBER, 1978 The load is being increased at 3% per hour from 59% at 0001. By 1500, unit load was 95%. Unit load remained at approximately 95% in preparation for an incore/excore detector calibration flux mapping surveillance.
 
Unit load was held at 95% in preparation for flux ping for the incore/excore detector calibration lance. Unit load was held at 95% for flux mapping. The flux mapping was completed by 1940 and the was creased to 99%.by 2210. Unit load remained greater than 99% for the remainder of the day. Unit load remained greater than 99% for the day. Unit load remained greater than 99% until 2055. Load was reduced to 93% by 2335 to allow maintenance to be performed on 11 Main Turbine Governor Control Valve with the valve in the closed position.
DECEMBER, 1978 12-1      The load is being increased at 3% per hour from 59% at 0001. By 1500, unit load was 95%. Unit load remained at approximately 95% in preparation for an incore/excore detector calibration flux mapping surveillance.
Unit load is being maintained at approximately 94% while maintenance is being performed on 11 Main Turbine Governor Control Valve. Maintenance was completed and load increase to 100% commenced at 0320 from 94%. At.0610, load was 100% and remained greater than 99% for the day. Unit load remained greater than 99% for the day. Unit load remained greater than 99% for the day. Page_ 11 of 15 J 12-9 12-10 12-11 12-12 12-13 12-14 thru 12-19 Unit load remained greater than 99% until 2145 when a load decrease was commenced at 3% per hour to clean Condensate and Steam Generator Feedwater Pump Strainers.
12-2      Unit load was held at 95% in preparation for flux map-ping for the incore/excore detector calibration surveil-lance.
Load at 2400 was 92%. Unit load is being decreased at 3% per hour -to __ :clean Main Condensate and Steam Generator Feedwater Pump Strainers.
12-3      Unit load was held at 95% for flux mapping. The flux mapping was completed by 1940 and the unit~load was in-creased to 99%.by 2210. Unit load remained greater than 99% for the remainder of the day.
At 1530, unit load was stabilized at mately 52%. At 1858, a load increase was commenced from 53% power at a rate of 3% per hour to return to full power operation.
12-4      Unit load remained greater than 99% for the day.
By 2400, unit load was 64.5%. Unit load increase at 3% per hour in progress.
12-5      Unit load remained greater than 99% until 2055. Load was reduced to 93% by 2335 to allow maintenance to be performed on 11 Main Turbine Governor Control Valve with the valve in the closed position.
Unit load was greater than 99% by 1415 and remained there for the remainder of the day. Unit load remained greater than 99% until 2145. 11 Governor Control Valve was found to oscilate from 80% to 100% open. Load was decreased to 95% by 2225 to allow the Performance Department to troubleshoot the electro-hydraulic controls for 11 Governor Valve. Unit load remained at approximately 95% for the remainder of the day. Unit load is being held at approximately 95% due to tenance on 11 Governor Control Valve controls.
12-6      Unit load is being maintained at approximately 94% while maintenance is being performed on 11 Main Turbine Governor Control Valve. Maintenance was completed and load increase to 100% commenced at 0320 from 94%. At.0610, load was 100%
At 1257, the Reactor tripped from 97% _due to 13 :Steam Generator Low Level in coincidence with Low Feedwater flow. The cause of the trip was a procedural error made during testing of the Steam Dump controls.
and remained greater than 99% for the day.
The unit was shutdown for the remainder of the day. Unit shutdown for maintenance.
12-7      Unit load remained greater than 99% for the day.
Page 12 of 15 12-20 . 12-21 12-22 12-23 12-24 The unit was critical at 0545. At 0951, a unit shutdown was commenced fnom 6% power to investigate cause of 11 Low Pressure Turbine noise. At 1704, the Reactor was critical.
12-8      Unit load remained greater than 99% for the day.
Load was being increased to evaluate turbine noise but was limited to 2%odue to failure of Low Pressure Turbine rupture-, discs resulting from the loss of a Vacuum Pump. Load was reduced to less than 1% for the remainder of the day for repair of the rupture, discs. Unit load was less than 1% until 0800 when load was being increased to evaluate turbine noise. Evaluation complete and unit load less than 1% by 0930. The cause of the turbine noise was found to be a loose turbine rotor balance plug. The unit was back in service and the generator synchronized by 1934. Load was,increased at 3% per hour and by 2400 load was 31%. Unit load was 31% at 0001 and being increased at 3% per hour. By 2400, unit load was;85%. Unit load was 85% at 0001 and being increased at 3% per hour. At 0230, a load decrease at 5% per hour was commenced from 89% power. The load decrease was initiated due to the malfunction of :the Volume Control Tank (VCT) relief valve 1CV241. By 0400, unit load was 60%. Load was maintained at approximately 60% while an attempt was made to restore the relief valve to service. The flange connection of the relief valve was found to be leaking. Unit load reduction was commenced at 0525 from 59% in preparation for possible down. At 0606, the turbine was manually tripped at 35% load followed by a Reactor trip. The unit was shutdown for the remainder of the day for maintenance.
Page_ 11 of 15
The unit was taken critical at 0136. The turbine-generator was synchronized at 0404 and load increase commenced at 3% per hour. By 2400, unit load was 66%. Page 13 of 15 12-25 12-26 thru 12-29 12-30 12-31 Unit load was 66% at 0001 and being increased at 3% per . hour. By 1530, unit load was greater than 99% and remained greater than 99% for the remainder of the day. Unit load was greater than 99% for the day. At 0006, a load reduction was commenced from 99% power at 3% per hour in preparation for cleaning the Main Condensate Strainers.
 
Load was reduced to 68% by 0825 and held at approximately 68% while the Main Condensate Pump Strainers were cleaned. Unit load increase commenced at 1338 from 67% power .. at 3% per hour. By 2400, unit load was 96%. At 0001, unit load was 96% and being increased at 3% per hour. By 0125, unit load was greater than 99% and remained greater than 99% for the remainder of the year. Page 14 of 15. ' i I December 1978 e REFUELING INFOF.MATION.
12-9     Unit load remained greater than 99% until 2145 when a load decrease was commenced at 3% per hour to clean Condensate and Steam Generator Feedwater Pump Strainers.
: e. DOCKET NO.: 50-272 UN IT: Salem #1 DATE: January 10, 1979 . COMPLETED BY: L.K. Miller TELEPHONE:
Load at 2400 was 92%.
609-365-7000 X507 1. Refueling information has changed from last month: 2. 3. YES NO X Scheduled date of next refueling:
12-10    Unit load is being decreased at 3% per hour -to __:clean Main Condensate and Steam Generator Feedwater Pump Strainers. At 1530, unit load was stabilized at approxi-mately 52%. At 1858, a load increase was commenced from 53% power at a rate of 3% per hour to return to full power operation. By 2400, unit load was 64.5%.
March 31, 1979 Scheduled date for* restart following refueling:
12-11    Unit load increase at 3% per hour in progress.     Unit load was greater than 99% by 1415 and remained there for the remainder of the day.
June 23, 1979 4 *. . A. Will Technical Specification changes or other. license*
12-12    Unit load remained greater than 99% until 2145.     11 Governor Control Valve was found to oscilate from 80% to 100% open.
* amendments be required?
Load was decreased to 95% by 2225 to allow the Performance Department to troubleshoot the electro-hydraulic controls for 11 Governor Valve. Unit load remained at approximately 95% for the remainder of the day.
YES** X
12-13    Unit load is being held at approximately 95% due to main-tenance on 11 Governor Control Valve controls.     At 1257, the Reactor tripped from 97% _due to 13 :Steam Generator Low Level in coincidence with Low Feedwater flow. The cause of the trip was a procedural error made during testing of the Steam Dump controls. The unit was shutdown for the remainder of the day.
* NO ---NOT DETERMINED  
12-14 thru    Unit shutdown for maintenance.
*TO-DATE December 1978 B. Has the-reload fuel design beenreviewed by the Station Operating Review-Committee?
12-19 Page 12 of 15
YES NO x ---If no, when is it _scheduled'?
 
. 12-20
      ~    The unit was critical at 0545. At 0951, a unit shutdown was commenced fnom 6% power to investigate cause of 11 Low Pressure Turbine noise. At 1704, the Reactor was critical. Load was being increased to evaluate turbine noise but was limited to 2%odue to failure of Low Pressure Turbine rupture-, discs resulting from the loss of a Vacuum Pump. Load was reduced to less than 1% for the remainder of the day for repair of the rupture, discs.
12-21  Unit load was less than 1% until 0800 when load was being increased to evaluate turbine noise. Evaluation complete and unit load less than 1% by 0930. The cause of the turbine noise was found to be a loose turbine rotor balance plug.
The unit was back in service and the generator synchronized by 1934. Load was,increased at 3% per hour and by 2400 load was 31%.
12-22  Unit load was 31% at 0001 and being increased at 3% per hour. By 2400, unit load was;85%.
12-23  Unit load was 85% at 0001 and being increased at 3% per hour.
At 0230, a load decrease at 5% per hour was commenced from 89% power. The load decrease was initiated due to the malfunction of :the Volume Control Tank (VCT) relief valve 1CV241. By 0400, unit load was 60%. Load was maintained at approximately 60% while an attempt was made to restore the relief valve to service. The flange connection of the relief valve was found to be leaking. Unit load reduction was commenced at 0525 from 59% in preparation for possible shut-down. At 0606, the turbine was manually tripped at 35% load followed by a Reactor trip. The unit was shutdown for the remainder of the day for maintenance.
12-24  The unit was taken critical at 0136. The turbine-generator was synchronized at 0404 and load increase commenced at 3%
per hour. By 2400, unit load was 66%.
Page 13 of 15
 
12-25   Unit load was 66% at 0001 and being increased at 3% per .
hour. By 1530, unit load was greater than 99% and remained greater than 99% for the remainder of the day.
12-26 thru    Unit load was greater than 99% for the day.
12-29 12-30    At 0006, a load reduction was commenced from 99% power at 3% per hour in preparation for cleaning the Main Condensate Strainers. Load was reduced to 68% by 0825 and held at approximately 68% while the Main Condensate Pump Strainers were cleaned. Unit load increase commenced at 1338 from 67% power .. at 3% per hour. By 2400, unit load was 96%.
12-31    At 0001, unit load was 96% and being increased at 3% per hour. By 0125, unit load was greater than 99% and remained greater than 99% for the remainder of the year.
Page 14 of 15.
i I
                                                                      ~
 
e   REFUELING INFOF.MATION. e.
50-272 DOCKET NO.: -----~~--
UN IT: Salem #1
                                                                        ---"-=~_.....;;_.._~~
DATE: January 10, 1979 .
COMPLETED BY: L.K. Miller TELEPHONE: 609-365-7000 X507 December 1978
: 1. Refueling information has changed from last month:
YES         NO X
: 2. Scheduled date of next refueling:         March 31, 1979
: 3. Scheduled date for* restart following refueling: June 23, 1979
                                                              ---------~--~---~-
4 *. . A. Will Technical Specification changes or other. license*
* amendments be required?           YES** X
* NO NOT DETERMINED *TO-DATE December 1978 B. Has the- reload fuel design beenreviewed by the Station Operating Review-Committee?                 YES         NO x If no, when is it _scheduled'?
Febrna:ty 1979
Febrna:ty 1979
: 5. Scheduled date(s) for submitting proposed licensing action: March 1979 If Required 6-. Important licensing considerations associated with refueling:
                                              ----------------~--------------------
NONE 7. Number of Fuel Assemblies:
: 5. Scheduled date(s) for submitting proposed licensing action:
A. In-Core 193 B.-In Spent Fuel Storage* 0 8. *Present licensed spent fuel storage capacity:
March 1979 If Required 6-. Important licensing considerations associated with refueling:
264 Future spent fuel storage*.
NONE
capacity:
: 7. Number of Fuel Assemblies:
1,170 ------------------
A. In-Core                                                     193 B.- In Spent Fuel Storage*                                       0
: 9. Date of that can be discharged to the spent fuel pool* assriming the* present capacity:
: 8. *Present licensed spent fuel storage capacity:                     264 Future spent fuel storage*. capacity:                       1,170
_Ap_r_i_1
: 9. Date of la~t iefrielin~ that can be discharged to the spent fuel pool* assriming the* present -~icensed. capacity: _Ap_r_i_1__19_s_2__________
__ 19_s_2 _________
Page 15 of 15 8-l-7.R4}}
_ Page 15 of 15 8-l-7.R4}}

Latest revision as of 14:23, 23 February 2020

Monthly Operating Rept for Dec 1978
ML18078A642
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/10/1979
From: Miller L
Public Service Enterprise Group
To:
Shared Package
ML18078A641 List:
References
NUDOCS 7901160269
Download: ML18078A642 (14)


Text

e AVERA.GE DAILY lliE ?Oi'i"E~ Lt. 1'EL 1

DJCKET NO. 50-272 UNIT Salem #1 nA:u: January 10, 1979 COMPLETED BY L. K . Miller TELEPHONE . 609-365-7000 X507 MONTH December 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POl'iER LEVEL (MWe-NET) (MWE-NET) 1 950 17 0 2 1,005 18 0 3 1,100 19 0 4 1,051 . 20 0 5 1,115 21 . 5 6 1,074 22 551 7 1,132 23 186 8 1,104 24 259 9 1,031 25 956 10 752 26 1,110 11 986 27 1,104 12 1,099 28 1,101 13 562 29 1,105 14 0 30 866

15. 0 31 1,110 16 0 Pg. 2 of 15 8.1-7.PJ.

CAn:: January la, 1979

~BY: L. K. Miller

~:: 6a9_.365-70aa X5a7

l. Onit:Nane:. Salem #1*
2. P.epJr1:inq Per.i.c:d: D ~ c ember 19 7 8
3. Licensed ~ Poller* (M<it): ___3 __3__3__8_______
4. _ Naueplate Rat:inq (Gross me): _ _1_1_3_5_~----
5. Design El.ectrical.. Ra.t:inq~ (Net ~) : a a 1 9 6.. . Maximlm Cependabl.e. Cailac::i:ey .(Gross:*~) : . 112 4
7. MaXimllm:* OP{>eodabl e. capa.city* (Net Kie) : 1 a7 9 *
a. If Changes Occur ill capacity Ratings' (Itell'S NIJlli:ler 3 'lln:cugh 7) S.ince Last Report.,. Give Reason:

NONE

9. J?cwer I.evel. To Which* Fest::ricted, If l!rr:f: (Net Kie") :. _ ___..N_o-.N_E"------------......;,----
10. lleascrls For* Restrictions,. I f };rrrfr ___ N_O_N_E___._.- - - - - - - - - - - - - - - - - - - -

Cumulative 744 8 ,".760 *.. 13,2al.

u.. Jblr.3* In. ~q Period.

u. Nl.lnD!r. Of. acurs ~ctor was- Critical. 556.7 5,113.7 7,656.9
13.
  • Reactor Re.serve Shutdown ~urs-. a.a o.a a.a
14. liours Generator on-Lina 523. 4 4,867.4 7,298.a lS. Unit Reserve" Shutdown HOm:s . a. a a.o a.o 1.6. Gress 'Jllel:inal. Energ:{ Generated CMiH> L 5 7 4 , 9 26 14,289,516 2a,984,736 17.. *Gl::OSS. Eleetrical. Energy Galera.te:i ~) . 535, 37a 4,786,5ao 6,972,810
18. Net El.ect:rical. Energy Generated(Mim) 5a8, 621 - 4,528, 762 6,586,980
70. 4 . 55.6 55.3 19.

20.

Onit Service Factor Unit Availability. Fact:cr ,7a. 4


55.6 55.3 6 3. 4 47.9 46.2 21.

22:..

Unit capacity Factor (Usinq MOC Net)

Unit capacity Factor (Usinq DER Net) . 62. 7 47.4 -------- 45.8

23. Unit.Forced: outage Rate* . 29. 7 44.a 36.E
24. * 'Shutdowns ScbedUled'~- Next 6 M:nths. (Type, Date, and Duration of Ea.ch):

.. Unit Refueling 3/31/79 - 6/23/79 . .

25. If. Shut:eown At End of. Report l'eri.cid! Est:imate!d-Da.te o£"Sta,rtup: --..;;.N...::.::A..__ _ _ _ _..;.__ _ _ _ __
  • 26. Units In* Test.Status(Prior to* cammcial-Cperaticn):

Forecast Achieved INITIAL CRITICALIT'I 9/3a/76 12/JJ /76 INIT:rAL EllX:'l'RICI'I"- 11/al/76 12/25/76 S-l-7.R2 Pg. 3 of 15 ... .

  • a::MME:R:!AI. OPERATION 12/20/76 6/3a/77

UNIT SllU'.lin'INS l\NO PCWER REDUCfIONS DOCKET NO. :

50-272 ~

~~~~--~~~~-

REPORT MJ!-,m1 December 1978 UN 11' :Nl\ME: *Sal em #1 D/\TE: January 10, 19 79 COMPI,ETF.D DY: L. K. Miller

~~~~~~~~

TELEPllONE: 609-365-7000 X507 MIITllOD

  • OF OOR/\TION SHUITING LICENSE SYSTEM <Il1PCNENl' Cl\USE /\ND amru:cnvr.

1 tn. Dl\TE TYPE !ilOURS) REl\ooif lXMN EVEN!' moE" CXJOE5 /\CrIOO 'IU RE1\CI'OR REPOIU t PREVENI' RFUJRPJ'NCE 78-297 12/09/78 F 0.0 B 4A - - - HC FIL'IER Cleaning strainers on 12 Condensate Pump & Steam Gen. Feed Pumps78-305 12/13/78 F 1.04 A 3 - - - HI H'IEXCH Low-IDw Level, 13 Steam Generator 78-306 12/13/78 F' 33.98 A 4B - - -i HI H'IEXCH 13 Auxilia:r:y Steam Generator Feed i Pump Control Malfunction 78-308 12/14/78 F 144 A 4B - - - HJ HTEXCH Repair 13 & 14 Steam Gen~ ~llanway .:Leaks78-309 12/20/78 F 19.58 B 4B - - - HA WRBIN #1 Low Pressure Turbine Inspection 78-310 12/23/78 F 22 A 2 - - - WG zzzzzz Volurre Control Tank Relief Valve Flange Leak 78-312 12/30/78 F 0.0 B 4B - - - HG HTEXCH Oil Change On 11 Condensate Pump &

11 Heater Drain Pump, IDwer Motor Bearing 1 2 3 4 5 F: Forced Peason: M3thod: Exhibit G - Instructions Exhibit 1-SLlllE S: Scheduled 1\-EquipiEnt Failure(Explain) I-Manual for Preparation of Data Source B--Maintenance or Test 2-Manuai Scram. Entry Sheets for Lkensee C-Refueling 3-Autanatic Scram. Event Peport (LEn) File 0-Regulatory Restdction 4-0ther (Explain) (NUHID--0161)

E-Operator Trainin~ & License EKamination F-1\dmlnistrative 8-l-7.R2 G-operational Error(Explai11) A. LOAD REDUCT!ON II-Other (Explain)

Pg. 4 - 15 B. CONTINUATION OF PREVIOUS OUTAGE

/

DOCKET NO.: 50-272 MAJOR PLANT MODIFICA~NS

~~~~~~~~~-

UN I .E: Salem #1

~~~~~~~~~~

REPORT MONTH December 1978 DATE: January 10, 1979 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507

  • DCR NO. PRINCIPLE SYSTEM SUBJECT IBC-0430 Solid State.Prat. System Modify Circuit to Assure Closure bf Containment Vent Valves on Safety Injection IBC-0444 Main Turbine Lube Oil Modify Level Indicator, Deduc.to:r:

and Suction Line Check Valve lEC-0448 Radiation Monitoring System Delete Automatic Fan Coil Unit High Activity Interlock lOD-0037 eves Change Letdown Heat Exchanger Temperature Controller Setpoint from 115° F. to 100° F.

  • DESIGN CHANGE REQUEST Page 5 of 15 8-1-7 .Rl

DOCKET NO. : 50-272 MAJOR PLANT MODIFICA~NS ~------------------

0 UN I irttAME: ~-s_a_l_em__#_l___________

REPORT MONTH December 1978 DATE: January 10, 1979 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507

  • DCR NO. 10CFR50.59. SAFETY EVALUATION lEC-0430 This design change will assure that an SI trip will cause the SSPS to trip the Containment Isolation Valves, without regard to the state or histm:y of the Containment Radiation Alarms. This change does not constitu_te an unreviewed safety qUestion.

lEC-0444 Functional operation is unchanged. This design change is not Safety Related, nor does it affect the operation of any Safety Related systems.

lEC-0448 This change eliminates a non-safety grade trip function which could otherwise affect the performance of a safety system. The trip circuitry to be eliminated was originally considered to be reqUired due to assumptions regarding service water pressure versus peak containrrent pressure. Recent investigation has determined that the trip function is not reqUired for safety. Tech. Spec. margiris and safety. analysis *are :

not affected.

lOD-0037 This design change does not affect any safety related funtions, nor does it create any new safety hazards.

\_

  • DESIGN CHANGE REQUEST Page 6 of J;,5°

DOCKET NO * : _5,,,_0-_,2.._.7._.2..__ _ _ _ _ _ __

SUMJ0.:ARY OF SAFETY RELATED ~NTENANCE UNIT NW:. Salem #1 DJ:.~: January 10, 1979 DEPAR'I'MENT Performance CO!v1_FLETED BY: L. K. Miller P.EPORT MONTH December 1978 -------------

T :S:SEP HONE: 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESC:K.!:PTION CORRECTIVE ACTION NO.

OD-11123 1LT528. Mismatched Readings From Blewdown Feeder Lines & Cali-I Other Channels. brated Transmitter. i OD-11050 1FA3542Z-l Flow Transmitters Out of l

Calibrated Transmitters & Freed 1FA3542Z-2 Spec. , Frozen Hand.wheel & Hand.wheel & Repaired Reach Rod.

lFA3172Z-2 Failed Reach Rod.

14SW223.

OP-0461 Valves lOVCOOl, Modify SSPS I.A.W. OCR JEC- Completed.

10VC002, 10VC003, 0430.

10VC004, 10VC005, 10VC006.

PD-4283 1FT128. Last Calibration Perforrred Recalibrated.

.With Out-Of-Cal. Test Equip PD-900358 lLT-537." Channel Readings Mismatched Blewdown Feeler Lines.

I Pb-5244 ll.C-549A/B Unstable Output No. 1. Replaced Faulty-Capacitors.

OD-10804 1Rl7B. Channel Spiking. Replaced Faulty Bistable Printed Circuit Board.

PD-900359 All Stearn Generator Repeated Discovery of Completed Blowdowns.

Transmitters. Sludge In Feeler Lines. I I

PD-5202 1FT414. Channel Readings Mismatched calibrated.-

I OD-900514 1LT459A. Channel Readings Mismatched Calibrated.

OD-900582 10VC006. No Open Indication On Con- 1 Limit SWitch Adjusted.

trol Bezel.

OD-900614 Valves llSW039 Stuck Open. Repaired Control Air Solenoid

& 13SW039. Valves.

Page 7 of 15 8-1-7.Rl

50-272 DOCKET. i\10. : ___.;~...=..;-=-~--~----~

UNIT N~*: _s_a._l_em

__#_l_ _ _ _ _ _ _ __

SU~-~...RY OF SAFETY RELATED ~NTENANCE DA'J.E: January 10, 1979 DEPARTY..ENT Performance EEPOR!I' MONTH December 1978 COMPLETED BY: L. K. Miller


~--~------~

TELEP BONE: 609-:-365-7000 X507 WORK ORDER EQUIPMENT I NO. II FAILURE DESCRIPTION Il CORH..ECTIVE ACTION I

i II OD-900652 N32 Source Range Channel Readings Mismatched.! Repaired Loose Connection. I I

Detectors.

OD-11194 llA5424. Channel Readings Mismatched.I Blewdown Feeler Line.

I OD-11071 10CV172. Valve Does Not Remain Open j Replaced Control Air Solenoid When In "Auto" *  : Valve.

I OD-9043 l Batch_ Tank Temp. Does Not Increase Temp. To Calibrated Operating Band.

Normal From Cold Condition.

PD-5238 1LT460. Channel Readings Mismatched.I Replaced Strain Gauge & Re-I Calibrated.

I PD-900336 11TE411AB. - Out of Spec. .ICalibrated.

II

. PD-5235 11PM474B. Out of* Spec . Calibrated.

OD-11125 tlFT521. Feeler Line Blown Out. I Reinstalled.

i OD-11132 14MS018. Diaphragm Ruptured. IReplaced Diaphragm.

II I

l OD-11133 1FT532. Flow Reads Zero. IRecalibrated.

I I

i l

OD-11184 11 Waste Gas Corrp:. .__ Breaker Will Not Close. l Replaced Brush Assigrurent &

I Tightened.

i Page 8 of 15 8-1-7.Rl

~UMMARY DOC KE I

OF SAFETY DEPART1'IBNT RELATED eNTENP.~NCE Maintenance UNIT N.:

D.A: .r:.. :

Salem #1 January 10, 1979

~PORT MONTH December 1978 CO.V!PLETED BY: L. K. Miller

~~~~~~~~~~~~~

TELEPHONE: 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION COR....~ECTIVE ACTION NO.

MD-3276 12 Service Water Hole in Pipe Between 12SW24 Temporarily patched.

Strainer Discharge & 12SW25 Valves.

Line  !

MD-3274 13 Service Water Hole in Pipe on Discharge Temporarily patched.

Strainer Discharge Side of 13SW25 Valve.

Line.

MD-3290 Service Water Lines Hole in Pipe on Discharge Temporarily patched.

Side of 11SW122 Valve.

OD-11203 14 Service Water Packing Gland Leaking. Repacked Valve.

Purrp.

OD-11108 11 Waste Gas Comp. Inspect & Repair. Replaced Rotor, Shaft & Bearings.

I l- MD-3277 Boric Acid Evapor- Replace Rupture Disc. Replaced Disc.

ator. -- - -

OD-900553 14 Fan Coil Unit. Trips While Atterrptihg To Inspected & Cleaned 1B7X 440V Start. Brkr.

OD-10464 11 Seal Water Inj. Hi !iP. Replaced Filter.

Filter.

MD-1490 13, 14, & 15 Heater Install Drain Line Supports Completed ED-0076.

Vents & Drains. as per ED-0076.

OD-900525 -11 Service Water Strainer Runs With Purrp Replaced PD-285 & Calibrated.

Purrp Strainer. Shutdown & Strainer on Auto.

OD-900592 le Diesel. Audible Alarm Not Working. Replaced Hom.

OD-900564 lB Diesel. Lube Oil Heater Terrp. *Alarm. Lube Oil Heater Temperature Controller Recalibrated.

MD-900947 lB Diesel. Invalid Alarm. ,Recalibrated TD-7211.

Page 9 of 15 8-1-7.Rl

1- DOCKET NO.: 50-272 UNIT. ~:-S_a_l_ern---#1--------------~-

SUMMI>..cRY OF SAFETY RELATED .INTENANCE DEPARTMENT Maintenance DATE: January 10, 1979 COMPLETED BY: L. K. Miller REPORT MONTH December 1978 ~~~~~~~~~~~~~

TELEPHONE: 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

OD-11067 12 Waste Gas Comp. Excessive Seal Leakage. Replaced Seal.

OD-11024 13 Roddrive Vent Trips Breaker. Replaced Fan.

Fan.

JYID-900960 Kl 125VDC Battery Does Not Accept Loading. Replaced Faulty Receiver Charger. Diode.

OD-900662 #1 Errergency Air Trips on Low Press When Calibrated PD-3819.

Compressor. Started In Manual.

MD-900952 100' Elev. Con- Inner Door Broken Bearing. Replaced Bearing.

tainrrent Air Lock.

OD-11148

  • Fire Pumps. *-* - Pump Failed To Start. Reset Timers To Proper Settings JYID-3251 Valve 10MS095. Valve leaks. Replaced Valve. *- . - -

JYID-3273B 130' Elev. Con- Repair Inner Door. Replaced Inner Door Carn Roller.

tainrrent Air Lock Door.

OD-11054 13 Charging Purrp. Piston Packing Leaks. Repacked, Installed Two New Plungers.

OD-11097 13 Service Water Packing leaks. Repacked.

Pump Strainer.

PD-5194 1Rl4. Channel Failed. Replaced Bistable Card.

OD-900677 RC 12-6 Position Ground In Circuit. Replaced Push Button.

No. 7 C.B.

OD-900742 14 Service Water Vibration. Repacked Gland.

Pump.

Page 10 of 15 8-1-7.Rl

SALEM UNIT I OPERATING

SUMMARY

DECEMBER, 1978 12-1 The load is being increased at 3% per hour from 59% at 0001. By 1500, unit load was 95%. Unit load remained at approximately 95% in preparation for an incore/excore detector calibration flux mapping surveillance.

12-2 Unit load was held at 95% in preparation for flux map-ping for the incore/excore detector calibration surveil-lance.

12-3 Unit load was held at 95% for flux mapping. The flux mapping was completed by 1940 and the unit~load was in-creased to 99%.by 2210. Unit load remained greater than 99% for the remainder of the day.

12-4 Unit load remained greater than 99% for the day.

12-5 Unit load remained greater than 99% until 2055. Load was reduced to 93% by 2335 to allow maintenance to be performed on 11 Main Turbine Governor Control Valve with the valve in the closed position.

12-6 Unit load is being maintained at approximately 94% while maintenance is being performed on 11 Main Turbine Governor Control Valve. Maintenance was completed and load increase to 100% commenced at 0320 from 94%. At.0610, load was 100%

and remained greater than 99% for the day.

12-7 Unit load remained greater than 99% for the day.

12-8 Unit load remained greater than 99% for the day.

Page_ 11 of 15

12-9 Unit load remained greater than 99% until 2145 when a load decrease was commenced at 3% per hour to clean Condensate and Steam Generator Feedwater Pump Strainers.

Load at 2400 was 92%.

12-10 Unit load is being decreased at 3% per hour -to __:clean Main Condensate and Steam Generator Feedwater Pump Strainers. At 1530, unit load was stabilized at approxi-mately 52%. At 1858, a load increase was commenced from 53% power at a rate of 3% per hour to return to full power operation. By 2400, unit load was 64.5%.

12-11 Unit load increase at 3% per hour in progress. Unit load was greater than 99% by 1415 and remained there for the remainder of the day.

12-12 Unit load remained greater than 99% until 2145. 11 Governor Control Valve was found to oscilate from 80% to 100% open.

Load was decreased to 95% by 2225 to allow the Performance Department to troubleshoot the electro-hydraulic controls for 11 Governor Valve. Unit load remained at approximately 95% for the remainder of the day.

12-13 Unit load is being held at approximately 95% due to main-tenance on 11 Governor Control Valve controls. At 1257, the Reactor tripped from 97% _due to 13 :Steam Generator Low Level in coincidence with Low Feedwater flow. The cause of the trip was a procedural error made during testing of the Steam Dump controls. The unit was shutdown for the remainder of the day.

12-14 thru Unit shutdown for maintenance.

12-19 Page 12 of 15

. 12-20

~ The unit was critical at 0545. At 0951, a unit shutdown was commenced fnom 6% power to investigate cause of 11 Low Pressure Turbine noise. At 1704, the Reactor was critical. Load was being increased to evaluate turbine noise but was limited to 2%odue to failure of Low Pressure Turbine rupture-, discs resulting from the loss of a Vacuum Pump. Load was reduced to less than 1% for the remainder of the day for repair of the rupture, discs.

12-21 Unit load was less than 1% until 0800 when load was being increased to evaluate turbine noise. Evaluation complete and unit load less than 1% by 0930. The cause of the turbine noise was found to be a loose turbine rotor balance plug.

The unit was back in service and the generator synchronized by 1934. Load was,increased at 3% per hour and by 2400 load was 31%.

12-22 Unit load was 31% at 0001 and being increased at 3% per hour. By 2400, unit load was;85%.

12-23 Unit load was 85% at 0001 and being increased at 3% per hour.

At 0230, a load decrease at 5% per hour was commenced from 89% power. The load decrease was initiated due to the malfunction of :the Volume Control Tank (VCT) relief valve 1CV241. By 0400, unit load was 60%. Load was maintained at approximately 60% while an attempt was made to restore the relief valve to service. The flange connection of the relief valve was found to be leaking. Unit load reduction was commenced at 0525 from 59% in preparation for possible shut-down. At 0606, the turbine was manually tripped at 35% load followed by a Reactor trip. The unit was shutdown for the remainder of the day for maintenance.

12-24 The unit was taken critical at 0136. The turbine-generator was synchronized at 0404 and load increase commenced at 3%

per hour. By 2400, unit load was 66%.

Page 13 of 15

12-25 Unit load was 66% at 0001 and being increased at 3% per .

hour. By 1530, unit load was greater than 99% and remained greater than 99% for the remainder of the day.

12-26 thru Unit load was greater than 99% for the day.

12-29 12-30 At 0006, a load reduction was commenced from 99% power at 3% per hour in preparation for cleaning the Main Condensate Strainers. Load was reduced to 68% by 0825 and held at approximately 68% while the Main Condensate Pump Strainers were cleaned. Unit load increase commenced at 1338 from 67% power .. at 3% per hour. By 2400, unit load was 96%.

12-31 At 0001, unit load was 96% and being increased at 3% per hour. By 0125, unit load was greater than 99% and remained greater than 99% for the remainder of the year.

Page 14 of 15.

i I

~

e REFUELING INFOF.MATION. e.

50-272 DOCKET NO.: -----~~--

UN IT: Salem #1

---"-=~_.....;;_.._~~

DATE: January 10, 1979 .

COMPLETED BY: L.K. Miller TELEPHONE: 609-365-7000 X507 December 1978

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date of next refueling: March 31, 1979
3. Scheduled date for* restart following refueling: June 23, 1979

~--~---~-

4 *. . A. Will Technical Specification changes or other. license*

  • amendments be required? YES** X
  • NO NOT DETERMINED *TO-DATE December 1978 B. Has the- reload fuel design beenreviewed by the Station Operating Review-Committee? YES NO x If no, when is it _scheduled'?

Febrna:ty 1979


~--------------------

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

March 1979 If Required 6-. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblies:

A. In-Core 193 B.- In Spent Fuel Storage* 0

8. *Present licensed spent fuel storage capacity: 264 Future spent fuel storage*. capacity: 1,170
9. Date of la~t iefrielin~ that can be discharged to the spent fuel pool* assriming the* present -~icensed. capacity: _Ap_r_i_1__19_s_2__________

Page 15 of 15 8-l-7.R4