ML18081A914
| ML18081A914 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 01/11/1980 |
| From: | Miller L Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18081A913 | List: |
| References | |
| NUDOCS 8001170337 | |
| Download: ML18081A914 (22) | |
Text
~-,
AVERAGE DAILY UNIT POWER LEVEL MONIH December 1979 DAY AVERAGE DAILY POWER LEVEL 1
2 3
4 5
6 7
8 9
10 11 1.2 13 14
- 15.
16 Pg. 2 of 23 8.1-7.PJ.
(MWe-NET)
- O 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
DOCKET NO.
50-272 UNIT Salem #1 DATE January 11, 1980
. CO.'-'IPLETED BY L. K. Miller TELEPHONE 609-365-7000 X507 DAY AVERAGE DAILY POWER LEVEL (MWE-NET) 17 0
18 0
L9 0
20 0
21 0
22 o*
23 0
24 0-25 0
26 0
27 0
28 130' 29 0
30 90 31 149 8001170.33 7
50-272 rx:x:KET NJ.: ___________ _
~
J.;;;.an-.u.;;;.a-.r;;;..Yi-..;l;.;;l'-',~l;..:;.9;..:;.8.;;.0_
CCMPIE.IEJBY: __
L_._K_._M_i_l_l_e_r __ _
~: 609-365~7000 X507
- l. llnit Ncme: ___
s_a._1_e_m_ll_1_..,.....,... _______ _
- 2.
Rej;:ortinq J?eriod: ____
D_e_c_e_* m_h_*e_r___,,1,.,,9,.,,7.... 9 __...._ __
- 3. Lic:ensel;1 Thema.l J?or.er (~>: ____
3_33_8 ____ _
Notes:
- 4.
Naneplate Ratinq (Gmss K-Je): ____
1_1_3_5 ____ _
- s.
Design Electrical. Ratinq (Net MWe) : __
1_09_0 ____ _
- 6.
Max:inUJln Dependable Capacity (Gl:OSs. K-Je) : __ 1
.... 1_2_4 __ _
- 7.
Max:il!UJln* Cependable Capacity (Net MWe) : ___
1_0_7_9 __
- 8. If Changes Occur in Capaciey Ratings (Item Nul?Cer 3 Through 7) Since Last P.epor:t, Give Reason:
NONE
- 9.
Power* Level To Which* Restricted, If Aey* (Net M-Tel : ___ N_o_N_E------------------
- 10.
Reasons For Restricticns, If Aey: ___ N_O_N_E------------------------
This M:nth Year to Date CUl!ulative Hours In Rey;:orting Period 744 8,760 21,961
- u.
- 12.
Nllll'tler Of Hours Reactor Was Critical 246.9 2,431.4 10,088.0
- 13. Reactor Reserve Shutdown Hours 0
22.7 22.7
- 14. eours Generator On-Line.
71.8 2,233.l 9,531.l
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gmss The:cna.l Energy Generated CmHl 69,0710 6,551,561 27,536,297
- 17. Gmss Electrical Energy Generated (K-IH) 12,920 2,194,690 9,167,500
- 18. Net Electrical Energy Generated (MWH)
. (2,261) 2,042,610 8,629,590
- 19. O'nit Service Factor 8.6 25.4 43.4
- 20. llnit Availability Factor 8.6 25.4 43.4
- 21. O'nit Capaciey Factor (Using MOC Net) 0
- 21. 6 36.4
- 22. O'nit Capacity Factor (Using DER Net) 0 21.4 36.1
- 23. O'nit Forced Outage Rate 90.8
- 61. 3 45.0
- 24.
Shutdowns Scheduled OVer Next 6 Months (Type, Date, and Duration o£ Each) :
NONE
- 25. If Shut r::own At End o£ Report l?eriodr Estimated Date of Startup: __
N_f_A _____________ _
- 26.
1Jnits In Test Status(Prior to Camercial Cperation):
8-l-7.R2 Pg.'~
- .. 3 of 2 3 Forecast 9/30/76 11/1/76 12/20/76 Achieved 12/11/76 12/25/76 6/20/77
- 00.
DATE 79-329 12/1/79 79-350 12/1/79 79-352 12/5/79 79-354 12/27/79 79-356 12/27/79 79-358 12/27/79 79-360 12/29 /79 79-362 12/30/79 79-364 12/30/79 79-365 12/30/79 79-366 12/31/79 1
F: Forced S:
Scheduled Page
. 4 of 23 9-1-7.Rl TYP~
F F
F F
F F
F F
F F
F 2
UNIT SlllmXMNS l\\ND PCl'JER mrix:TIONS REPORI' MJlml December 1979 DOCKET NO. : _5_0_-_2_1_2 _____ _
- UNIT 'NAME:
Salem Ill MEl'll)D OF OOMTIOO
~
SllUITIOO (llXJRS) ram REACTOR 101.5 D
4B 101. 5 D
4B 537.8 D
4B 7.2 D
4B 0.5 D
4B 30.3 D
4B 18.8 D
4B 5.8 D
4B 6.0 D
4B 17.6 D
4B 7.6 D
3 Reason:
A-B:]ui[IIEilt Faiiure(Explain)
&-Maintenance or 'l'est C-Refueling 0-Regulatory Restriction LICENSE EVENr REroRI' '
E-Qperator Training & License Examination F-Jl.dministrative
~rational Errur(Explain)
II-Other (Explain)
SYSTEM CXM'OOENl' CODE4 CODES.
SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz SH zzzzzz cc PUMPXX DATE:
January 11, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507 CAUSE 1\\ND CDRRECI'IVE ACTION TO PRE.VEN!' REX:URRENCE Safety Environmental Requirements NRC Tech.
Speci;>._/~eg. _Guides NRC Required Mod/Add. to Plant.
NRC Tech. Specs./Reg. Guides Switchgear NRC Tech. Specs. /Reg. Guides Required inspection or test NRC Tech. Specs. /Reg. Guides.
Required inspection or test NRC Tech. Specs./Reg. Guides Steam Generator High High Level 3
4 5
Mathcxl:
1-Manual 2-Manual Scram.
3-Automatic Scram.
4-0ther (Explain)
A. Load Reduction B. Continuation of Previous Outage Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG-0161)
Exhibit 1-Saim Source
'MAJOR PLANT MODIFICA'r*s REPORT MONTH December ~79 50-2 72 DOCKEl..NO. :
UNIT "'1E:
Salem tll
~~~~--'"'~~~~~~
DATE: January 11, 1980 COMPLETED BY:
L. K. Miller
~~~~~~~~~~~
TELEPHONE:
609-365-7000 X507
~~~~---~~~~~~
- DCR NO.
PRINCIPLE SYSTEM SUBJECT lED-0068 Chemical Treatment Add filters, valves and gauges to Panel 380 (Chemical Tr.eatment Panel) lEC-0452 Containment Various Install upgraded solenoid valves lEC-0453 Containment Pressure-Vacuum Relief Install protective basket on 1VC15 lEC-0470 Condenser Air Removal Install loop seals on vacuum pump drains lEC-0471 Control Air lEC-0484 Main Turbine Lube Oil 1ET-0495A eves 1EC~0561 Main Turbine Lube Oil lEC-0568 Fire Protection
'lEC-0623 Main Stearn lET-0681 S.G. Instruments lEC-0699 Containment Sump lMD-0103 Containment TV lPD-0087 DM Water
.lSC-0009 Sampling System lST-0178 RHR Pumps lST-0179 Charging Pumps lSS-0011 Fire Protection lEC-0465 Condenser Retubing
- DESIGN CHANGE REQUEST 8-1-7.Rl Replace 1CA129 with 2" nipple Cut ',',Bow-Tie" grooves in #1, #9 &
- 10 bearings Retest for DCP 1 s lEC-0386, 0387 &
0514 (1CV3, 4,
& 5 modification)
Install MTLO filter Install additional hose reel in Aux.
Building, El. 100' Remove overload jumpers on MS-167 1 s hyraulic operators NDE testing of instrument lines Revise setpoint of level transmitters Install ventilation to TV cameras Install remote DM level indicators Install leak rate test connections at 1SS107 and 110 Temporary DM supply for C.C. outage Temporary DM supply for C.C. outage Install new cardox P.B. station for vital bus area co2 Remove and install control air piping
, )
Page 5 of 23
DOCKET NO.:
50-272 MAJOR PLANT MODIFICAT.S RF.PORT MONTH December 1979 UNIT~
Salem tf l
- DCR NO.
lED-0068 lEC-0452 lEC-0453 lEC-0465 lEC-0470 lEC-04 71 lEC-0484 1ET-0495A lEC-0561 lEC-0568 lEC-0623 lET-0681 10CFRS0. 5 9.
DATE:
January 11, 1980 COMPLETED BY:
L. K. Miller
~~~~~~~~~~~~
TELEPHONE:
609-365-7000 X507
~~~~~~~~~~~~
SAFETY EVALUATION This is not a safety related change and does not affect safety related equipment.
This change replaces existing equipment with equipment qualified to latest seismic and environmental standards.
The function of circuits has not been altered.
The existance of detailed reliability data on new equipment en-hances the reliability of the circuits. Material, installation physically similar and functionally identical.
The subject change does not affect any presently performed safety analysis nor does it create any new safety hazards.
The bases of the Tecnical Specifications are not affected.
This design change does not affect any presently performed safety analysis nor does it create any new safety hazards.
The bases ot the Tech. Specs.
are not affected.
This change affects only non-safety related equipment and does not involve any previously conducted acc+/-dent analyses, nor does it create conditions which would require additional safety analysis.
It also does not affect the bases of the Technical Specif*ications.
The subject design change request is non-safety related and does not impair any safety related system function or reliability function.
The changes involved are non-nuclear and seismic class 3.
This design change does not affect any presently performed safety analysis nor does it create any new hazards.
The bases of the Technical Specifi~
cations are not affected.
Operation modes will be simulated in this test, therefore, everything will be within the ~design bases and an unreviewed safety question is not involved.
This design change will not require a change to the Tech. Specs or FSAR.
The additional filter equipment nor the sur~ounding equipment is safety related.
This modification will improve the main turbine lube oil clean-liness and increase reliability.
This installation of the hose station. required by this DCR has been previ-ously reviewed and it has been found that it does not present and unreviewed safety question.
No additional fire hazard is introduced by the addition of this hose station.
It.improves the plant safety features against fire.
The modification does not change the functional operation of the system nor degrade its performance.
The :retest will establish the specification requirements for the instrument process lines involved.
~- *.
(
Page 6 of 23
MhJOR PLANT RF.PORT MONTH
- DCR NO.
lEC-0699 lMD-0103 lPD-0087 lSC-0009 lST-0178 lST-0179 lSS-0011 DOCKET NO.:
50-272 MODIFICATI-S UNIT *=
Salem Ill December 1979 DATE:
Januar:t: 11, 1980 COMPLETED BY:
L. K. Miller TELEPHONE:
609-365-7000 X507 10CFRS0. 5 9.
SAFETY EVALUATION Implementation of this DCR will insure a safer shutdown of the NSSS equip-ment following an accident involving a breach in the primary coolant system by providing anti-vortex baffles in the reactor bldg. sump. pit on the suction side of the residual heat removal pumps.
The subject change doe-s:.:not affect any presently performed safety analysis nor does it create any new safety hazards.
The bases of the Technical Specifications are not affected.
This change is not safety related and does not affect safety related equipment.
This design change is not safety related and does not in any way affect any safety related systems or the safe shutdown of the unit.
The use of DM water as cooling to the RHR pump seal heat exchangers in lieu of component cooling will not pose an unreviewed safety question as this test will be conducted with the plant in a cold shutdown condition.
The use of DM water as cooling to the charging and safety injection pump seal heat exchangers in lieu of component cooling will not pose an un-reviewed safety question as this test will be conducted with the plant in a cold shutdown condition.
Not safety related and does not affect any safety related system.
Page 7 of 23
DOCKET. NO.:
50-272 MA*~ENA~CE NAf.At SliHM.. ::\\..."l:{Y OF SP...FETY RELATED UNIT Salem tll DE?.. 'ill':'.:1E NT Performance DATE:
January 11, 1980 COMPLETED BY:
L. K. Miller REPORT MONTH December 1979 TELEPHONE:
609-365-7000 X507 WOR...I{ ORDER I
EQUIPMENT I
FAILURE DESCRIPTION CORRECTIVE ACTION NO.
I 911838 Instrument, 1N31 Investigate & repair. cause Replaced detect01::, pre-amplifier,
- source range of excessive noise
& _rebuilt high voltage triaxial*
plug at drawer 911838 Instrument, 1N35 Investigate & repair cause Replaced detector, high voltage source range (NIS) of excessive noise.
power supply & c.v. triaxial plug at drawer 915218 Damper, containment Control air supply solenoid Replaced solenoid valve pressure relief SV930 is sticking 915222 Instrument, 1FT510 Module 1BS510A found out of Replaced signal isolator module (11 S.G. feed water spec. during functional 1FM510A flow channel) test.
Problem resulted from defective signal isol-a tor module 1FM510A 915224 Instrument, 1FT128 There is a 36 GPM charging Calibrated flow transmitter (Charging pump dis-seal flow with 0 GPM in-charge flow trans.
dicated.
Transmitter out of calibration.
915292 Instrument, 1N41 Amplifier module NM306 out Adjusted gain of module NM306 power range, (NIS) of calibration 915296 Instrument 1N41 Amplifier module NM301 out Iso*lated and cleared short power range, (NIS) of spec.
Cables from drawer to reactivity com-puter were shorted together 915297 Valve operator, Control air supply regu-Replaced control air suppiy 13MS171 lator has blown regulator regulator 915306 Instrument, 1N43 Upper, lower flux signals Moved reactivity computer input power range (NIS) loading.
Reactivity com-signals to proper outputs of the put er inp:i;i.t*:: signals are isolation amplifier.
Rescaled not isolated causing load-amplifiers A-1, A-3 & £!.I Record-
- ing.
ers 915322 Instrument,* 1N31 Cable plug on high voltage Replaced connector source range (NIS) power supply has broken tenter iack Page 8 of 23
~
DOCKET NO.:
50-272 SU~il1ARY OF SAFETY RELATED MA.TENA~CE UNIT NAl'e Salem Ill DEPARTMENT Performance REPORT MONTH December 1979 DATE:
COMPLETED BY:
January 11, 1980 L. K. Miller TELEPHONE:
609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.
915334 Inst., 1N41 power Cable connector on high Rebuilt high *voltage callile plug range (NIS) voltage from picoammeter is introducing noise into the reactivity computer*
915150 Inst.,. 1N41 power Reset LH recorder for 100%
Set target band for +2.5 at.100%
range (NIS) operator, found faulty power, replaced relay axial flux detector Hi-Lo selector relay 915614 Inst., reactor 5 thermocouples have leak-Tightened *connections, stopped inc ore thermocouplEs a~e at connection leakage 915615 Inst., 1N42 power Recorder 1XA5904RB will not Replaced recorder 1XA5904RB range (NIS) calibrate 915637 Inst., 1N44 power Amplifier NM301 out of spec Calibrated amplifier NM301 range (NIS) 915731 Inst., 1N43 power Red pen on NR43 recorder Adjusted zero on the red pen range (NIS) out of adjustment 915840 Valve operator, Valve operator leaks air, Replaced failed diaphragm, 13MS171 operator diaphragm failed stroked valve 917429 Heat trace, 1055 Will not turn off.
Thermo-Adjusted thermostat vital stat contact out of adjust-ment.
917440 Heat trace, T221P Thermostat contacts stuck Adjusted thermostat vital cl.osed, contacts out of adjustment.
917545 Inst., 2D5 Rod Indication out of step with Rod position indication recali-Position Indicatior group brated 917546 Inst., 2SA1 Rod Indication out of step witb Rod positon indication recali.,-
Position Indicatio 11 group brated Page 9 of 23
- .1
DOCKET. NO.:
50-272 MA.TENA~CE NAf.1-
SUMMARY
OF SAFETY RELATED UNIT Salem ill DEPARTMENT Performance DATE:
January 11, 1980 December 1979 COMPLETED BY:
L. K. Miller REPORT MONTH TELEPHONE:
609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.
917556 Inst., 1FT128 Indicator on console about Calibrated fiow transmitter (Charging Pump dis 50 GPM low.
Flow trans-charge flow trans) mitter may be out of cal.
919363 Valve Operator, Control switches to manual Reset and cleaned relays.
1CV179 when flow setpoints is in-creased in the auto mode.
Dirty relays in servo set-point station.
919371 Inst., FA3176C-l In high speed, indicated Reset high speed setpoint to 25%
flow is 1900 GPM.
Set-points out of adjustment 919377 Damper op*erators, Failed to close.
Damper Freed damper, lubricated, 1CAA3, 1CAA4 b:i,.nding limit switch out adjusted limit switch
__ of ::adjustment 919378 Valve, airlock sea Adjust regulator to,
Adjusted regulato.'F air supply regula~* required setpoint range.
tor 919394 Inst., FA3165Z-l
- Check, calibrate. Does not Blewdown and calibrated (12 Cont. Fan Coil control service water flow Unit Inlet Flow Transmitter) 919394 Inst., FA3540Z-l Check, calibrate. Does not Replaced oscillator ampl~fier, (12 Cont. Fan Cciil control service water flow...
calibrated.
Unit Outlet Flow Oscillator amp. defective Transmitter) 919400.
Inst., LA5744-l &
Calibrate.
Calibrated LA1688-l(Aux. FW Storage Tank Level Transmitters) 919406 Inst. 1Rl5 Radi-Detector fat.l.lty Replaced detector at ion Monitor Channel (Condenser Air Ejector) 1 Page 10 of 23 n
~,
I DOCKET NO.:
50-272 su~~y OF SAFETY RELATED MA.TENANCE DEPAR'l'!<i.ENT Performance UNIT NA DATE:
Salem 111 January 11, 1980 REPORT MONTH December 1979 COMPLETED BY:
L. K. Miller TELEPHONE:
609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.
919456 Inst., lRlB Radi-Detector Faulty.
Replaced detector, calibrated ation Monitor channel Channel (Control Room Intake Duct) 919524 Inst., Air partic...: Belt broken Replaced broken belt ulate detector radiation monitor 929204 Damper operator, Control air supply solenoid Rep1aced solenoid valve coil 1SWV7 valve SV562 coil failed 929230 Inst., 1N31 source High voltage meter indica-Replaced meter range (NIS) tion drifts 929246 Inst., 1PC457E &
__ Recalibrate Recalibrated 1PC474B (Pressur-izer Pzr:Comparato.r>
929247 Inst., 1TE440B Failed open Replaced (14 Rx Coolant Loop Temperator Element) 929248 Inst.~ 1N41 power Amplifiers NM301 & NM302 Calibrated NM301 & NM302 range (NIS) out of calibration 929309 Inst., 1FT522 (12 Module 1FM522C out of cal.
Calibrated module 1FM522C S.G. Stm. Flow Transmitter) 929335 Inst., 1PT948A Pressure comparator lPC~
Calibrated 1PC948A/D and (Cont. Pressure 948A/D out of calibration.
recorder 1PR948A Trans. Protection.
Pressure recorder 1PR948A Channel IV) out of specification.
929338 Inst., 1FT531 (13 Flow comparator 1FC531A/B Calibrated flow comparator S.G. FW Flow T:r:ans.
Channel II)
Page 11 of 2~
~ -
~,
i
DOCKET NO.:
50-272 SUM..7-1.ARY OF SAFETY RELATED MA.TENA~CE DEPARTMENT Performance UNIT NAM--~S-al_e_m~#-1~--~~~~--~
REPORT MONTH December 1979 DATE:
J~nuary 11, 1980 COMPLETED.3Y:
L. K. Miller
~--------------~~-----
TELEPHONE:
609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACT.ION NO.
929820 Ins.t., 1Rl8 Radi-Failed low.
Faulty detec-Solder repaired connector ation Monitoring tor wire connections Channel.
929849 Valve Operator, Air operator bolts loose.
Tightened bolts lPRl 929233 Inst., 1N44 power Test point TP442-l in rack Reset range (NIS) 15 out of spec. high 919506 Valve Operator, Gauge on regulator has Replaced broken gauge glass, 1CV179 broken glass, valve oscil-Replaced faulty relays.
!ates badly due to faulty relays 905424 Inst. 1N31 source. _Extremely sensitive to Rebuilt all cable plugs and range (NIS) noise.generated by welding jacks etc.
Possible deficiencies in cable plugs and. jacks Page 12 of 23 n
,_ __ ______!""r__'T""'ll"1 ___
DOCKET NO.:
50-272 MA.TEN AN CE NAL41 SU~Y OF SAFETY RELATED UNIT Salem /fl DATE:
January 11, 1980 DEPARTMENT Maintenance REPORT MONTH December 1979 COMPLETED BY:
L. K. Miller TELEPHONE:
609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.
OD-5556 Valve, 12CC14 Relief valve relieving Disassembled, cleaned terminals while RHR heat exchanger reassembled.
Popping pressure is out of service.. Dirt setpoint *tested.
in internals.
900223 Valve, 1VC4 Butterfly disc pin sheared, Valve removed from system, sent valve linear damaged and to vendor for factory repairs.
and dislodged.
900228 Valve, 1VC5 Valve to be repaired/mod-Valve removed & shipped to vendor ified by vendor.
for factory repairs/mod1fication~
Modified spare valve installed.
900852 Heat Exchanger, Inspect & maching as neces-Manway inspected, machined and 14 Stm. Generator
.sary inboard manway cover reinstalled 901610 Valve, 11MS12 Disassemble, inspect, lap, Work completed reassemble 901609 Valve, llMSll Disassemble, inspect, lap, Work completed reassemble 901611 Valve, 11MS13 Disassemble, inspect, lap,
_Work completed reassemble 901612 Valve, 11MS14 Disassemble, inspect, lap, Work completed reassemble 901613 Valve, 11MS15 Disassemble, inspect, lap, Work completed reassemble 901614 Valve, 12MS11 Disassemble, inspect, lap, Work completed reassemble 901615 Valve, 12MST2 Disassemble, inspect, lap, Work completed reassemble Page 13 of 23
_n
- . __ ~,..,..,
DOCKET NO * :
50-2 72 SU~-~y OF SAFETY RELATED MA.ENA~CE UNIT N~--S-a_l_e_m~#-1-----------------
DEPARTMENT Maintenance REPORT MONTH December 1979 DATE:
January 11, 1980 COM.FLETED BY:
L. K. Miller
~--~~~~~~~~--~--~--
609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.
901616 Valve, 12MS13 Disassemble, inspect, lap, Work comple.ted reassemble 9016f7 Valve, 12MS14 Disassemble, inspect, lap, work completed reassemble 901618 Valve, 12MS15 Disassemble, inspect, lap, Work completed reassemble 901624 Valve, 14MS11 Disassemble, inspect, lap, Work completed reassemble 901625 Valve, 14MS12 Disassemble, inspect, lap, Work completed reassemble 901626 Valve, 14MS13
.. - Disassemble, inspect, lap~*
Work completed reassemble 901627 Valve, 14MS14 Disassemble, inspect, lap, Work completed*
reassemble 901628 Valve, 14MS15 Disassemble, inspect, lap, Work completed
- reassemb.le 902124 Valve, 15SW25 Valve stem is off bushing Disassembled, repaired, re-Will not move.
assembled 902801 Valve, 14GB4 Failed leak rate testing.
Installed newgaskets, repacked Repair.
valve, machined seat & disc.
Valve was reassembled and passed leak rate testing.
905.585 Valve, 12SW124 Repair pin hole leak at Repaired pin hole leak welded joint to nipple.
Pipe metal erroded, corrode a.
906019 Heat Kxch., 12 S.G. Machine man way pad, gasket Machine gasket surfaces surface pitted.
Page 14 of 23
~,
DOCKET NO.: 50'-272 SUMi.'1.A.HY OF SP.FETY RELATED MA~~TEN.Ai~CE UNIT NA_s_a_l_e_m_ll_l ________ _
Maintenance REPORT MONTH December 1979 DATE:
January 11, 1980 COMPLETED. BY: L. K. Miller
~~~~~~~~~~~~~~~
TELEPHONE: 609-365-7000 X507 WOR..T<
ORDE...~
EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.
906022 Heat Exch., 11 Stm. Machine inboard manway Machined manway covers Generator cover as per West. letter 906-023 Heat Exhh~, 11 Stm. Machine.outboard manway Machined Manway *covers.. -.
Generator cover as per West. letter 906024 Heat Exch., 12 Stm. Machine inboard manway Machined Manway covers.
Generator cover as per West. letter 906025 Heat Exch., 12 Stm. Machine outboard manway Machined Manway covers..
Generator cover as per West. letter 906026 Heat Exch., 13 Stm. Machine inboard manway Machined Manway covers.
Generator*
cover as p~r West. letter 906028 Heat Exch., 14 Stm. Machine outboard manway Machined Manway covers.
Generator cover as*per West. letter 906029 Heat Exch., 11 Stm. Machine inboard secondary Machined manway pad.
Generator manway pad as per West; letter.
906104 Heat Exch., 13 Stm. Machine inboard manway pad Machined manway pad Generator 906115 Heat Exch., 13 Stm. Machine outboard manway pad Machined manway pad
- Generator 906119 Heat Exch., 11 Stm. Machine outboard manway pad Machined manway pad Generator 906120 Heat Exch., 12 Stm. Machine outboard manway pad Machined manway pad Generator 906121 Heat Exch., 14 Stm. Machine outboard manway pad Machined manway pad Generator Page 15 of 23
DOCKET NO.:
50-272 MA.TENA~CE NA Salem Ill UNIT SU~Y OF SAFETY RELATED DATE: January 11, 1980 DEPARTMENT Maintenance L. K. Miller COMPLETED BY:
REPORT MONTH December 1979 609-365-7000 X507 TELEPHONE:
WOR..1< ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.
906127 Pump, 11 Charging Disassemble, inspect &
Replaced rotating assembly.
Safety Injection repair as necessary 913705 Pump, 22 Chiller Expansion joint leaking Replaced exp ans.ion joint spool Recirculating badly, failed piece 913820 Heat trace, 221T Thermostat does not turn Adjusted contacts, thermostat Primary off circuit.
Contacts out functionally tested.
of adjustment 913846 Heat trace, 212B Contacts stuck.
Switch Adjusted switch movement Vital movement touching conduit union in controller 914293 Filter, 11. Cont.
Roughing filters dirty, Replaced filters Fan Coil Unit replace
~
915346 Heat trace, Cont.
Temporaty heat trace sen-Temporary heat trac.ed sensing Vent. Stack Flow ing line Trans. Sensing Line 916084 Valve, llSJ40 Repack, packing failed Repacked 12SJ40 0
- L>
917389 Valve, 14MS175 Handwheel missing Reptaced hand wheel 917405 Valve, 13SW236 Handwheel damaged Replaced handwheel 917423 Strainer, ll Ser-Repack, packing failed Repacked vice water pump 917506 Pump, 11 Safety Inboard:, outboard seals Replaced spacers, replaced Injection leaking.
Pump has a rub inboard & outboard seals due to cracked spacers.
917537 Valve, 13MS171 Leaks through seat.
Lapped seat & stem assembly.
Replaced all gaskets Page 16 of 23
~,
DOCKET NO.: 50-272
SUMMARY
OF SAFETY RELATED ATENANCE UNIT N~~S-a-1-ern~#-l~~~~~~~~-
Maintenance REPORT MONTH December 1979 DATE: January 11, 1980 COMPLETED BY: L. K. Miller
~~~~~~~~~~~~~~
TELEPHONE: 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.
919402 Orifice, 11 Main The 3/32" flow orifice µp-Sealed flange leak with steam piping 3/32" stream of 11MS200 has hole furrninite piping flow orifice 919407 Valve, 11MS6 Repack, packing failed Repacked 919478 Breaker, 2C 4KV No open/closed indication Replaced adaptor, tested cir-2C4D on console.
Console mount~ cuit.
ing box adapter in 28 VDC indication circuit failed 919488 Valve, 1SJ149 Rep"iace, packing failed Repacked 919490 Inst., LD7755-l Level switch operating irn-Cleaned and oiled.
(14 Residual Heat properly.
Operating device Removal Sump Punip dfrty, sticking
Charging preventative maintenance 919504 Bus, lADC 119
- j.
Apparent ground on the lEP Repaired broken insulator Breaker lA 125 VDC 480 VAC Pzr. Heater Breaker Eroken insulator on lA Regulator Supply EP Htr.
Bus. Bkr.
919508 Pump, 11 Boric Aci.B: Oil seals leak, Internals Replaced shaft bearings, - oil damaged seals, shaft & mechanism seals 919535 Valve, 15SW25
- Does not close by use of Replaced defective parts handwheel.
Valve race bearings, hand wheel all en screws, stern o1'.ring are defective.
919561 Inst., FD7668-1(14 Intermittent annunciator Replaced flow switch.
Control Rod Drive alarm.
Faulty flow switch.
Vent Fan Lo-Air Flow Switch)
Page 17 of 23
~,____ __ _
DOCKET NO.:
50-272 SUM..?-1.AHY OF SAFETY RELATED MAITENANCE UNIT NAM--S-a_l_e_m_ll_l ________ _
DEPARTMENT Maintenance REPORT MONTH December 1979 DATE:
January 11, 1980 COMPLE':'ED BY:
L. K. Miller
~~~~~~~~~~~~~~--
TELEPHONE:
609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.
919562 Pump, 11 Distil- *'*
Pump suction flange is Replaced gasket.and motor late leaking, gasket failed.
919562 Motor, 11 Dis-Motor stator oil relief Replaced motor.stator till ate pump valve has water coming out.
Motor stator defective 919605 Valve, 13GB3 Repack, packing failed Repacked 919625 Valve, 13RC21 Repack, packing failed Repacked 919629 Valve, 13RC27 Repack, packing failed Repacked I
919662 Valve, 12MS174 Repack, packing failed Repacked 919665 Valve, 12MS7 Repack, packing failed Repacked 919682 Valve, 12MS199 Repack, packing failed Repacked 919708 Airlock, 100' EL, Air ieakage, Latch me ch-Reversed inner, outer door seals Personnel an ism out of adjustment Realigned latch mechanism 919713
_Pump, 13 Component AXial movement.
Defective Replaced bearing housing, oiled Cooling bearing housing, oil seals seals, bearings
& bearings 919740 Valve, 14RC25 Repack, packing failed Repacked 919755 Inst., 1FE499B-l Flange leaks, gaskets Replaced flange gaskets (12 Rx Coolant failed Loop Flow Orifice) 919757 Valve, 11RC24 Repack, packing failed Repacked 919758 Valve, *11RC28 Repack, packing failed Repacked P
18 of 2 3
_age
I DOCKET NO. :
50-272 sm~~Y OF SAFETY RELATED MAITENA~CE UNIT N~~S-a_l_e_m_li_~l~~~~~~~~~
DEP.i\\.R'l'MENT Maintenance REPORT MONTH December 1979 DATE: January 11, 1980 C0!-1..PLETED BY: L. K. Miller TELEPHONE:
609-365-7000 X507 WOR...."t{ ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.
919765 Valve, 13MS7 Body to bonnet leak, gasket Replaced gasket failed 919767 Valve, 1PS2 Stem broken Replaced valve spindle &
repacked 919795 Airlock, 100' El.'
Door hinge pin damaged Replaced latch pin, tightened Cont. Personnel latch turnbuckle, tightened latch hinge 920188 Valve, 14SW223 Valve fluctuates.
Sticky Adjusted actuator 1.arm actuator* arm binding 929811 Pump, 11 *Boric Oil Seal Leak.
Oil Seal Replace oil seal*
Acid Tank failed 4***
929821 Valve Operator, Motor wired backwards, Rewired motor correctly 12CW126 motor overload, breaker tripped 906098 Piping, Service Pipe leaks, salt water Weld repaired leaks, built up Water Spool Piece induced corrosion & silt wall thickness with weld metal.
errosion.
Have reduce Installed Bel.zona molecular pipe wall thickness lining.
914341 Valve, 1PR9 Re.pack, packing failed Repacked 917568 Valve, 13RC16 Repack, packing failed Repacked 917578 Valve, 14RC28 Repack, packing failed Repacked 917579 Valve, 14RC24 Repack, packing failed Repacked 919589 Fan, 11 FHB Drive belt off Re~laced drive belts Exhaust
~?
Page 19 of 23
~
~ - _,
DOCKET NO.:
50-272 SU1-L71ARY OF SAFETY RELATED MA..
ENA~CE UNIT NAl..~~S-a_l_e_m~#-1~~~~~~~~-
l I
Maintenance REPORT MONTH Decemb;er 1979 DATE: January 11, 1980 COMPLETED BY:
L. K. Miller
~~~~~~~~~~~~~~
WORK ORDER EQUIPMENT NO.
919602 Valve, 14RC25 919603.
Valve, 12SJ54 919614 I
Valve, 11RC12 919619 Valve, 11RC16 919623 Valve, 13RC11 919624 Valve, 13RC12
. 919628 Valve, 13RC19 919630 Valve, 1RC7 919631 Valve, lPSll 919646 Valve, 11MS130 919661 Valve, 12MS173 919670 Valve, 14MS173 919683 Valve, 12MS130 919689 Valve, 14MS131 919787 Valve, 14MS8 919815 Valve, 1SJ19 Page 20 of 23 TELEPHONE:
609-365-7000 X507 FAILURE DESCRIPTION Repack, packing failed Repac.k, packing failed Repack, packing failed Repack, packing failed Repack, packing failed Repack, packing failed Repack, packing failed Repack, packing failed Repack, packing failed Repack, packing failed Repack, packing failed Repack, packing failed Repack, packing failed*
Repack, packing failed Repack, packing failed Repack, packing failed CORRECTIVE ACTION Repacked Repacked Repacked Repacked Repacked Repacked*
Repacked Repacked Repacked Re.packed Repacked Repacked Repacked Repacked Repacked Repacked
12/1 thru 12/22 12/23 thru 12/24 12/25 thru 12/27 12/28 12/29 12/30 SALEM UNIT #1 OPERATING
SUMMARY
DECEMBER 1979 Cycle 2 initial criticality occured at 1640 on 12/1/79.
Low power physics testing commenced on 12/1 and ran through to 12/12.
The unit was shutdown at 1726 on 12/12 to modify piping 'Supports on the emergency diesel generator auxiliary support systems.
Startup recommenced on 12/22.
Reactor critical at 0020.
Low power physics testing was completed by 0700 on 12/24.
For the remainder of the day plant was less than 1% power.
Plant power was increased to 5% by 1240 on 12/26 and held at less than or equal to 5% during which time the balancing of the turbine generator was checked.
Plant power increase from 5% to 20% power was commenced at 1140 on 12/27.
Power was held at 20% to stabilize turbine generator temper-atures in preparation for the turbine trip test.
Unit power was reduced to 7%, the trip test performed and unit power returned to 15% by 2400 on 12/27.
Unit power increased to 20% by 0200 and held at 20% for flux mapping.
Unit power held at 20% until 0425 when load was decreased to 7% in preparation for the.turbine overspeed trip test.
At 0530, the reactor tripped due to a turbine trip.
Reactor critical at 1714 and plant power increased to 5% by 2400.
Plant power being increased.
At 0430, power was decreased to less than 5% to allow repairs to be made to the turbine generator exciter cooler.
Load increase commenced at 1120 and power stabilized at 30% by 2100.for test data collection.
Load increase commenced at 2300.
Page 21 of 23
12/31 Load increase in progress.
Reactor trip occured at 0536 following the loss of #11 main feedwater pump.
Reactor critical at 1135 and load increase to 40% commenced.
Unit load stabilized at 40% by 2040.
Page 22 of 23
e REFUELING INFORMATION December 1979
. DOCKET NO.: 50-272
~---------~
UNIT: Salem # 1 DATE:January 11, 1980 COMPLETED BY: L. K. Miller TELEl?HONE:609-365-7000 X507
- l.
Refueling information has changed from last month:
YES NO x
- 2.
Scheduled date of next refueling:
September 20, 1980
- 3.
Scheduled date for restart* following refueling: November 16, 1980
- 4.
A.
Will Technical Specification-changes or other license amendments be required?
YES NO ----
. NOT DETERMINED TO-DATE December 1979
~~-
- B-. -- *Has the-reload fueJ.. design.. been* reviewed. by the Statign
__ Operati_ng Review Committee?
YES NO x
If no, when is it scheduled?
July 1980
- 5.
Scheduled date(s) for submitting proposed. licensing action:
August 1980 (If Required)
- 6.
Important licensing considerations associated with refueling:
NONE
- 7.
Number of Fuel Assemblies:
A.
In-Core 193 B.
In Spent Fuel Storage*
. 40
- 8.
Present licensed spent fuel storage capacity:
264
~
Future spent fuel storage capacity:
1,170
~
- 9.
Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:
Page 23 of 23 8-l-7.R4 September 1982