ML19030A329
| ML19030A329 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 07/12/1978 |
| From: | Midura H Public Service Electric & Gas Co |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML19030A329 (16) | |
Text
'
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,?o/(. f=-,L-£ Public Service Electric and Gas Company P.O. Box 168 Hancocks Bridge, New Jersey 08038 Salem Nuclear Generating Station July 12, 1978 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Corrmission Washington, D.C.
20555 Dear Sir~
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 0
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In compliance with section 6.9, Reporting Requirements for the Salem 'l 1echnical Specifications, 10 copies of the follm*;ring monthly 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
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.. ~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 MONTH June, 19 7 8 DAY AVERAGE DAILY POWER LEVEL 1
2 3
4 5
/"?,,,
"96 i'
7 8
9 10 11 12 13 14
- 15.
16.
9.. Pg. 2-4 8.1-7.Rl (MWe-NET) 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 Page 2 of 16 DOCKET NO.
50-272 UNIT,
Salem 1
~-------
DATE 7 7 8 COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 X507 DAY AVERAGE DAILY POWER LEVEL (MWE-NET) 17 20 18 164 19 346 20 695 21 806 22 946 23 507 24 197 25 1029 26 971 27 964 28 747 29 873 30 930 31
e OPERATING DA'XA REPORl' 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.__ __ _
r:xx::KE1' NJ.: 5 0- 2 7 2 DATE :
7-1 2-78 caMPLETm BY: L. K. Mj 1J er TEI.EPHONE:609-365-7000 Ext. 507
- 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 ll.
!'.ours In Rep:irting Period 220 4 343
- 12.
NU!lt:er Of Hours Peac'"..cr was C...""1 tical 412.8 1~35.5
- 13.
Reactor Reserve Shutdown Hours 0
- 14.
Hours Generator On-Line JQ :z I 2.
1767.3
- 15.
IJnit Reserve Shutdo~*.n Hours
_o_
16
- Gross '!henial Energy Generated (M<inl
- Z29,895.2 5,235,374.2
- 17.
Gross El~..::ical Energy Generated (M-lH) 235,140 li783,640
- 18.
Net Elect..""1cal. Energy Generated (MWH) 213 diJ2 1,680,791
- 19.
O'nit Se..."'Vice Factor
- 42. :z 40.7
- 20.
O'nit Availability Factor
~2. :z 40.7
- 21.
Unit Capacity Factcr (Using Mo: Net) 2:Z. 5 35.9
- 22.
Unit capacit"f Factor (Using DER Net) 2 :z I 2 35.5
- 23.
Unit Forced OUtage Rate
~
59.3
- 24.
Shut.dcwns Scbedul..ed Over Next 6 :t-mths (~, Date, and Duration o:f EaoJ :
e Cl.milative 8,784 4,478.7 0
4,197.9 0
11,930,594.2 3!.969,950 3£739,009 47.8 47.8 39.5 39.l 33.4
- 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:
8-l-7.R2 Pg. 3-4 Page 3 of 16 INITT.J\\L CRITICALITY IN.!TIAL ELEC'l':R!CIT.l CCMME!CIAL OPERATION Forecast 9/-30/26 11/1/76 12/20/76 Ac..'ti.eved 12/Jl/76 12/25/76 6/30/77
'\\
I.
!IK),
DJ\\'l'E 78-40 3-15-78 78-41 6-15'."':'78 78-42 6-16-78 78-43 6-16-78 78-44 6-17-78 78-45 6-19-78 1
F:
forced S:
Scheduled 8-1-7.R2 Pg. 4 - 4 Page 4 of 16 I
'l'YPEl I
F F
F F
F F
..-\\
UN['l' SlllJ'l'IXMNS 1u~1J rOtl[;;R IZEDOCl'IONS rmr.om*.mm.11,Tune Ml::f!DD
()[o' IXJ!Wl'ION SHlTI'l'ING UCENSE SYSTEM CU'1PONn.J'l' (l!OUl'lS)
RJW:;CJN2 IX11'il'l
!>VENT com~4 com;;'.i Hl'J\\CJDR m:POH'l' #
335.40 B
1 (A)
HA Turbine 2
26.01 A
3 0
A 4 (A) 29.95 A
1 0
A 4 (A) 0 A
4 (A)
I1cm;on:
l\\-B:]uiprrcnl: Pailw:c (r::,.1ilain)
P..-M.:d.n tcwmcc or 'l'c::; t C-Pnfuc.J.j.i19 D-Rcguln l:or.y Res td.ction E-Cpcrtt\\:or '!'.mining & Lio.:?nm~ Bxomi.nntion P-1i*.1mlnistrati ve G--Opcrnti.onti 1 r::rror (r::xpla.in)
U-Ot-J1cr (E:xplnin) 3 HB Filter HA Turbine HC HTEXCH
.CG Valve HC Filter
~~U1o<l:
- 1-MJ.rl\\lill 2-H-.1nual Scr<.1m.
3-.1\\ul:orml:.ic Scr<1m.
4-0th8r (Explain)
DOCKE'r NO. : ~5~Q.,..-::;;...L.2_,7_,,2'"------"-
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 C/\\U~E J\\Nl> COMF.Cl'IVE
/\\CI'ION 'm PHEVJ\\'Nl' rtl:X.1JRrJ'J~Cr, High vibration in No. 3 bearing of main turbine.
Unit outage to make required turbine repairs Feed water flow transient from condensate pump strainers re-sulting in steam generator high level turbine trip.
Turbine break in prior to plan-ned overspeed trip.
Condenser Tube Leak.
Valve 1CV35 diverting waste hold-up tanks.
Clean condensate pump strainers.
4 E:<lilbi t G - Ins t.J:ucl:ions
. for Pmparnl:ion of Data Entry Sheets for I.l.censrJc Event: Rcport(J.* EH) Fila (NVH&;-0161) flow to suction 5
I!:xllJb.l t 1-S,lJl'C Source A.
LOAD REDUCTION B.
CONTINUATION OF PREVIOUS OUTAGE.
I
NO.
DATE 78-46 6-20-78 78-47 6-20-78 78-48 6-21-78 78-49 6-22-78 78-50 6-23-78 78-51 6-26-78 78-52 6-27-78 78-53 6-28-78 78-54 6-28-78 78-55 6-28-78 8-1-7.R2 Page 5 of 16 TYPE1 F
F F
F F
F F
F F
F OORATION REl\\S()rl (HOUHS) 0 A
0 A
0 A
0 A
21.40 A
0 A
0 A
0 A
0 A
0 A
UNIT SllU'l'IXMNS l\\ND PCMER HEDUCTIONS HEPORT MJNTII June 9 19 7 8 METIIOD OF SIIUITING LICENSE SYSTEM CXM'ONENT rum EVENT CODE4 CODES HEACTDR REPORT #
4 (A)
HA Turbirn*
4 (A)
HA Turbirne 4 (A)
HH Filter 4 (A)
HH Filter 3
HS
£i £i £i £i £i £i 4 (A)
HH Filter 4 (A)
HH Filter 4 (A)
HH Filter 4 (A)
HH Filter 4 (A)
HH Filter DOCKET NO.: 50-272 uNrr NAME:
Salem 1 DATE: 7-12-78 COMPLETED BY: __L_._ K. Miller TELEPHONE: 609-365-7000 ext. 507 CAUSE AND CORRECTIVE ACTION 'ID
!?REVEN.I' REOJRREt-lCE High Turbine Vibration High Turbine Vibration Clean condensate pump suction strainers Clean condensate pump suction strainers Turbine trip from 11 steam generator high level. No. 11 feed flow control in manual during instrument surveillance Clean condensate pump suction strainers.
Clean condensate pump suction strainers Clean conden.s ate pump suction strainers Clean 12 condensate pump suction strainers Clean condensate Pump suction strainers.
NO.
DATE 78-56 6-28-78 78-57 6-29-78 78-58 6-29-78 78-59 6-30-78 78-60 6-30-78 8-l-7.R2 Page 6 of 16 TYPE1 F
F F
F F
DURATION RE1\\SON2 (HOURS) 0 A
4 0
A 4
0 A
4 0
A 4
0 A
4 UNI'r SHU'l'IXMNS 1\\ND ro~R REDUCTIONS REPORT MJNI'H
.Tune, 19 7 8 METHOD OF SllUITING LICENSE SYSTEM ro1PONENT IXMN EVENT OJDE4 OJ DES REACIDR REPORT ii (A)
HH Filter (A)
HH Filter (A)
HH Filter (A)
HH Filter (A)
HH Filter DOCKET NO.:
50-272 UNIT NAME:
Salem 1 DATE: 7-12-78 coMPLETED BY: L. K. Miller TELEPllONE:6Q9-365-7000 AXt 507 CAUSE AND CORRECI'IVE ACrION *ro PREVEN.l' REOJRRENCE Clean 11 & 12 steam gen. feed pump strainers Clean condensate pump suction strainers Clean condensate pump suction strainers Clean 12 Heater Drain Pump suction strainers Clean condensate and 12 Heater drain pump suction strainers.
MAJOR PLANT MODIFICA.S REPORT MONTH June.1978
- DCR NO.
EX-0011 ED-0148 ED-0268 ED-0297 ED-0 302 ED-0357 ED-0370 EC-0374 EX-0 381 EC-0383 EX-0391 MD-0093 MD-0094 MD-0107 MD-010 8 MD-0130 MD-0137 MD-0138 OD-0019 OD-0020 OD-0061 PD-0125 PRINCIPLE SYSTEM 500KV P.O.P. System Service Water Diesel Generators lA and le Aux. Feed Reactor Coolant Inst.
Main Turbine Lube Oil Main Turbine Service Water eves Condensate Condensate Boric Acid Rad Waste Rad Waste Main Turbine Lube Oil C.A.R.
P.L. Rods CVCS -
B.A. Recovery Waste Liquid Cont. Pressure Alarm Nitrogen
- DESIGN CHANGE REQUEST 8-1-7. Rl Pageo 7 of 16 DOCKET N1 1~~5~0_-_2_7_2~~~~~~~
Salem l DATE: 7-12-78 COMPLETED BY:
L. K. Miller TELEPHONE:
(609) 365-7000 e_xt. 507 SUBJECT Energize Main Power Transformer for Test Impliment Revision 4 to Remove Redundant Air Regulators Install Spool Pieces at Fan Coil Units Modify Fuel Lines Replace P..FP Recirc Orifices Rework Low Flow Panels to meet Seismic Requirements Extend Oil Lift to No. 8 Bearing Remove Equalizing Line Adjust 15 S.W. Pump Coupling Gap Restore Normal Air Supply to 1CV4 Install Modified Suction Strainer Install Split Bearing in 12 Condensate Pump Install Improved Mechanical Seals in BAT Pumps Install Truck Connection:for Evaporator Bottoms Install Truck Connection for Spent Resin Modify Low Level Alarm Supply Vacuum Pumps from TAC System Mount Unlatching Tool Install Check Valve to Prevent Backf low Install Check Valve to Prevent Backflow Reset to T/S Value Replace 1NT31 with Larger Capacity Valve
MAJOR PLANT MODIFICAT.S REPORT MONTH June 1978 DOCKET NO. :
-=5°""'0._-.... 2.... 7_..2.___ ____ _
UNIT.E: Salem 1
~~~------~~~~~~
DATE:
7-12-78
- DCR NO.
EX-0011 ED-0148 ED-0268 ED-0297 ED-0302 ED-0357 ED-0370 10CFR5 0. 5 9.
COMPLETED BY:
L. K. Miller TELEPHONE: (609) 365-7000 ext. 507 SAFETY EVALUATION 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.
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.
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.
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.
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.
This is a change to meet original design commitments.
Criteria for an unreviewed safety question are not met.
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.:
MAJOR PLANT MODIFICAT.1S UNIT*=
DATE:
50-272 Salem 1
- REPORT MONTH June 1978 7-12-78
- DCR NO.
EC-0374 EX-0381 EC-383 EX-0391 MD-0093 MD-0094 MD-0107 MD-0108 10CFR50. 59.
COMPLETED BY: L. K. Miller TELEPHONE: (609) 365-7000 ext. 507 SAFETY EVALUATION 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.
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.
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.
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.
Criteria for an unreviewed safety question are not met.
An unreviewed safety question is not' involved.
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.
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
MAJOR PLANT MODIFICAT.S DOCKET NO.:
~5u0~-~2~7~2;.__~--~
UNIT ~:
.......:S:::.:a~l""'e~m~J~----
DATE:
7-12-78 REPORT MONTH_;:;J~un==e;_....;;1~9~7~8"------~
- DCR NO.
MD-0130 MD-0137 MD-0138 OD-0019 OD-0020 OD-0061 PD-0125 10CFR50.59 COMPLETED BY:
L. K. Miller TELEPHONE: (609) 365-7000 ext. 507 SAFETY EVALUATION Not safety related, does not affect any safety related equipment or Tech. Spec., and does not require a safety analysis to be performed.
Systems are non-safety related.
This design change does not affect any presently performed safety analyses nor does it create any new safety hazards.
The bases if the Tech.
Specs. are not affected.
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.
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.
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.
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.
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 OD-9027 OD-9057 OD-9099 OD-9l05 No. 15 & 16 Screen ~P 1 s High S.W. Pump Screens 1CV2 Valve Repair valve bonnet leak 1WL12 Valve Valve failed to oper-ate Cleaned out level indica-tion bubbler tubes Replaced bonnet gaskets, seat gaskets and body studs Installed jump on valve relay to allow operation.
D.C.R. submitted for permanent change.
No. 13 charging pump cooling flow indication Freed up indicator to pump not working No. 15 S.W.
Strainer Packing leak Repacked Strainer Pump Strain.
OD-9109 No. 11 S.W.
No auto or manual Pump ScreenE operation Recalibrated PD-2713 OD-9ll4 OD-9124 OD-9129 OD-9147 OD-9199 OD-9215 OD-92l9 No. 11 Fan Coil Unit Aux. Feed
!Aux. Feed Pumps No. 14 & 15 S.W.. Pump strainers 13RC16 Valve 12SW24 Val VE No. 11 s. w.
Pump Screen Page 11 of 16 Low speed breaker won't discharge Removed Breaker and made adjustments to control device and tripping springs.
No flow indication for Repaired leaking instru-flow to No. 14 Steam ment valve.
Generator No. 11 & 12 Aux. Feed Pumps did not start when No. 11 & 12 S.G.
F.P. Tripped.
Packing leaks Packing Leak Valve operator not working No auto or--...JTlanual operation Replaced faulty relay in No. 11 S.G.F.P. Controls.
Repaired Packing leaks Replaced packing and tightened nut.
Installed new operator diaphragm.
Repaired leaky tube fitting on pressure cont.
MONTHLY SAFETY RELATED WORK ACTIVITIES June 1978 W. 0. NUMBER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION MD-2498 MD-2723 MD-2746 MD-2773 4KV. ACB's Inspect for cracked welds ICI 125V.
Will not carry rated Batt. Cbgr. load Inspected.
Replaced two Diodes, SCR's and cards lCVZ Valve Replace body and BonnetReplaced Studs studs 15 SW. Pillnp Strainer Drive Shaft Strainer Bent Straightened & Aliened shaft.
Replaced Flanges OD-007027 12SW122 Valve 12SW122 Did not operate Reset Valve limit switch.
during testing.
OD-008160 llMS 171 Valve Valve leaking through OD-008806 No. 11 Aux. Repair & change filter Bldg. Suppl1 Fan Replaced valve stem, seat and gaskets.
Changed both sets of filters 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 not position during testing
~Adjusted CAAl au.d 1CH74 limit switches.
OD-8888 OD-8949 OD-8977 OD-8986 OD-8988 OD-8995 11 RH 18 Valve No open indication Adjusted Limit Switch 1WG36 valve Valve does not control Calibrated valve controll-.
Pressure Properly.
or Control Rm.
Rolimatic Filter not
~entilation moving in auto or manual Replaced Drive Chain and tightened motor hold down bolts No. 11 Saft. Pump Flow Indication Rebuilt flow rater injection not working.
Pump No. 11 Accu~ Redundant channels do Vented all accumulator ulator level not agree reference bellows 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 PD-4778 PD-4779 PD-4782 PD-4787 PD-4794 PD-4805 PD-4819 RE-142 15 S.W. Pum1 Adjust motor coupling Adjusted coupling gap from.075" to.040" No. 11 Accu-mulator_
level 1CV2 Valve ROP Control No. 11 6.T Channel level indication out of spec.
Restroke valve 1CV2 Replace Blown Fuse &
S.C.R. in llBD Cabinet Channel out of spec.
on functional test.
Recalibrated indicator &
level alarm points Restroke valve, adjusted limit switches.
Replaced fuse and S.C.R.
Recalibrated channel.
No. 12 R.H.I Cooling flow indication Repaired flow rator stem Pump to pump not working checked setpoint &
operation.
ROD Control Urge_nt failure in llAC Replaced 3 Master cycle
& 12BD Cabinet cards.
14MS18 Valve will not open.
Replaced ruptured Valve operator diaphragm.
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 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
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 MONTH:
June 1978 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
- 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.
B.
In-Core In Spent Fuel Storage 193 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