ML18081A914

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Monthly Operating Rept for Dec 1979
ML18081A914
Person / Time
Site: Salem PSEG icon.png
Issue date: 01/11/1980
From: Miller L
Public Service Enterprise Group
To:
Shared Package
ML18081A913 List:
References
NUDOCS 8001170337
Download: ML18081A914 (22)
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Text

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 50-272 UNIT Salem #1 DATE January 11, 1980

. CO.'-'IPLETED BY L. K. Miller TELEPHONE 609-365-7000 X507 MONIH December 1979 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) (MWE-NET)

  • O 0 1 17 2 0 18 0 3 0 L9 0 0 0 4 20 5 0 21 0 6 0 22 o*

7 0 23 0 8 0 24 0-9 0 25 0 10 0 26 0 11 0 27 0 1.2 0 28 130' 13 0 29 0 14 0 30 90

15. 0 31 149 16 0 Pg. 2 of 23 8.1-7.PJ. 8001170.33 7

.. rx:x:KET NJ.: _ _50-272

~  : _ _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_..,.....,..._ _ _ _ _ _ __ Notes:
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_ _ _ __
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 744 8,760 21,961

u. Hours In Rey;:orting Period
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):

Forecast Achieved 9/30/76 12/11/76 11/1/76 12/25/76 8-l-7.R2 Pg.'~  :**. 3 of 2 3 12/20/76 6/20/77

UNIT SlllmXMNS l\ND PCl'JER mrix:TIONS DOCKET NO. : _5_0_-_2_1_2_ _ _ _ __

REPORI' MJlml December 1979 *UNIT 'NAME: Salem Ill DATE: January 11, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507 MEl'll)D OF OOMTIOO SllUITIOO LICENSE SYSTEM CXM'OOENl' CAUSE 1\ND CDRRECI'IVE

00. DATE TYP~ (llXJRS) ~ ram EVENr CODE4 CODES. ACTION TO REACTOR PRE.VEN!' REX:URRENCE REroRI' '79-329 12/1/79 F 101.5 D 4B - - - SH zzzzzz Safety Environmental Requirements79-350 12/1/79 F 101. 5 D 4B - - - SH zzzzzz NRC Tech. Speci;>._/~eg. _Guides79-352 12/5/79 F 537.8 D 4B - - - SH zzzzzz NRC Required Mod/Add. to Plant . .79-354 12/27/79 F 7.2 D 4B - - - SH zzzzzz NRC Tech. Specs./Reg. Guides79-356 12/27/79 F 0.5 D 4B - - *- SH zzzzzz Switchgear 79-358 12/27/79 F 30.3 D 4B - - - SH zzzzzz NRC Tech. Specs. /Reg. Guides79-360 12/29 /79 F 18.8 D 4B - - - SH zzzzzz Required inspection or test 79-362 12/30/79 F 5.8 D 4B SH zzzzzz NRC Tech. Specs. /Reg. Guides.79-364 12/30/79 F 6.0 D 4B - - - SH zzzzzz Required inspection or test 79-365 12/30/79 F 17.6 D 4B - - - SH zzzzzz NRC Tech. Specs./Reg. Guides79-366 12/31/79 F 7.6 D 3 - - - cc PUMPXX Steam Generator High High Level 1 2 3 4 5 F: Forced Reason: Mathcxl: Exhibit G - Instructions Exhibit 1-Saim 1-Manual for Preparation of Data Source S: Scheduled A-B:]ui[IIEilt Faiiure(Explain)

&-Maintenance or 'l'est 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File 0-Regulatory Restriction 4-0ther (Explain) (NUREG-0161)

E-Qperator Training & License Examination A. Load Reduction F-Jl.dministrative

~rational Errur(Explain) B. Continuation of II-Other (Explain) Previous Outage Page . 4 of 23 9-1-7.Rl

50-2 72 DOCKEl..NO . :

'MAJOR PLANT MODIFICA'r*s UNIT "'1E: Salem tll REPORT MONTH December ~79 ~~~~--'"'~~~~~~

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 Replace 1CA129 with 2" nipple lEC-0484 Main Turbine Lube Oil Cut ',',Bow-Tie" grooves in #1, #9 &
  1. 10 bearings 1ET-0495A eves Retest for DCP 1 s lEC-0386, 0387 &

0514 (1CV3, 4, & 5 modification) 1EC~0561 Main Turbine Lube Oil Install MTLO filter lEC-0568 Fire Protection Install additional hose reel in Aux.

Building, El. 100'

'lEC-0623 Main Stearn Remove overload jumpers on MS-167 1 s hyraulic operators lET-0681 S.G. Instruments NDE testing of instrument lines lEC-0699 Containment Sump Revise setpoint of level transmitters lMD-0103 Containment TV Install ventilation to TV cameras lPD-0087 DM Water Install remote DM level indicators

.lSC-0009 Sampling System Install leak rate test connections at 1SS107 and 110 lST-0178 RHR Pumps Temporary DM supply for C.C. outage lST-0179 Charging Pumps Temporary DM supply for C.C. outage lSS-0011 Fire Protection Install new cardox P.B. station for vital bus area co2 lEC-0465 Condenser Retubing Remove and install control air piping

  • DESIGN CHANGE REQUEST

, )

Page 5 of 23 8-1-7.Rl

DOCKET NO.: 50-272 MAJOR PLANT MODIFICAT.S UNIT~ : Salem tf l RF.PORT MONTH December 1979 DATE: January 11, 1980 COMPLETED BY: L. K. Miller

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

TELEPHONE: 609-365-7000 X507

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

  • DCR NO. 10CFRS0. 5 9. SAFETY EVALUATION lED-0068 This is not a safety related change and does not affect safety related equipment.

lEC-0452 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.

lEC-0453 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.

lEC-0465 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.

lEC-0470 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.

lEC-04 71 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.

lEC-0484 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.

1ET-0495A Operation modes will be simulated in this test, therefore, everything will be within the ~design bases and an unreviewed safety question is not involved.

lEC-0561 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.

lEC-0568 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.

lEC-0623 The modification does not change the functional operation of the system nor degrade its performance.

lET-0681 The :retest will establish the specification requirements for the instrument process lines involved.

' ~- *.

(

Page 6 of 23

  • =

DOCKET NO.: 50-272 MhJOR PLANT MODIFICATI-S UNIT Salem Ill RF.PORT MONTH December 1979 DATE: Januar:t: 11, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507

  • DCR NO. 10CFRS0. 5 9. SAFETY EVALUATION lEC-0699 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.

lMD-0103 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.

lPD-0087 This change is not safety related and does not affect safety related equipment.

lSC-0009 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.

lST-0178 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.

lST-0179 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.

lSS-0011 Not safety related and does not affect any safety related system.

Page 7 of 23

. DOCKET. NO.: 50-272 SliHM..::\..."l:{Y OF SP...FETY RELATED MA*~ENA~CE UNIT NAf.At 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 I

WOR...I{ ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO. I 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 DATE: January 11, 1980 DEPARTMENT Performance REPORT MONTH December 1979 COMPLETED BY: 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

  • .1
  • I 915615 Inst., 1N42 power Recorder 1XA5904RB will not Replaced recorder 1XA5904RB I range (NIS) calibrate I I

. - I 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

. DOCKET. NO.: 50-272

SUMMARY

OF SAFETY RELATED MA.TENA~CE UNIT NAf.1- Salem ill DEPARTMENT Performance DATE: January 11, 1980 COMPLETED BY: L. K. Miller REPORT MONTH December 1979 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 ~,

DOCKET NO.: 50-272 su~~y OF SAFETY RELATED MA.TENANCE UNIT N A Salem 111 DEPAR'l'!<i.ENT Performance DATE: 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 I

929246 Inst., 1PC457E & __ Recalibrate Recalibrated 1PC474B (Pressur-izer Pzr:Comparato.r>

929247 Inst., 1TE440B Failed open Replaced i I

(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~

~

- ~,

DOCKET NO.: 50-272 UNIT NAM--~S-al_e_m~#-1~--~~~~--~

SUM..7-1.ARY OF SAFETY RELATED MA.TENA~CE DATE: J~nuary 11, 1980 DEPARTMENT Performance REPORT MONTH December 1979 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 SU~Y OF SAFETY RELATED MA.TENAN CE UNIT NAL41 Salem /fl DATE: January 11, 1980 DEPARTMENT Maintenance COMPLETED BY: L. K. Miller REPORT MONTH December 1979 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 UNIT N~--S-a_l_e_m~#-1-----------------

SU~-~y OF SAFETY RELATED MA.ENA~CE DATE: January 11, 1980 DEPARTMENT Maintenance COM.FLETED BY: L. K. Miller REPORT MONTH December 1979 ~--~~~~~~~~--~--~--

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

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DOCKET NO.: 50'-272 UNIT NA_s_a_l_e_m_ll_l_ _ _ _ _ _ _ __

SUMi.'1.A.HY OF SP.FETY RELATED MA~~TEN.Ai~CE DATE: January 11, 1980 Maintenance REPORT MONTH December 1979 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 Generator cover as per West. letter Machined Manway covers .. -

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 SU~Y OF SAFETY RELATED MA.TENA~CE UNIT NA Salem Ill DATE: January 11, 1980 DEPARTMENT Maintenance COMPLETED BY: L. K. Miller 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 UNIT N~~S-a-1-ern~#-l~~~~~~~~-

SUMMARY

OF SAFETY RELATED ATENANCE DATE: January 11, 1980 Maintenance COMPLETED BY: L. K. Miller REPORT MONTH December 1979 ~~~~~~~~~~~~~~

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

  • Level Switch) -- -**

919494 Pumps, 11 & 12 - Lubricate pump coupling, Lubricated coupling .. - ..

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, handwheel 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) 17 of 23 Page

...., ~,____ __ _

DOCKET NO.: 50-272 UNIT NAM--S-a_l_e_m_ll_l_ _ _ _ _ _ _ __

SUM..?-1.AHY OF SAFETY RELATED MAITENANCE DATE: January 11, 1980 DEPARTMENT Maintenance COMPLE':'ED BY: L. K. Miller REPORT MONTH December 1979 ~~~~~~~~~~~~~~--

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

_age 18 of 2 3

DOCKET NO. : 50-272 sm~~Y MAITENA~CE UNIT N~~S-a_l_e_m_li_~l~~~~~~~~~

OF SAFETY RELATED DEP .i\.R'l'MENT DATE: January 11, 1980 Maintenance C0!-1..PLETED BY: L. K. Miller REPORT MONTH December 1979 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

~? -

19 of 23 Page

~ ~ _,

DOCKET NO.: 50-272 UNIT NAl..~~S-a_l_e_m~#-1~~~~~~~~-

SU1-L71ARY OF SAFETY RELATED MA. . ENA~CE Maintenance DATE: January 11, 1980 REPORT MONTH Decemb;er 1979 COMPLETED BY: L. K. Miller

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

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

919602 Valve, 14RC25 Repack, packing failed Repacked 919603. Valve, 12SJ54 Repac.k, packing failed Repacked I

919614 Valve, 11RC12 Repack, packing failed Repacked 919619 Valve, 11RC16 Repack, packing failed Repacked 919623 Valve, 13RC11 Repack, packing failed Repacked 919624 Valve, 13RC12 Repack, packing failed Repacked* -

. 919628 Valve, 13RC19 Repack, packing failed Repacked l

I 919630 Valve, 1RC7 Repack, packing failed Repacked 919631 Valve, lPSll Repack, packing failed Repacked 919646 Valve, 11MS130 Repack, packing failed Re.packed 919661 Valve, 12MS173 Repack, packing failed Repacked 919670 Valve, 14MS173 Repack, packing failed Repacked -

919683 Valve, 12MS130 Repack, packing failed* Repacked 919689 Valve, 14MS131 Repack, packing failed Repacked 919787 Valve, 14MS8 Repack, packing failed Repacked 919815 Valve, 1SJ19 Repack, packing failed Repacked 20 of 23 Page

SALEM UNIT #1 OPERATING

SUMMARY

DECEMBER 1979 12/1 Cycle 2 initial criticality occured at 1640 on 12/1/79.

thru 12/22 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.

12/23 Reactor critical at 0020. Low power physics testing was thru 12/24 completed by 0700 on 12/24. For the remainder of the day plant was less than 1% power.

12/25 Plant power was increased to 5% by 1240 on 12/26 and held thru 12/27 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.

12/28 Unit power increased to 20% by 0200 and held at 20% for flux mapping.

12/29 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.

12/30 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 *

. DOCKET NO.: 50-272

~---------~

UNIT: Salem # 1 DATE:January 11, 1980 COMPLETED BY: L. K. Miller TELEl?HONE:609-365-7000 X507 December 1979

l. Refueling information has changed from last month:

x YES

--- ---NO

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 i t scheduled?

5.

July 1980 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: September 1982 Page 23 of 23 8-l-7.R4
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