ML19030A324

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Submit Monthly Operating Report for the Month of August 1978 for Salem No. 1
ML19030A324
Person / Time
Site: Salem  
Issue date: 09/12/1978
From: Midura H
Public Service Electric & Gas Co
To:
Office of Nuclear Reactor Regulation
References
Download: ML19030A324 (15)
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Text

PS~G e RESUl.ATORY DOCKH n!I !IY Public Service Electric and Gas Company P.O. Box 168 Hancocks Bridge, New Jersey 08038 Salem Nuclear Generating Station September 12, 1978 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, D.C.

20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272

\\.:.-**,

In compliance with section 6.9, Reporting Requirements for the Salem Technical Specifications 1 10 copies of the following monthly operating reports for the month of August, 1978 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Summary of Safety Related Maintenance Operating Summary Refueling Information Sincerely yours, 11fr'~,

H. J. Midura Manager -

Salem Generating Station LKM: jcm cc:

Mr. Boyce H. Grier Director of U. s. NRC Off ice of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, Pa.

19406 Director, Office of Management Information and Program Control moa-T:P:srs-:f Nuclear Regulatory Ccrmnission

~ington, D.C.

20555 Enc W1mn*1rn Page l of 8-l-7.R4 95-2189 (4M) 3-78

MONTH August 1978 AVERA.GE DAILY lI'ffT PC'iE~ LEVEL DJCKET i\\0.50-2 72

~~-'---~~~~~

UNIT Salem No. 1 DATE.September 12, 1978 CG*lPLETED BYL. K. Miller TELEPHON.t 609-365-7000, X507 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1

743 2

1069 3

1053 4

1062 5

1038 6

948 7

925 8

496' 9

1022 10 1066 11 1053 12 1092 13 1077 14 1071 15' 1045 16 959 Pg. 2 of 15 8.1-7.Rl a.iwe-NET)

(Mlvc-NET) 17 1073 18 1092 19 1076 20 11 2 21

_:373 22 23 313 24 783 25 9

26 1002 27 535 28 0

29 117 30 968 31 1060

i. Onit Nana:.*

Salem* No. 1

2.

Repc:rrt:i.nq* Peric:d:_A_u g.._u.-.s~t....;;;;1~9-.7.-8__.;. _____ _

3. Licensed 'lllema.l Pc7.er* (mt) : ____

3_3_3_8 ___ _

4.

Ncmep.late Ratinq (Gross.. !fie): ____

'!:"'1~1~3~5 ___ _

s. Design Electrical. Ratinq (Net !fie): __

1_0_9_0 ___ _

6 *. Maximum Dependable capac:ity (Gz:css:,~): 112 4

7.

Maxilllllm: lJet'endable capacity* (Net~): _1_0_7_9 ___ _

Notes *.. -

.e IXX::XEr ro. :_5_0.... -...... 2.... 1... 2 _____ _

~: Seotern.be.r 12:,_ 19}8 a::M?LEm) BY: L.. K. Mi lier TEU:PB:m:: 609-365-7000, X507

a. If. Changes Occur in capacity Ratings. (Items Nul!Cer 3 Thl:co;h 7) S.ince Last P.eport, Give Reason:.

None

9.

J?ower I.eveJ. To Which* PSstricted, If Arr:f* (Net.i.tiel :.* _. _N

.... o

.... n;.;..;;.e ______ ~-----------

lO..

Reasons For P.estrictions ;. If Arr:!~

None

__.;.;.;;..;;. _______________________ ~-

lL. - Hours' In P.e!;Crtinq Peric:d

12.

Nlll!i::er. Of HCtJrs..Reactor Was Critic:al

u. Reactor Reser.le Shuteewn Hours.

l4.

Hou.rs. Generator On-Line,

15. Oriit P.eserve Shutdown Hours l6.

GJ:CSs. 'Ibmnal. Ene?:gy* Generated (Mora) l7 *. GJ:CSs El.ectr.i.cal... Ecergy Generated(Kola).

lS. Net Elect:rical. Energy Generated (Mta) l9. Unit Service Factor 20., Unit AvaiJahility_Factcr 2l. Unit capacity Factcr (Us.inq *MOC Net) 22~ Unit capacity Factor. (Using DER Net)_.

23 *. Unit Forced Ol.It:age Rate

. '!bis M:lnth 744 656.3 0

648.8 0

1,989,124.8

.657,860 626,775 87.2 87.2 78.l 77.3 12.8 Year to Date 5,831 3,257.8 0

3,069.0 0

9,157,994.2 3,084;350.

2.,919,291 52.6 52.6.

46.4 45.9 47.4

  • 24.
  • ShiltdcwriS Scheduled over Next 6 ~
  • (Type, Date, and Duration o£ Each.> :

Cumulative 10,272 5, 801. 0 0

5,499.6 0

15,853,214.2 5,270,660 4,977,509 53.5

53. 5 44.9 44.5 36.2
25. If Shut. Down At End of Report Peri.Odr Estimated Dii.te of* Startup:. ____
26.

Onits* In Test Status (Prior**tc camerc:ial <:peraticn):

  • 8-l-7.R2 Pg. 3 of 15
    • Forecast.

9/30/76 11/01/76 12/20/76 Achieved

  • 12/11/76 12/25/76 6/30/77

NO.

D/\\TE 78-100 8-1-78 78-108 8:::5....:78 78-115 8-7-78 78-116 8-8-78 78-129 8-15-78 l

F: Forced Si Scheduled 8-l-7.R2 Pg. 4 -

15 TIP El F

F F

F F

2 OOFJ\\TION RE1\\9'.JN2 (HOURS) 0 B

0 A

0 A

0 A

0 A

UNIT SI IU'l'IU'INS mID 1'F.R REOOCfIONS REPORT MJ1'm1 August, 19 7 8 MlITIDD OF SHlJITING LICENSE SYSTEM cx:t1I'CWENT IXMN EVEN!'

rnoE'1 CODES RFJ\\CTOR REPOin' I 4

HH FILTER 4

HH FILTER 4

HH FILTER 4

HH TURBIN 4

HC HTEXCH DOCK~~T NO. :

UNIT:Ni\\ME:

50-272 Salem #1 D/\\TE: September 12,' 1~78 COMPJ,ETED DY: L. K. Miller TELEPHONE: 609-365-7000 X507 CJ\\USE J\\ND rnrmocrIVE J\\CTIOO TO PREVENI' RFilJRP.ENCE Clean Steam Generator Feed Pump and Condensate Pump Suction Strainers.

Clean Condensate Pump Suction Strainers.

Clean Steam Generator Feed Pump Suction Strainers and repair,

  1. 11 Recirc. Valve.

Turbine vibration caused by Governor Valve going open (due to blown 0-ring on EH,Oil Line).

12A Condenser leak.

3 4

5 Peason:

1\\-Equiprent Failure (Explain)

B-Maintenance or Test C-Refueling D-Regulatory nestriction E--operator Training & License Examination F-1\\dmlnistrative

~rational Error(Explain)

II-Other (P..xplain)

M3thod:

!-Manual 2-Manuai Scram.

3-Autanatic Scram.

4-0ther (Explain)

Load Reduction Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event lleport (LER) File (NIJREX}-0161)

F.x.hibi t 1-Sane Source

NO.

DATE TYPE1 78-137 8-21-78 78-138 8-23-78 78-141 8-24-78 78-142 8-24-78 78-145 8-25-78 78-154 8-27-78 Page 5 of 15 ll'-1-'7.Rl F

F F

F F

F DURATION IlEASON2 (HOURS) 45.75 G

0 A

0 A

0 A

0 A

49.43 H

UNIT smmx:mNS 1\\ND PCMER IlEOUCTIONS REPORI' IDHI'H August' 19 7 8 METHOD OF SHUITING LICENSE SYSTEM COMPONENT IXMN EVEN!'

<XlDE4 CODES REI\\C'IDR REPORT II 1

IA PUMP XX 4

HH FILTER 4

HC HTEXCH 4

HC HTEXCH 4

HC HTEXCH 3

HA TURBIN DOCKET NO.: 50-272 UNIT NAME:

Salem #1 DATE:

S*eptember 12, 1978 COMPLETED BY:

L.K. Miller TEIJEPllONE:

609-365-7000 X507 CAUSE AND CORRECTIVE ACfION 'ID PRE\\IENI' REOJRRENCE Reactor trip due to loss of Reactor Coolant Pump.

  1. 12 Reactor Coolant Pump breaker was manually opened.

Clean #11 and #13 Condensate Pump Suction Strainers.

  1. llA Condenser leak.
  1. llA Condenser leak.
  1. 12A Condenser leak.

Reactor trip due to a Maintenance error on the part o*f outside contractor causing turbine trip l

I, l

MODIFICA'9Ns MAJOR PLANT REPORT MONTH August 1978

  • DCR NO.

PRINCIPLE SYSTEM l-ED-0364 Service Water l-ET-0400 4 kv Bus u.v. Relays l-EX-0402 Circulating Water l-OD-0048 Waste Liquid

  • DESIGN CHANGE REQUEST 8-1-7.Rl DOCKET NO.:

5Q-2:Z2 UNIT -~1E:

Salem I DATE:

Septei:nber 12, 1978 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000, X507 SUBJECT Install Modified No. 14 s.w.

Pump Install Temporary D. c. Feed Determine Reduced c.w. Flow by Throttling Discharge V~lve Replace Saunders Valves with Full Flow Plug Valves Page 6 of 15

DOCKET NO.: 50-272

.=.,:._....-...-....~~~~~~-

MAJOR PLANT MODIFICAT~S IU:'PoRT MONTH August 1"'8 UNIT,~:

ATE:

Salem I

  • September. 12, 1978
  • DCR NO.

l-ED-0364 l-ET-0400 l-EX-0402 l-OD-0048 10CFRSO. 59.

COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000, X507 SAFETY EVALUATION Setpoint change required to comply with new s.w. Pump performance curves.

The change does not degrade system performance.

Addition of noise suppressor will not affect safety function of the relay.

Safety analysis are not affected.

The implementation of this experiment does not affect any presently performed safety analysis nor does it create any new hazards.

The basis of the Technical Specifications are not affected.

This DCR requests the substitution of plug-type valves for diaphragm-type valves.

This change does not increase the probability or consequences of an accident, create a possibility for an accident or malfunction or reduce the margin of safety as previously defined.

  • ---.... ~
  • nESIGN CRAJ.'1GE.RF.QUEST Pa e 7 of ls

DOCKET NO.: 50-272

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

UN IT N~:~_s_a_l_e_m~#_l~~~~~~~-

SUMMARY

OF SAFETY RELATED 'INTENANCE c

Maintenance REPORT MONTH August, 1978 DATE:

September 12, 1978 COMPLETED BY: L.K. Miller TELEPHONE: 609-365-7000 ( X507)

WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

MD-2939 11RC17 Valve Packing leak.

Tightened packing.

MD-2918

  1. 14 Service Water Auto Breaking shear keys.

Replaced bottom wear Strainer shears and keys.

OD-10033

  1. 12 Service Broken shear keys.

Replaced shear keys.

Water Strainer MD-2781 Cask Handling Worn cable.

Replaced cable.

Crane OD-8878 lDDC #27 Check for ground.

Replaced limit switch.

Breaker MD-2916 Containment Failed leak test.

Adjusted locking device.

Air Lock Inner Door OD-9481 Service Water Pipe leak.

Installed temporary Piping patch.

OP-9431 Service Water Pipe leak.

Installed temporary Piping patch.

OD-9527

  1. 16 Service Broken shear key.

Replaced distributor barrel Water Pump 0-ring and shear key.

Strainer OD-9909 13MS168 Valve Packing leak.

Packing tightened.

OD-9474

  1. 11 Chiller Leak.

Replaced tubing reducer to Unit condenser.

OP-9885 12SW23 Valve Valve leak.

Applied temporary patch and clamp.

OD-9535

  1. 11 Service Housing leak.

Temporary patch installed.

Water Pump

~ --

Strainer 8-1-7.Rl Page 8 of 15

DOCKET NO.:

50-272

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

UNIT N~:

Salem #1 DATE:

September 12, 1978 sriMMA.RY. OF SAFETY RELATED.lrNTENANCE Performance COMPLETED BY:

L. K. Miller TELEPHONE:

609-3£5-7000 (X507)

REPORT MONTH August, 1978 WORK ORDER NO.

PD-4930 PD-4934 PD-4937 PD-4939 PD-4944 PD-4902 PD-4904 PD-4917 PD-4920 PD-4926 PD-4927 OD-9388 OD-9384 Page 10 of rt:;

8-1-7.Rl EQUIPMENT 13RC431C 1PM505B 1PC526C 1PT536A/B 1LC461A/B 11 Steam Generator Steam Flow Channel II - -

1TM441E 1FC511A/B 14 Steam Generator -* -*

1LT549 11 Boric Acid Tank level 1LT106~

12 Batt. Level 1LT102.

A.F.D. Recorder XA-8740..

  1. 13 Steam Generator Level FAILURE DESCRIPTION CORRECTIVE ACTION Verify setpoint.

Adjusted calibration of Tavg.

Summa tor failed low.

Replaced summator.

Verify setpoints.

Adjusted trip and reset points.

Trips 8rnv high.

Adjusted output #2 setpoint, Verify setpoints.

Adjusted setpoints.

Stearn flow failed low. Repaired faulty connections on-the PCB

  • -- - --Elco connector.

High trip point.

Adjusted trip points.

Low setpoint.

Adjusted setpoint.

Out of calibration.

Installed and calibrated new PCB transmitter.

Low setpoint.

Calibrated.

High transmitter Calibrated.

output.

Out of calibration.

Recalibrated recorder.

Verify stable operation.Recalibrated transmitter.

SU~Y OF SAFETY RELATED IINTENANCE DEPARTMENT Maintenance DOCKET NO.:

50-272 UNIT N~:~~-S-a_l_e_m~#-1~~~~~~

DATE:

SEi.ptember 12, 1978

~~~---~~~~--"-~~~-

REPORT MONTH August, 1978 C 0 MP LET ED BY:

L.K. Miller

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

WORK ORDER NO.

OD-10051 MD-8956 OD-10124 MD-2951 MD-2851 OD-10077 MD-2892 OD-9569 MD-2846 OD-10099 OP-0311 MD-2944 OD-10068

  • Page 9 of is*

8-1-7.Rl EQUIPMENT

  1. 16 Service Water Pump Strainer 1CC190 13RC26 Valve Airlock Door 4kV Group UF Relays lH and lF 11MS169 Valve lA Diesel Controls"
  1. .T2 RHR Room.. **

Cooler 13CV78 Valve 13MS168 Valve

  1. 14 Service Water Pump 1CC190
  1. 13 Service Water Screen TELEPHONE:

609-365-7000(X507)

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

FAILURE DESCRIPTION CORRECTIVE ACTION Strainer trips.

Replaced moter, seals, and fittings.

Motor malfunctioning.

Replaced motor.

Packing leak.

Tightened packing nut.

Door leaks repacking Replaced two cam followers needed.

and two inner door gaskets Relays causing trips.

Replaced relays.

Valve leaks through.

Replaced stem and seat disc.

Spike on D.C. feed.

Replaced power supply.

Service Water leak.

Repaired plugs in coil.

Bonnet leak.

Furmanited valve.

Packing leak.

Furmari+/-ted*~ackirig *gland.

Replace pump.

Removed and installed rebuilt pump.

Valve motor operator Replaced operator.

malfunctioning.

Inch pushbutton not Cleaned threads and hole working.

on shaft.

50-272 SUMMA'RY OF SAFETY RELATED IINTENANCE DEPARTMENT Performance DOCKET NO.:

UNIT N~:

DATE:

Salem #1 September 12, 1978 L.K. Miller REPORT MONTH August, 1978 COMPLETED BY:

WORK ORDER NO.

OD-9377 OD-9337 OD-9117 OD-9260 OD-9291 TELEPHONE:

609-365-7000 (X507)

EQUIPMENT

  1. 11 Steam Gen.

Low Low Level

  1. 12 Boric Acid
Tank, Safety Inject.

Accumulator FAILURE DESCRIPTION Verify stable operation.

Hi-Low Temp. Alarm is illuminated.

Calibrate 11 and 12 Accumulator level.

CORRECTIVE ACTION Replaced comparator and calibrated 1LC518A/B.

Inserted fuse.

Recalibrated-LT-934A,

Gf.r.,...9 35A,_LT-9 35B, LT-9 34B.

Safety Inj-ectior Channel A shows Repaired sticking 11.. Accum.Ch.A increase while Channel indicatoL~eplaced strain B is constant.

gauge.

Safety Injection Channel A erratic.

  1. 11 Accum.

Repaired and -recalibrated indicator.

Page 11 of 15 8-1-7. Rl

i SALEM I OPERATING

SUMMARY

AUGUST 1978 8-1 Unit load was reduced to 50% to clean feed pump suction strainers.

At 0900 a load increase was started and the unit reached full output at 2200.

The unit remained at full load until 8-5.

8-5 At 2124 a load reduction to 70% was initiated in order to clean condensate pump suction strainers.

8-6 The unit returned to full load at 1200 and operated there the remainder of the day.

8-7 At 1455 a load reduction was initiated in order to clean feed pump suction strainers.

At 2400 the unit was at 45%

load.

8-8 At 0030 the unit was at 40% load.

At 0400 unit load reached 52%.

This level was held while repairs were made to a feed pump recirculation valve.

A load increase was started at 1200 but was terminated at 1448 due to turbine vibration.

Load was decreased from 62%-to 55% while the problem was analyzed.

The vibration was caused by the failure of a turbine governor valve to open.

The cause was a blown 0-ring in the E-H oil line.

Repairs were made and a load increase was started at 1900.

8-9 The unit reached full load at 0642.

The unit remained at full power until 8-15.

8-15 At 2045 a load reduction at 15%/HR. was initiated because of condenser tube leaks.

Load was stabilized at 70%.

Page 12 of 15

8-16 8-21 8-23 8-24 8-25 8-26 8-27 At 0330 a load increase was initiated at 5%/HR.

The unit reached £ull load at 1000.

The unit remained at £ull load until 8-21.

At 0312 load was decreased to 97% due to condenser tube leaks.

At 0915 a Reactor/Turbine Trip occurred £rom £ull load.

The trip was caused by a loss 0£ reactor coolant flow when a reactor coolant pump breaker opened.

The unit was taken critical at 0355.

The delay in going critical was caused by repairs that had to be made to an inoperable £an coil unit.

The unit was synchronized at 0700.

A load increase was initiated and the unit reached 70% at 2000.

The unit was held at this level while condensate suction strainers were cleaned.

The load increase was continued at 2230.

The unit reached £ull load at 0600.

At 0713 a load decrease was initiated due to high condenser backpressure.

Load was reduced to 78%.

At 1155 load was £urther reduced to 70% when a circulator was removed from service.

A load increase was initiated 2040.

The unit reached full load at 0300.

At 0424 load was reduced to 90% due to condenser tube leaks.

At 1022 power was increased to £ull load.

At 1648 load was reduced to 91% in.order to remove a circulator from service.

At 1050 power was increased to full load and the unit operated at this level all day.

At 1257 a reactor/turbine trip occurred £rom £ull load when an outside contractor dropped an air horn on the turbine trip block.

Page 13 of 15

~

8-29 8-30 8-31 The unit was taken critical at 1000.

The delay in going critical was due to repairs to a containment fan coil unit, contai~ment air lock door, lA Vital Bus Instrument Inverter and the rod control system.

The unit was synchronized at 1425 and at 2400 load had increased to 63%.

The unit reached full load at 0800 and remained at full load for the day.

The unit was at full load for the day.

Page 14 of 15

REFUELING INFORMATION.*

DOCKET NO.:

50-272 UNIT: Salem No. 1 DATE: Septeinl5er 12 ~.1978 COMPLETED. BY: L.K. Miller TELEPHONE: 609-365-7000 -

X507 MONTH:

August, 1978

l.

Refueling information has cha."'lged from last month:

YES X

NO ---

2.

Scheduled date of next refueling:

March 31, 1979 May 26, 1979

3.

Scheduled date for restart following refueling:

~---------~

4.. A.

Will Technical Specification changes or other license

  • amendments be required?

YES NO __ _

NOT DETERMINED TO-DATE August, 1978 B.

Has the reload fuel design. been reviewed by the Station Operating Review Cammi ttee'?

YES NO X

If no, when is it scheduled?

5.

Scheduled date(s) for submitting proposed licensing action:

February. 1979 if reg:ujred, 6.*

  • Importan.t licensing considerations.associated with refueling:

None

7.

Number of Fuel Assemblies:

A.

In-Core 193 B.

In Spent Ftiel Storage

  • 0
8.

Present licen~ed spent fuel storage capacity:

264

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

Future spent fuel storage capacity:

1 170

--~-=-:~------~

9.

Da.te *of last refueling that can* be discharged to the spent. fuel pool assuming the present licensed capacity:.

Page 15 of 15 8-l-7.R4

  • ~....._.

i:\\pril, 1982

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