ML19031A352

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Submit Operating Report for Month of September 1978
ML19031A352
Person / Time
Site: Salem  PSEG icon.png
Issue date: 10/10/1978
From:
Public Service Electric & Gas Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML19031A352 (15)
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Text

{{#Wiki_filter:MONTH September., 1978 DAY AVERAGE DAILY POWER LEVEL 1 2 3 4 5 6 7 8 g 10 11 12 13 14

15.

16 Pg. 2 of 16 8.1-7. PJ. (MWe-NET) 1066 1052 1062 1078 1073 1095 1055 1066 980 1093 1113 1022 1072 1076 1131 1065 18'1ot.bDCJ9o IXJCKET NO. 50-272 UNIT Salem #1 DATE October 10, 1978 COMPLETED BY L.K. Miller TELEPHONr: 609-365-7000 X507 DAY AVERAGE DAILY POWER Ll::VEL (MWE-:NET) 17 1084 18 1087 19 1077 20 1089 21 1089 22 1077 23 0 24 20 25 0 26 614 27 231 28. 505 29 661 30 809 31

. l. llait Naaa:. Salem # 1

2.

P.epaz:t:inq Pe:icd: September, 1978

3.

I icensed ~ Power.: (Mit}: _ __,3_3_3_8 _____ _

4.

Nama!p.late Rat:i.Dq. (Gl:css. MNal : __ 1_13_5 _____ _ . S *. Design: !lertrirnl..Ra:tm;; (Net::.MNa): _....;;l;;.;:0-.9.;;.0 ___ _ 6 *. Max=!xmmCependable:capacity (Gl:css.*Kfel :_* _1_*1_2_4 __ _

7.

Maximin* nepoondable*capad.t'/* (NetMNa~: _.,...1... 07_9.__ __ r:x:c:ET ro.: 50-272 CM'E.: October 10, 1978 ~ SY: L.K. Miller ~:. 609-365-7000 X507 a.. If °'an;JPS Oc:cm: in Capacity Pad:Jt;s:: (Il:em Nulli:ler-3 ~ n Since Last: R.epott *. Give* Reascn: None ll. Ei:nIJ:3 In Rep:t:i.nq Pe:io::1. 12-NmD!r. Of Hcurs Read:cr' was Critical.

13.

P.eactcr* ReServe Shlltxbm. lblrs. 14..

  • Hours Generator on-til'la IS. Onit Peserve*Shut:dcwn*Hcc:rs l5.. GJ:Css. Tberma 1. Ecergy Ge:a!:ated (MtiH) 17~ ' Gress Elect:d.cal Energy GeDerated (ME) lS. Net El.ect:::!.cal. ~

~(?>H!) 1.9. Onit Se:vl.ca. Factor* This*~ 720 663.6 0 657.9 0

  • 1,988;978.4

. 660,!60 630,269 91.4 20:. Onit Availabil'ity Factor

91. 4 2l. On:it capa.c:ity Factcr. (Us:illq MOC. Net) 81.1
22. Oni.t capacit'] Factcr* (C's:inq CER Net)..

80

  • 3 23 *. Onit: Forced 01%tage Rate
8. 6 Yeartc Date 6551 3921.4 0

3726.9 0 11,146,972.6 3,744,sio - 3,549,560 56.9 56.9 50.2. 49.7 43.1

24. Shatdcwns.Scheduled ~Next s* Martbs. riwe. Date, am OUraticn of Eadll:
  • Unit Refueling 3/31/79 -.5/26/79 10,992 6,464.6 0

6,157.5 0 17,842,192.6 5,930,820 5,607,778 56.0 56.0 47.3 46.8 34.07 25~ If Sbut. Down At Eccl o£ Rep:lrt Pericd~ Estimated. Date of St:art:IJP: _N_/_A _____________ _

  • 26.

Oni.ts* In.Test Statcs(Prior tc.Comerc:ial ~): *-. S-l-7.R2 Pq. 3 of 16 Forecast 9730/16 11/01/76 12/20/76 kh:l.eved 12/11/76 12/25/76 6/30/77

00.

DATE TYPEl 78-181 9-9 F 78-214 9-23 F 78-221 9-26 F 78-222 9-26 F 78-223 9-26 F 78-224 9-28 F 78-225 9-29 F 1 2 F: Forced S: SC'heduled 8-l-7.R2 Pg. 4 - of l'.6 UNI1' SllU'l'ln'/NS NllJ IU-W.R REIXJC'l'la-IS REOORT MJNnl Sept. 1978 MlmOO OF OOMTION ~: SlllJITIOO (Irons) cxw IU!'.l\\C'roR 0 (A) 4 (A) 62.1 (A) 3 0 A 4 (A) 0 A 4 (A) 0 A 4 (A) 0 A* 4 (A) 0 A 4 (A} Reason: A-Fl:juiprent Failure (Explain) &-Maintenance or Test C-Refueling LICDISE EVl!Nl' REPoRT I --~--- D-Regulatory llestricUon E-{\\>erator Training & License Examination F-1\\dmlnistrative G-Operational Errot(Explain) Ii-Other (Explain) 3 SYSTEM ~ CXlDE4 CXllJE5 HH FILTER HH PUMP XX HH PUMP XX HH PUMP XX HH PUMP XX HH PUMP XX HH PUMP XX Method: I-Manual 2-Manuai Scram. 3-Autanatic Scram. 4-0ther (Explain) DOCKET NO.: 50-272 ~~~~~~~~- UNIT NAME: Salem #1 DJ\\'l'E: October 10, 1978 COMPJ,ETED Dy: L. K. Miller TELEPHONE: 609-365-7000 X507 CJ\\USE l\\ID CXlimocTIVE 1\\CTIOO 'ID PREVml' RIUIRRl:"?O: Clean Condensate Pump Suction Strainer - Reactor Trip Due to Failure of #13 Condensate Purrp. Failure of #12 Condensate P~. Inspection of #13 Condensate Pump LchTer Bearing. Inspection of #11 Condensate Pump*' Lube Oil. Inspection of #13 Condensate Pump raver Bearing~*. Check #12 Condensate Punp Alignnent. 4 A. B. Ellhlbit G - lnstructions for Preparation of Data Entry Sheets for Licensee Event !Eport (LER) File. (trunm-0161) WAD REDUCTION. 5 Exhibit 1-S<me fiource CONTINUATION OF PREVIOUS ourAGE.

N'.J. DATE 78-228 9-29 78-229 9-30 78-232 9-30 78-233 9-30 Page 5 of 16 B-1-7.Rl TYP~ F F F F ruru\\TICN REl\\5002 (IPJURS) 0 A 0 A 0 A 0 A UNIT Sfll1ltnlNS AND IWER REIXJCTIONS REPORI' MJJmt September, 1978 ME'IUJD OF Slfl1ITIOO LICENSE SYS~ CXJ.fPOOENl' ~ E.VENI' CDDE CDDES. RFJ\\C'OOR REPORT I 4(A) HH PUMPXX 4 (A) ~ PUMP XX 4 (A) HH PUMP XX 4 (A) ----- HH PUMPXX I

  • ,i
I DOCKET NO.:

50-272

~

.. UNIT 1NAME: Salem #1 DATE: October 10, 1978 -COMPLETED PY: _L_._K_._Mi_' l_l_e_r __ _ TELEPHONE: 609-365-7000 X507 CAIJSE AND CDRRI'n'IVE ACTION 'IO PREVENI' REOJRRENCE

  1. 11 Steam Generator Feed Purrp

. Vilirations.

  1. 11 Steam Generator Feed Purrp
  • Vilirations.
  1. 11 Steam Generator Feed Purrp Vibrations *
  2. 11 Steam Generators Feed Ptimp Vibrations.

MAJOR PLANT MODIFiilTIONS RE;ORT MONTH sept!lber, 1978

  • DCR. NO.

PRINCIPLE SYSTEM ED-0110 ED-0281 ED-0364-13 l.-EC-0399 OD-0011 1* Control Rod Drive Circulating Water Service Water RMS ( l-R-8) Component Cooling 7.

  • DESIGN CBANGE REOilEST Vent Fans.

~T NAME: Salem #1 DATE: OctoberlO, 1978 COMPLETED BY:~_L_._K_. __ M_i_l_l_e_r ____ ~ TELEP HONE : ( 6 0 9) 3 6 5-7 0 0 0 X 5 0 7 SUBJECT Various Structural Improvements. Install Entrainment Sampling Pipe. Installed Modified No.13 Pump. Setpoint Change. Header Alarm Setpoint Change. Page 6 of 16

MAJOR PLANT MODIFICATIONS REPORT MONTH Septen& I 1978 IIT NAME: Salem #1

  • DATE:

October 10, -~1978

  • DCR NO.

ED-0110 ED-0281 ED-0364 lED-0300 OD-0011 COMPLETED BY:~_L_. __ K_._Mi_*_1_1e_r ______ _ TELEPHONE: (609) 365-7000 X507 10CFRSO. 59; SAFETY.'.EVALUATION An unreviewed safety question is not involved. Safety related equiprrent will not be affected. An unreviewed safety question is not involved. Saftey related equiprtent will not be affected. A revised seismic analysis has been done on the new aluminum bronze colutm pipe. The impeller m:xlification-produced a flatter head~capacity ~ without affecting* design fle7N point. System still performs.original design function. Probability of accidents has not increased, nor has the occurance of new accidents been made ~ssible. The Tech. Spec bases are unaffected. This rronitor*and its 'setting dees*nbt affect.the* safe* operation or shutdown of the plant. The Design Change alters a non-safety related function of a circuit which is otherwise safety related. The Safety related functions of the circuit remains unm:xlified. The new design has been reviewed and dete:rmined not to create new potential rralfunctions or increase the probability of previously arialyzed malfunctions or accidents * .LO.'::jO::: I U.1.. .LU L ............ ~- __j

DOCKET NO.: 50-..:1..: ~~~~~~~~~--~~

SUMMARY

.' OF SAFETY RELA~ MAINTENANCE UN-NAME : __ s_al_em

  1. _l ______ _

DEPARTMENT .perfonnance DATE: October 10, 1978 REPORT MONTH September, 1978 COMPLETED BY: L. K. Miller TELEPHONE: (609) 365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO. PD-4967 Reactor Coolant Recalibrate 12 Reactor Calibrated. System Coolant Loop to new /::,,T/Tavg values. PD-4964 1BS532 1FC532 out of spec. Repl~ed isolator and cali -

  • brat
  • PD-4966 lBSSlOA Console alann failed to Repaired comparator.

reset. OD-9968

  1. 13 Steam Generat01: High differential level Recalibrated.

bet.ween Channel N and other channels. PD-4969 Reactor Coolant Recalibrate 13 Reactor Calibrated. System Coolant Loop to new l::,,"f:/Tavg Values. PD-4973 1BS541B Out of spec. Calibrated.* PD-4'974 Nuclear Instru-'.". N43 isolation anplifier* Calibrated. nerttation System out of spec~ P0-:4989 Air Partibulate

  • rnvestigate *filter
  • -. Replaced* filter paper and Detection Unit failure. alann.

charcoal filter. Repaired c~stan shear pins. OD-10441_ Valve 13AF11 No closed indication. Adjusted limit switch. PD-5057 Reactor Protection Recalibrate l'IC-505 for Calibrated. new Tavg program. PD-5058 Reactor Protection Recalibrate lPI'"'."505 and calibrated. lPT-506. OD-9084

  1. 12 Steam Generatm I.Dll Channel III' pressure Perforrced calibration check.

indication.

    • ~.:*~,

OD-9295 Valve 1SW169 Failed open. Replaced control air supply solenoid valve SV598 *. Page 8 df 16 8-L-7.Rl

DOCKET. NO * :

JU-~/~

SUMMA.Ry' OF SAFETY RELA& MAINTENANCE. UN-NAME: Salem #1 6* OEP ARTMENT Perfonnance REPORT MONTH September, 1978 DA".['E: COMPLETED BY: October 10, 1978 L. K. Miller TELEPHONE.: (609) 365-7000 X507 WORK ORDER EQUIPMENT FAlLtJRE DESCRIPTION

  • CORRECTIVE ACTION NO.

OD-9562 TL6339 .Erroneous reading. Tightened packing nut on root valve

  • OD-9920 RMS 1Rl7A Channel alarm sounded.

Detection tube cleaned and channel functionally checked. OD-9934 Refueling Water Erroneous high level over-Calibrated level transmitter. Storage Tank head. annunciator alarm. OD-9966

  1. 11 Steam Gez:iera-High differential pressure Calibrated *.

tor bet.Ween Channels I & II. OD-9986

  1. 12 Service Back wash malfunctions

. Strainer gages recalibrated *. Water Pump in auto mDae.

  • - -r.-

Air Part:.:i.culate. Gas i?uriP-i-e}?1aceci

  • OD-10009 IJ:M*flow operation.

Detection Unit PD-4836 ll.Cl02C out of.spec. calibrated *. i .

  • PD-4958

-'.Nuclear* **rnstru-Channel N44

  • NC307 'Bistable., Replaced bistable.

rrentation System malfunctioning *. PD-499.0 Control Bank A Investigate alarm. Replaced fuse. OD-10330

  1. 13 RCP Channel II Channel out of adjustrrent.

Recalibrated. OD-10389 1CV172 Valve No open indication. Adjusted limit switch. OD-10134 Shutdown.Bank A Urgent alarm sounded. Replaced fuse F3 on rrovable grippes

  • PD-5053 1TE43JA/B lBS432C and lBS432D are Adjusted gain and bias l'le432C/D out of spec.

of l'IM432A. -~- OD-8166

  1. 11-14 Stearn Mismatched readings between Calibrated 1.FI'532.

Generators steam flow and F.W. flow. Calibrated 13&14 Steam Flow Page 9 of lfr and Feed Flow recorder & Isolate:::: 8-1-7.Rl I

DOCKET. NO. : 50-272

SUMMARY

. OF SAFETY RELA~ MAINTENANCE DEPARTMENT. Maintenance UN - NAME: ___ s_ai_ern_#_l _______ _ DATE: __ _..q_c~t~o~h~e~r.._1~0.._. 1 _1_9~7-8..._ ___ COMPLETED BY: L. K. Miller REPORT MONTH September, 1978

~

WORK ORDER .EQUIPMENT NO. OD-10281

  1. 12 Service Water Punp OD-10357 Boric Acid Evaporator OD-10363
  2. 11 Service Water Punp MD-2966
  3. 11 thru 15 Fan Coil Units OD-8722
  4. 13 and #14 Residual Heat Renoval Sump Punps OD-10052
  5. 12 Residual Heat Renoval Sump Punp MD-2441 Valves 1CV2, 5, 75, and19.

OD-10447 Valve 1CC131 OD-10381

  1. 13 Control Area Supply Unit OD-10331

. Valve 1CC40 OD-10202

  1. 12 Boric Acid Transfer Pump OD-10099
  • Valve 13MS168 Page 10 of 16 8-1-7.Rl~-~

TELEPHONE: (609) 365-7000 X507 FAILURE DESCRIPTION CORRECTIVE ACTION Leak at bottom of strainer Repaired leak by patch weld. Leak on condenser head. Replaced plug and tightened boltse Leak in upper bearing Replaced cooler. cooler. Weld couplings to rrotor Complete. cdoler nozzles. Will not run in auto. Dried and sealed motor lead terminations. overhead Annunciator Rercoved ground and repaired Alann on. level switch. i Boric Acid around packing. Repacked. Valve will not close Replaced Aux. contact * . electricity. Auto roughing filter Repaired control and replaced advance control inoperable. filter. Filter rroves constantly. Leaks. at flange connection Tightened bolts. Seals leaking. Replaced rrechanical seals. Replaced inboard and oui:board

  • -~--

bearings. Valve leaks. Fl "~ 'ted valve.

su~~*oF SAFETY RELA~ MAINTENANCE DEPARTMENT. Maintenance UN-NAME : __ s_al_ern

  1. _l ______ _

DATE: __ o_c_t_o_b_e_r_l_0..:..,_1_9_7_8 __ REPORT MONTH September, 1~78 COMPLETED BY: L.K. Miller TELEPHONE: (609) 365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO. OD-10179 Valve 12CS1 Flange Leak Tightened bolts. i OD-10203* EL 100' Cont. High air leak rate. Repaired poor seal. J?ersonnel Air I.Dck. OD-10204

  1. 15 Service Backwash pipe leaks.

Tenporary pipe patch. Water Strainer. OD-10243

  1. 16 Service Water Packing gland leaks.

Adjusted packing gland. Strainer. OD-10250 Valve 2SW105 Packing leaks.

  • Replaced lubricator wi:th pipe
  • plug
  • OD-10321
  1. l4RHR Smrp Purrp Fails to start in auto *.
  • Cleared ground and cleaned wire terminals.

OD-10338 Valve 1CC196 Flqnge leaks. Tightened bolts. MD-2680

#13 *Reactor Modify #3.Seal Ring Clamp Completed DCR Coolant Pump I.A.W. DCR ED-0146-13 MD-2837
  1. 1 Unit Cask Main heist nctor noisy.

Replaced wonn gear shaft Handling crane aligned clutch assembly. MD-2895

  1. 11 thru 15 Weld couplings to rrotor Completed.

Fan Coil Units cooler nozzles. MD-2923

  1. 11 Concentrate.

Repair heat trace. Insulated exposed conductors. Transfer Purcp. MD-2996

  1. 11 Carrp:>nent
  • 4KV Motor Breaker will
  • Replaced* breaker control relays Cooling PUitp

. not close. OD-10368

  1. 11 Fan Coil Motor Cooler leaks.

'Replaced Tl1otor Cooler. Unit Pagell of 16 8-1-7.Rl

DUCl\\Of; I: NU~ ----- .)U-l /l __ _ SU?J..MAR.~* OF SAFETY RELAe MAINTENANCE DEPARTMENT Maintenance UN-NAME : ___ s;;.,al......;.;;em~#;;.;;l;;,__ ____ _ DATE:~_o_c_t_o_b_e_r __ 1_0 __ 1_9_7_8 __ ~ REPORT MONTH September, 1978 COMPLETED BY: L.K. Miller WORK ORDER EQUIPMENT NO. OP-0346

  1. 12 Reactor Coolant Pump OD-7992
  2. 11 Steam Generator OD-8529 Valve 11.NT22 OD-9488 COntairment ~pray System OD-10024
  3. 11 Gas Stripper Pump

. OD-10042

  1. 16 Service Water

~ Pump. OD-10123 IA Vital Instrunent Inverter OD-10133

  1. 26 Service Water Pump OD-10141
  2. 11 Service Water Pump.

OD-10146

  1. 12 Service Water.

Pump OD-10147

  1. 15 Service Water Strainer.

OD-10158

  1. 14 Fan Coil Unit OD-10163 Valve llCSl Page 12 of 16 8-1-7.Rl TELEPHONE: (609) 365-7000 X507 FAILURE DESCRIPTION CORRECTIVE ACTION Modify #3 Seal Ring IAW Corrpleted DCR.

DCR ED-0146-12. Manway leaks. Repaired gasket surface. Threaded connection Replaced gasket. leaking

  • Intennittent annunciator Replaced circuit board.

alann. ICM discharge pressure. Disassembled and cleaned. Packing gland leaks. Repacked. Blown fuse. Replaced circuit. board and fuses. 4Kv Breaker will not rack Ra~g m:>tor repaired.

  • up~

Flex Coupling leaks. Replaced flex coupling. Flex Coupling leaks. Replaced flex coupling. Packing gland leaks. Repacked. Motor cooler leak. Replaced rrotor cooler. Flange leak. Tightened bolts.

SUMMAR.~l OF SAFETY RELAe MAINTENANCE UN-NAME:. Salem #1 DEPARTMENT Maintenance DATE: O.ctober 10, 1978 --~---~~~~~~- COMPLETED BY: L.K. Miller ~~~~~~~~~~~- REPORT MONTH September, 1978 TELEPHONE: (609) 365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO. r--~~~~-t-~~--~~---r--~~..;..._~--~~~-t-~~---~---~~~~---~1 OD-10451 OD-10449 MD-2846 OD-9071 Page 13 of 16 8-1-7.Rl Valve 1CV6 llRID Bypass Loop. Valve. 13CV78

  1. 11 Boric Acid Transfer PUIIp.

Plug on Valve Body is leaking. Flow orifice FE499A flange leak. Bonnet leak. Replace rrechanical seal. Tightened bolts. Tightened flange. Terrporarily furmanited Replaced seal.

9-1 thru 9-2 9-3 9-4 thru 9-8 9-9 9-10 thru 9-22 9-23 SALEM I OPERATING

SUMMARY

SEPTEMBER, 1978 The unit remained at full load for the day. The unit was at full power until a vacuum leak required the load to be reduced at ~10%/hour to 94% load at 1105. The cause of the vacuum reduction was due to loss of seal water to #11 vacuum pump seals. The seal water was restored and the unit was increased to full load by 1254. The unit remained at full load for the remainder of the day. The unit remained at full load for the day. At 0035 a load decrease was initiated due to high differ-ential pressure across the condensate strainers. Load was decreased at ~5%/hour to 70%. The condensate strainers were cleaned and the load increased at ~5%/hour starting at 1155. The unit was at full load at 1825 and remained at full load for the remainder of the day. The unit remained at full load for the day. At 0045 load was decreased with rods to 76% in an attempt to prevent a reactor trip due to loss of #13 Condensate Pump. At 0046 a Reactor/Turbine trip occurred from 76%. The trip was due to the loss of #11 Feed Pump on low suction pressure resulting in #11 Steam Generator Lo water level with steam flow/feed flow mismatch. Page 14 of 16

9-25 9-26 9-27 9-28 9-29 9-30 The unit was taken critical at 0904. The delay in going critical was caused by faulty pressurizer spray valve operation, repair on #13 Condensate Pump and other main-tenance oriented repairs. The unit was synchronized at 1448. A load increase was initiated at 1500 and the unit reached 47% at 2400. From 0001 to 1300 unit load was increased at 2-3% per hour to 83%. At 1325 unit load was decreased to 69% when #12 Condinsate Pump was taken out of service due to high temperature. A load decrease was initiated at 1506 to 10% per hour. and the unit reached 25% at 2010. Load was de-creased to allow taking #11 Condensate Pump out of service for maintenance. Commenced load increase at 0005 at 1% per hour to a level of 'V32% at 0400. Load was held at 32% while maintenance on #11 and =IH2 Condensate Pump was performed. Commenced load increase at 024*0 from 31% at 'V5% per hour to 55% at 0805. Load increase commenced at 1440 from 57% to 65% by 1610. Load remained at 65% for the remainder of the day while maintenance was being performed on #12 Condensate Pump. Load remained at 'V65% until 2320 when a load increase was commenced at a rate of 'V5% per hour. Load was increased at a rate of 'V5% per hour.Ae 0300 load was leveled off at 81.5%. Load increase recommenced at 0840 to 85% at 0955. At 1600 #11 Steam Generator Feed Pump. indicated bearing temperature problem. Load decrease was commenced at a rate of 5% per hour to a load of 50% at 2315. Page 15 of 16

°<J REFUELING INFORMAT. *_ DOCKET NO.: 50-272 UNIT.: Salem #1 DATE: October 10, 197 COMPLETED BY: L.K. Miller TELEPHONE: 609-365-7000 X507 MONTH: September, 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: May 26, 1979

4.

A.. Will. Technica1 Specification changes or other.* license

5.

6*. amend.men ts be* required:?. YEs** NO NOT DETERMINED-To~oATE September, 1978 B.. Has,_ the* reload* fuelc design. been reviewed. by the. Static~ Operating Review-. Conunittee? YEs* NO x If no, when is *it scheduled? J_a_n_u_a_r_y,_.,_1_9_7_9 _________ _ Scheduled date(s) for submitting proposed licensing action: February, 1979 if required. Important licensing co.nsiderations as.sociated 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, 1 7 O

~

9.

Da.te of last ref.ueling that can be.. discharged to the spent fuel pool assuming the present licensed capacity: April, 1982. Page 16 of 16

  • 8-l-7.R4
  • .............:.;:.:}}
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