ML19030A329

From kanterella
Jump to navigation Jump to search
Submit Monthly Operating Report for the Month of June 1978 for Salem No. 1
ML19030A329
Person / Time
Site: Salem  PSEG icon.png
Issue date: 07/12/1978
From: Midura H
Public Service Electric & Gas Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML19030A329 (16)
v • d • e


Text

t?/~

PS~G '

Public Service Electric and Gas Company P.O. Box 168 Hancocks Bridge, New Jersey 08038

,?o/(. f=-,L-£ Salem Nuclear Generating Station July 12, 1978 Director, Office of Inspection and Enforcement _..

U.S. Nuclear Regulatory Corrmission Washington, D.C. 20555 0

(/)

'°

-..1 OJ rn C)

-*i c_ en!::::!

u c

I r=-i<

OJ  ::::JrYJ a:;C:::,- <o

-u-t:-- ~

Dear Sir~ ).,

. -*en -  ! (')CJ z~~ ~u;

-l OU>~

cf'Tl
0

~

~ .

c:::U

-VJ MONTHLY OPERATING REPORT < 5

-IC:

j 0

SALEM NO. 1 rTJ c:>

C)

(/)

DOCKET NO. 50-272 \,;l In compliance with section 6.9, Reporting Requirements for the Salem 'l echnical Specifications, 10 copies of the follm*;ring monthly 1

operating reports for the month of June 1978 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Surmnary of Safety Related Maintenance Operating Summary Refueling Information Sincerely yours, H. J. Midura Manager - Salem Generating Station LfuVi: j Cr.1 cc: Mr. Boyce H. Grier Director of U. S. NRC Office of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pa. 19406 Director, Office of Management Information and Program Control m~a*e:*~ Nuclear F,egulatory Commission

~@'1~~ington, D.C. 20535 ll-:\llSlll' Enc.** "sEm1rn Page l of 16 8-l-7.R4 95*2189 (4M) 3-78

e AVERAGE DAILY UNIT POWER LEVEL

  • DOCKET NO.

- 272 UNIT , Salem 1

~-------

DATE 7 7 8 COMPLETED BY

- -L.-K.- -Miller TELEPHONE 609-365-7000 X507 MONTH June, 19 7 8 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) (MWE-NET) 1 0 17 20 2 0 18 164 3 0 19 346 4 0 20 695 5 0 21 806

/"?,,,

"96 i' 0 22 946 7 0 23 507 8 0 24 197 0 25 1029 9

0 26 971 10 0 964 11 27 12 0 28 747 13 0 29 873 14 30 930

15. 0 31 - - -

16 . 0 9 . Pg. 2-4 8.1-7.Rl Page 2 of 16

e OPERATING DA'XA REPORl' r:xx::KE1' NJ.:

DATE :

caMPLETm BY: L.

5 0- 2 7 2 7-1 2-78 K. Mj 1J er TEI.EPHONE:609-365-7000 Ext. 507 OPERATING STAIDS

l. unit Narte: s al em No *. 1 Notes:
2. P.eporting Peric:d: ...........1....1..,.1n...,*8...__.1_,9,_7,,_...s_ _ _ _ _ _ _ __
3. L.icsnsed Tr.eI:ma..l. Pol.er (MVt) : _,..3'""3.,.3,..8.._______
4. Nanet=ilate Rating (Gross I-Me) : _ ... 1....1...3...,5_______
5. Cesign Elec-..:ical. Rating (Net !<Me) : _1.,,,.0_9._.0.________
6. 1'1..aximum I::epP.ndable capacity (Gross ~) :_1_1.__2.... 4_ __
7. MaximLlm Cependable Capacity (Net I-We): _1'""0...,7~9.__ ___
8. If Changes Cccur in capacii:'.! Ratings (Items NU!l'b:r 3 Tluough 7) Since La.st ~rt, Give Reason:
9. Pcwer Lavel To w1ti.ch Pestricted, If ."A.rr:f (Net llie) : ....................__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __
10. P.easons For Pestrictions, If Any: __.N...o=n...e_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __

This M:mtb. Year to Date Cl.milative ll.  !'.ours In Rep:irting Period 220 4 343 8,784

12. NU!lt:er Of Hours Peac'"..cr was C...""1 tical 412.8 1~35.5 4,478.7
13. Reactor Reserve Shutdown Hours 0 0
14. Hours Generator On-Line JQ :z I 2. 1767.3 4,197.9
15. IJnit Reserve Shutdo~*.n Hours _o_ 0 16
  • Gross '!henial Energy Generated (M<inl :Z29,895.2 5,235,374.2 11,930,594.2
17. Gross El~..::ical Energy Generated (M-lH) 235,140 li783,640 3!.969,950
18. Net Elect..""1cal. Energy Generated (MWH) 213 diJ2 1,680,791 3£739,009
19. O'nit Se..."'Vice Factor 42. :z 40.7 47.8
20. O'nit Availability Factor ~2. :z 40.7 47.8
21. Unit Capacity Factcr (Using Mo: Net) 2:Z. 5 35.9 39.5
22. Unit capacit"f Factor (Using DER Net) 2 :z 2 I 35.5 39.l
23. Unit Forced OUtage Rate ~ 59.3 33.4
24. Shut.dcwns Scbedul..ed Over Next 6 :t-mths (~, Date, and Duration o:f EaoJ :

e

23. If Shut Co'Nn At .Er..d of Rep:lrt Pe...+icd! Estimated Date of Startup: - - - - - - - - - - - - - - - - - - - - - -
26. Units In Test St.atus(Prior to Ccmrercial C'9erationl:

Forecast Ac..'ti.eved INITT.J\L CRITICALITY 9/-30/26 12/Jl/76 8-l-7.R2 IN.!TIAL ELEC'l':R!CIT.l 11/1/76 12/25/76 Pg. 3-4 CCMME!CIAL OPERATION 12/20/76 6/30/77 Page 3 of 16

.. - \

UN['l' SlllJ'l'IXMNS 1u~1J rOtl[;;R IZEDOCl'IONS DOCKE'r NO. : ~5~Q.,..-::;;...L.2_,7_,,2'"------"-

rmr.om* .mm.11 ,Tune UN 1 'f NMm: - Sa:J,.er~!.__1_ ______ _

DJ\'l'E: _]~_12_-:,]_8__ ____ .__ _

C01-H'!.E'l'J::I) BY: L. K. Miller I

'l'ELEPllONE: 6-oi:36s-=_ioo 0 --~~t5071 Ml::f!DD I IXJ!Wl'ION 2

()[o' SHlTI'l'ING UCENSE SYSTEM CU'1PONn.J'l' C/\U~E J\Nl> COMF.Cl'IVE

!IK), DJ\'l'E 'l'YPEl (l!OUl'lS) RJW:;CJN IX11'il'l  !>VENT com~ 4 com;;'.i /\CI'ION 'm Hl'J\CJDR m:POH'l' # PHEVJ\'Nl' rtl:X.1JRrJ'J~Cr, I

78-40 3-15-78 F 335.40 B 1 (A) - - - HA Turbine High vibration in No. 3 bearing of main turbine. Unit outage to make required turbine repairs 78-41 6-15'."':'78 F 26.01 A 3 - - - HB Filter Feed water flow transient from condensate pump strainers re-sulting in steam generator high level turbine trip.

78-42 6-16-78 F 0 A 4 (A) - - - HA Turbine Turbine break in prior to plan-ned overspeed trip.

78-43 6-16-78 F 29.95 A 1 -. - - HC HTEXCH Condenser Tube Leak.

78-44 6-17-78 F 0 A 4 (A) - - - .CG Valve Valve 1CV35 diverting flow to waste hold-up tanks.

78-45 6-19-78 F 0 A 4 (A) - - - HC Filter Clean condensate pump suction I strainers.

1 2 3 4 5 F: forced I1cm;on: ~~U1o<l:

  • E:<lilbi t G - Ins t.J:ucl:ions I!:xllJb.l t 1-S,lJl'C S: Scheduled l\-B:]uiprrcnl: Pailw:c (r::,.1ilain) 1-MJ.rl\lill .for Pmparnl:ion of Data Source P..-M.:d.n tcwmcc or 'l'c::; t 2-H-.1nual Scr<.1m. Entry Sheets for I.l.censrJc C-Pnfuc.J.j.i19 3-.1\ul:orml:.ic Scr<1m. Event: Rcport(J.*EH) Fila D-Rcguln l:or.y Res td.ction 4-0th8r (Explain) (NVH&;-0161)

E-Cpcrtt\:or '!'.mining & Lio.:?nm~ Bxomi.nntion

'\ P-1i*.1mlnistrati ve 8-1-7 .R2 G--Opcrnti.onti 1 r::rror (r::xpla.in) A. LOAD REDUCTION U-Ot-J1cr (E:xplnin)

Pg. 4 - 4 B. CONTINUATION OF PREVIOUS I. Page 4 of 16 OUTAGE.

UNIT SllU'l'IXMNS l\ND PCMER HEDUCTIONS DOCKET NO.: 50-272 HEPORT MJNTII June 9 19 7 8 uNrr NAME: Salem 1 DATE: 7-12-78 COMPLETED BY: __L_._ K. Miller TELEPHONE: 609-365-7000 ext. 507 METIIOD OF OORATION SIIUITING LICENSE SYSTEM CXM'ONENT CAUSE AND CORRECTIVE 1 REl\S()rl NO. DATE TYPE (HOUHS) rum EVENT CODE4 CODES ACTION 'ID HEACTDR REPORT #  !?REVEN.I' REOJRREt-lCE 78-46 6-20-78 F 0 A 4 (A) - - - HA Turbirn* High Turbine Vibration 78-47 6-20-78 F 0 A 4 (A) - - - HA Turbirne High Turbine Vibration 78-48 6-21-78 F 0 A 4 (A) - - - HH Filter Clean condensate pump suction strainers 78-49 6-22-78 F 0 A 4 (A) - - - HH Filter Clean condensate pump suction strainers 78-50 6-23-78 F 21.40 A 3 - - - HS £i £i £i £i £i £i Turbine trip from 11 steam generator high level. No. 11 feed flow control in manual during instrument surveillance 78-51 6-26-78 F 0 A 4 (A) - - - HH Filter Clean condensate pump suction strainers.

78-52 6-27-78 F 0 A 4 (A) - - - HH Filter Clean condensate pump suction strainers 78-53 6-28-78 F 0 A 4 (A) - - - HH Filter Clean conden.s ate pump suction strainers 78-54 6-28-78 F 0 A 4 (A) - - - HH Filter Clean 12 condensate pump suction strainers 78-55 6-28-78 F 0 A 4 (A) - - - HH Filter Clean condensate Pump suction strainers.

8-1-7 .R2 Page 5 of 16

UNI'r SHU'l'IXMNS 1\ND ro~R REDUCTIONS DOCKET NO.: 50-272 REPORT MJNI'H .Tune , 19 7 8 UNIT NAME: Salem 1 DATE: 7-12-78 coMPLETED BY: L. K. Miller TELEPllONE:6Q9-365-7000 AXt 507 METHOD OF DURATION SllUITING LICENSE SYSTEM ro1PONENT CAUSE AND CORRECI'IVE NO. DATE TYPE1 (HOURS) RE1\SON2 IXMN EVENT OJDE4 OJDES ACrION *ro REACIDR REPORT ii PREVEN.l' REOJRRENCE 78-56 6-28-78 F 0 A 4 (A) - - - HH Filter Clean 11 & 12 steam gen. feed pump strainers 78-57 6-29-78 F 0 A 4 (A) - - - HH Filter Clean condensate pump suction strainers 78-58 6-29-78 F 0 A 4 (A) - - - HH Filter Clean condensate pump suction strainers 78-59 6-30-78 F 0 A 4 (A) - - - HH Filter Clean 12 Heater Drain Pump suction strainers 78-60 6-30-78 F 0 A 4 (A) - - - HH Filter Clean condensate and 12 Heater drain pump suction strainers.

8-l-7.R2 Page 6 of 16

.. MAJOR PLANT MODIFICA.S DOCKET N11~~5~0_-_2_7_2~~~~~~~

REPORT MONTH June .1978 UN IT NAM : Salem l DATE: 7-12-78 COMPLETED BY: L. K. Miller TELEPHONE: (609) 365-7000 e_xt. 507

  • DCR NO. PRINCIPLE SYSTEM SUBJECT EX-0011 500KV Energize Main Power Transformer for Test ED-0148 P.O.P. System Impliment Revision 4 to Remove Redundant Air Regulators ED-0268 Service Water Install Spool Pieces at Fan Coil Units ED-0297 Diesel Generators lA Modify Fuel Lines and le ED-0 302 Aux. Feed Replace P..FP Recirc Orifices ED-0357 Reactor Coolant Inst. Rework Low Flow Panels to meet Seismic Requirements ED-0370 Main Turbine Lube Oil Extend Oil Lift to No. 8 Bearing EC-0374 Main Turbine Remove Equalizing Line EX-0 381 Service Water Adjust 15 S.W. Pump Coupling Gap EC-0383 eves Restore Normal Air Supply to 1CV4 EX-0391 Condensate Install Modified Suction Strainer MD-0093 Condensate Install Split Bearing in 12 Condensate Pump MD-0094 Boric Acid Install Improved Mechanical Seals in BAT Pumps MD-0107 Rad Waste Install Truck Connection:for Evaporator Bottoms MD-010 8 Rad Waste Install Truck Connection for Spent Resin MD-0130 Main Turbine Lube Oil Modify Low Level Alarm MD-0137 C.A.R. Supply Vacuum Pumps from TAC System MD-0138 P.L. Rods Mount Unlatching Tool OD-0019 CVCS - B.A. Recovery Install Check Valve to Prevent Backf low OD-0020 Waste Liquid Install Check Valve to Prevent Backflow OD-0061 Cont. Pressure Alarm Reset to T/S Value PD-0125 Nitrogen Replace 1NT31 with Larger Capacity Valve
  • DESIGN CHANGE REQUEST 8-1-7. Rl Pageo 7 of 16

DOCKET NO . : -=5°""'0._-....2....7_..2.____ _ _ __

MAJOR PLANT MODIFICAT.S UNIT . E : Salem 1

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

REPORT MONTH June 1978 DATE: 7-12-78 COMPLETED BY: L. K. Miller TELEPHONE: (609) 365-7000 ext. 507

  • DCR NO. 10CFR5 0. 5 9. SAFETY EVALUATION EX-0011 While the unit is in cold shut-down a test is to be performed on the main step-up transformer. This test is to last approx-imately two weeks and upon completion, the test connections will be removed and the system will be restored to normal conditions. Criteria for an unreviewed safety question are not met.

ED-0148 This system effectively adds parallel logic to the opening signal for the pressurizer relief valves. Consequences of any presently performed safety analyses are not changed, and the probability of presently analyzed accidents (small loca, cap) is not significantly altered. The Bases of the Tech.

specs remain unchanged and valid.

ED-0268 This design change does not affect any presently performed safety analyses nor does it create any new safety hazards.

The bases of the technical specifications are not affected.

ED-0297 This modification will not reduce the margin of safety in any Technical Specification, cause an accident or malfunc-tion not previously analyzed i.n the FSAR, nor increase the probability of occurrence or consequences of such an accident.

ED-0302 This modification will not reduce the margin of safety in any Technical Specification, cause an accident or malfunc-tion not previously analyzed in the FSAR, nor increase the probability of occurrence or consequences of such an accident.

ED-0357 This is a change to meet original design commitments. Criteria for an unreviewed safety question are not met.

ED-0370 Functional operation is unchanged. Design change will improve reliability. Criteria for an unreviewed safety ques. are not mEet.

  • DESIGN CF.ANGE REQUEST Page 8 of 16

DOCKET NO.: 50-272 MAJOR PLANT MODIFICAT.1S UNIT*= Salem 1

  • REPORT MONTH June 1978 DATE: 7-12-78 COMPLETED BY: L. K. Miller TELEPHONE: (609) 365-7000 ext. 507
  • DCR NO. 10CFR50. 59. SAFETY EVALUATION EC-0374 This design change does not affect any presently performed safety analysis nor does it create any new safety hazards.

The basis of the Technical Specifications are not affected.

The system involved is non-nuclear, non-safety related.

EX-0381 The experiment is being conducted to utilize an adjustment capability in the pump design which was provided as a mechanism to improve pump performance. An unreviewed safety question is not involved.

EC- 383 The containment isolation function and fail safe design of valve 1CV4 is not affected by this change. The 10 second closure time will be maintained and verified by testing.

EX-0391 This experiment does not affect any presently performed safety analyses nor does it create any new safety hazards.

The bases of the Tech. Spec's are not affected.

MD-0093 Criteria for an unreviewed safety question are not met.

MD-0094 An unreviewed safety question is not' involved.

MD-0107 System is non safety related. This design change does not affect any presently performed safety analyses nor does it create any new safety hazards. The baseb of the Tech. Specs.

are not affected.

MD-0108 The piping affected is non-safety related. This design change does not affect any presently performed safety anal-yses nor does it create any new safety hazards. The bases 1 of the Technical Specifications are not affected.

  • DESIGN CF~Z\NGE REQUEST Page 9 of 16

DOCKET NO.: ~5u0~-~2~7~2;.__~--~

~: .......:S:::.:a~l""'e~m~J~----

MAJOR PLANT MODIFICAT.S UNIT REPORT MONTH_;:;J~un==e;_....;;1~9~7~8"------~

DATE: 7-12-78 COMPLETED BY: L. K. Miller TELEPHONE: (609) 365-7000 ext. 507

  • DCR NO. 10CFR50.59 SAFETY EVALUATION MD-0130 Not safety related, does not affect any safety related equipment or Tech. Spec., and does not require a safety analysis to be performed.

MD-0137 Systems are non-safety related. This design change does not affect any presently performed safety analyses nor does i t create any new safety hazards. The bases if the Tech.

Specs. are not affected.

MD-0138 This design change will not affect a previously performed safety analysis. Thr bracket is to be used during refueling outages and will not affect the safe operation of the plant.

OD-0019 This design change involves the addition of a check valve to prevent reverse flow in a primary water flush line.

Criteria for an unreviewed safety question are not met.

OD-0020 This change involves the addition of a check valve to prevent reverse flow in Primary Water line. Criteria for an unre-viewed safety question are not met.

OD-0061 This change will increase the margin of safety as defined in the Technical Specification 3.6.1.4. Required in orqer to meet Tech. Spec. Setpoint Requirements with change - safety analyses are not affected.

PD-0125 This change is requested to protect regulator valve 1NT31 when nitrogen is supplied through valve 1NT54. This portion of the system is not safety related nor is the system fuction altered. Consequently, this change does not: (1) increase probability of or consequences of an accident, (2) create a possibility for same, or (3) reduce a previously defined margin of safety.

  • DESIGN CHANGE REQUEST Pag§ 10 of 1

MONTHLY SAFETY RELATED WORK ACTIVITIES June 1978 W. 0. NUMBER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION OD-9019 No. 15 & 16 Screen ~P 1

s High Cleaned out level indica-S.W. Pump tion bubbler tubes Screens OD-9027 1CV2 Valve Repair valve bonnet Replaced bonnet gaskets, leak seat gaskets and body studs OD-9057 1WL12 Valve Valve failed to oper- Installed jump on valve ate relay to allow operation.

D.C.R. submitted for permanent change.

OD-9099 No. 13 cooling flow indication Freed up indicator charging to pump not working pump OD-9l05 No. 15 S.W. Strainer Packing leak Repacked Strainer Pump Strain.

OD-9109 No. 11 S.W. No auto or manual Recalibrated PD-2713 Pump ScreenE operation OD-9ll4 No. 11 Fan Low speed breaker Removed Breaker and made Coil Unit won't discharge adjustments to control device and tripping springs.

OD-9124 Aux. Feed No flow indication for Repaired leaking instru-flow to No. 14 Steam ment valve.

Generator OD-9129 !Aux. Feed No. 11 & 12 Aux. Feed Replaced faulty relay in Pumps Pumps did not start No. 11 S.G.F.P. Controls.

when No. 11 & 12 S.G.

F.P. Tripped.

OD-9147 No. 14 & 15 Packing leaks Repaired Packing leaks S.W .. Pump strainers OD-9199 13RC16 Valve Packing Leak Replaced packing and tightened nut.

OD-9215 12SW24 Val VE Valve operator not Installed new operator working diaphragm.

OD-92l9 No. 11 s. w. No auto or--...JTlanual Repaired leaky tube Pump Screen operation fitting on pressure cont.

Page 11 of 16

MONTHLY SAFETY RELATED WORK ACTIVITIES June 1978 W. 0. NUMBER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION MD-2498 4KV. ACB's Inspect for cracked Inspected.

welds MD-2723 ICI 125V. Will not carry rated Replaced two Diodes, SCR's Batt. Cbgr. load and cards MD-2746 lCVZ Valve Replace body and BonnetReplaced Studs studs MD-2773 15 SW. Pillnp Strainer Drive Shaft Straightened & Aliened Strainer Bent shaft. Replaced Flanges OD-007027 12SW122 12SW122 Did not operate Reset Valve limit switch.

Valve during testing.

OD-008160 llMS 171 Valve leaking through Replaced valve stem, seat Valve and gaskets.

OD-008806 No. 11 Aux. Repair & change filter Changed both sets of Bldg. Suppl1 filters Fan OD-008941 12 Bat. TankLevel Indication failed Unplugged high side bubbler tube OD-008953 llRTD by~ass~ocate & repair valve Replaced valve gaskets loop leaks OD-008956 CAAl & 1CH74 Dampers & valve did ~Adjusted CAAl au.d 1CH74 not position during limit switches.

testing OD-8888 11 RH 18 No open indication Adjusted Limit Switch Valve OD-8949 1WG36 valve Valve does not control Calibrated valve controll-.

Pressure Properly. or OD-8977 Control Rm. Rolimatic Filter not Replaced Drive Chain and

~entilation moving in auto or tightened motor hold down manual bolts OD-8986 No. 11 Saft. Pump Flow Indication Rebuilt flow rater injection not working.

Pump OD-8988 No. 11 Accu~ Redundant channels do Vented all accumulator ulator level not agree reference bellows OD-8995 No. 15 Switcn Damper in0-1cation not Rebuild solenoid SV-1036 gear ventila working & adjusted limit switch

  • ~..; --

Page 12 of 16

MONTHLY SAFETY RELATED WORK ACTIVITIES

.T11n!"> 1 q7R W. 0. NUMBER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION OP-0344 15 S.W. Pum1 Adjust motor coupling Adjusted coupling gap from .075" to .040" PD-4778 No. 11 Accu- level indication out Recalibrated indicator &

mulator_ of spec. level alarm points level PD-4779 1CV2 Valve Restroke valve 1CV2 Restroke valve, adjusted limit switches.

PD-4782 ROP Control Replace Blown Fuse & Replaced fuse and S.C.R.

S.C.R. in llBD Cabinet PD-4787 No. 11 6.T Channel out of spec. Recalibrated channel.

Channel on functional test.

PD-4794 No. 12 R.H.I Cooling flow indication Repaired flow rator stem Pump to pump not working checked setpoint &

operation.

PD-4805 ROD Control Urge_nt failure in llAC Replaced 3 Master cycle

& 12BD Cabinet cards.

PD-4819 14MS18 Valve will not open. Replaced ruptured Valve operator diaphragm.

RE-142 Incore Flux Repair sticky drive Remove Paint from drive Mapping sys. Unit unit reel.

Page 13 of 16

MO.HLY OPERATING

SUMMARY

SALEM I JUNE, 1978 -1 6-10 The reactor was taken critical seven times during the day for operator training.

6-14 The reactor was taken critical at 1502. The unit was synchron-ized at 2324 and a slow power increase was started.

6-15 The unit tripped at 0224. The cause was 13 Steam Generator high high, l;evel initiated by clogging of a condensate pump suction strainers and the subsequent starting of another condensate pump.

The reactor was taken critical at 2225.

6-16 The unit was synchronized at 0425 and power was slowly raised to about 18% for an eight hour turbine "soak" prior to a planned overspeed trip. At 1043 power was decreased and the unit taken off the line due to leaking condenser tubes and to perform the turbine overspeed test.

6-17 The unit was synchronized at 1640 and a slow power increase was started. The unit reached 20% at 2200.

6-18 The unit operated at 20% power all day.

6-19 During the day unit load increased from 20% to 55%.

6-20 Load was increased to 70% and the unit operated here the majority of the day.

6-21 During the day load increased to 85%.

6-22 Power was decreased to 70% to clean condensate pump suction strainers.

The unit began a load increase reaching full load at 2000.

6-23 A reactor trip occurred at 1126 from 100% power due to 11 Steam Generator high-high level. The trip occurred following the per-formance of a regularly scheduled surveillance procedure for #11 Steam Generator level control.

Page 14 of 16

1 6-24 The reactor was taken critical at 0435 and the unit was synchronized at 0850. During the day unit load increased to 70%.

6-25 The unit reached full load at 0855. A load decrease-was started at 1725 in order to clean condensate pump suction strainers.

6-26 At 0248 a power increase was started from 70% power. The unit reached full load at 2000.

6~27 At 1500 a load decrease was started in order to clean condensate pump suction strainers. The unit reached 70% power at 1900. At 2200 a load increase was started.

6-28 At 0125 a load decrease was started from 90% in order to clean condensate pump suction strainers. At 0352 the unit reached 70%.

At 0443 a load 'increase began until 0900 when the unit reached 93%. At 0948 a load decrease of approximately 30%/HR, was started due to problems with 12 Heater Drain Pump and clogging of condensate pump suction strainers. The unit reached 64% at 1054. At 2135 load was -decreased to 50% in order to clean steam generator feed pump suction strainers.

6-29 At 0330 a load increase was started. The unit reached 100% load at 1000. Load was later decreased in order to clean condensate pump strainers * -

6-30 At 0223 a load increase was started. The unit reached 100% load at 0030. At 1112 a load decrease to 90% was started to clean a heater drain pump suction strainer. At 1800 a load decrease to 70% was started to clean condensate pump suction strainers.

Page 15 of 16

  • REFUELING INFORMATION DOCKET NO.:_:::;s~o_-~2~7~2 _________

UNIT:salem No. 1 DATE: 7-12-78 COMPLETED BY:ri, K, Mjller TELEPHONE:6Q9-365-7000 Ext. 507 MONTH: June 1978

1. Refueling information. has changed from last month:

YES NO ...........x..___

2. Scheduled date of next refueling: _A=p...___r=i=l___l~,_..1~9~7~9.._........._ _ _ _ _- _ _ __
3. Scheduled date for restart following refueling: May 29, 1979
4. A. Will. Techni.cal Specification changes or other license amendments be required? YES

---- NO NOT DETERMINED TO-DATE~nne. 1978 B.. Has the reload fuel design been reviewed by the Station Operating Review C'onunittee? YES

NO X If no, when is it' scheduled'? _J_a_.n....u. . . a.. .,ry.. . _. _,___1__9_.7...9___________

5. Scheduled date (s) for submitting proposed licens*ing action:

Fehr11ary, J 919 ; f *req11j red 6.. Important licensing considerations associated with refueling:

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_1.....o__________

9. Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:* April, 1982 Page 16 of 16
Retrieved from "https://kanterella.com/w/index.php?title=ML19030A329&oldid=2503570"