ML19030A337

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Submit Monthly Operating Report for the Month of March 1978 for Salem No. 1
ML19030A337
Person / Time
Site: Salem  PSEG icon.png
Issue date: 04/10/1978
From: Heller H
Public Service Electric & Gas Co
To:
NRC/IE, Office of Nuclear Reactor Regulation
References
Download: ML19030A337 (14)
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Text

  • O PSJffiG
  • Public Service Electric and Gas Company Salem Generating Station P. 0. Box #168 Hancocks Bridge, New Jersey 08038 April 10,* 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, 10 copies of the following monthly operating reports for the month of March, 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,

/

  • ~ '_' -------

H. -J. Heller Manager -

Salem Generating Station JMZ:jcm cc:

Mr. Boyce H. Grier Director of U. S. NRC Office of Inspaction and Region I Enc.

631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 PagJ°h:E! b'Ier!J~ People 8-1-7. R4

"""'\\

I 781090036 95-2189 (2M) 10-76

e OPERATING DATA REPoRI' OPERATING STATUS

l. Unit Nana:

Salem No. 1 Notes:

2. ~g Period:

March, 1978

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

3.

Licensed Thel:ITa.l. Polo.er (.:-wt) :

3338

-=--=-~,.---------

4.

Nam::plate Rating (Gross MWe) :

1135

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

5.

Design Elec'"..rical P.ating (Net MWel:

1090

6.

Maximum Dependable Capacit'J (Gross !<We): 1124

7.

!".axiirum Dependable Capacity (Net ~) : --=1..,,0=7""9,....----

e CX:X:::"(El' ~. :

5 0-2 72 DA...."'E :

April 10, 1978 CCMPLETED BY: J.M. Zupko, Jr.

TELEPHCNE: 609-365-7000 X507

8.

If Changes Occur in capacit:'.f P.atings (!tats Nl.ll!i:er 3 Through 7) Si11ce Last Rep:irt, Give Reason:

None

9.

Pcwer Level To Whid1 Festricted, If Arr-I (Net me) : ___

N_o_n_e ____________________ _

10.

Rea.sons For Restrictions, If Any:----------------------------------

This M:lnth Year to Date 0.mtlative 744 2160 6601 ll. Eours L>1. Rep:irting Pericx:l.

12.

Nuirber Of !'.ours Reactor Was Critical 354.2 1522.7 4065.9

13.

Reactor Reserve Shut:Ccwn Hours 0

0 0

14.

Hours Generator on-Li!le 352.6 1460.1 3890.7

15.

Unit Reserve Shutecwn Hours 0

0 0

16.

Gross Ther.na..l Er.ergy Generated (~'Hl l,080,I6'.J 4,505,479 II I :2C:i0 I 699

17.

Gross Elect...'"ical Energy Generated (MWH) 3:Z4,Q2Q 1,548,500 3[734[810

18.

Net Elect..'"ical Energy Generated (I-~'H) 354,613 1,475,405 3,715,333

19.

Unit Se...""Vi.ce Fac'"...or 47.4 67.6 58.9

20.

Unit Availability Factor 47.4 67.6 58.9

21.

Unit Capacity Factor (Using 1'10C Net) 44.2 63.3 52.1

22.

Unit Capacicy Factor (Usi.'"lg DER Net)

!13. :z 62.7 51.6

23.

Unit Forced Outage Rate 52.6 32.4 21.3

24.

Shutda.ins Scheduled over Next 6 M:nt.~ (Type, Date, and Duration of Each):

None

25.

If Shut~ At End of Report :i?edcd~ Estirated Date of Start:.:p: _____

5/_2_1_/_7_8 __________ _

25.

Units In Test Status (Prior to Ccm!l=rcial Gperation):

8-1-7.R2 Page 2 of 14 INITIAL CP.ITI~""TY DITTI..'U. EL:."""CTRICITI C"'~

OPERAT:::CN Fore---....ast 9/30/76 11/1/76 12/20/76 Ac."lieved 12/11/76 12/25/76 6/30/77

MONTH March, 1978 LGE DAILY UNIT POWER LEVEL e OOCKET NO.

50-272 UNIT Salem No. 1 DATE April 10, 1978 CCTvIPLETED BY J.M. Zupko, Jr.

TELEPHONE 609-365-7000 X507 DAY AVEAAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)

(MWE-NET) 1 1116 17 0

2 1115 18 0

3 1057 19 0

4 758 20 0

5 1042 21 0

/'-* '

409

'. i,

. 6 22 0

7 835 23 0

8 1090 24 0

9 1054 25 0

10 1117 26 0

11 1115 27 0

12 1103 28 0

13 1023 29 0

14 1059 30 0

15 1010 31 0

16 9

8.1-7.Rl.

Page 3 of 14

oo.

DATE TYPE!

78-32 3-3-78 F

78-33 3-5-78 F

78-34 3-6-78 F

78-35 3-8-78 F

78-36 3-12-78 F

78-37 3-13-78 F

78-38 3-13-78 F

1 2

F:

Forced S:

Scheduled 8-l-7.R2 Page 4 of 14 UNIT SlllT.l'IXMNS l\\ND PCMl\\R REIXJCl'IONS DOCKET NO.:

50- 212

~-~--

REWRT MJNTII March I 197 8 UN IT NAME:

Salem No. 1 DATE:

April 10, 1978 COMPLETED DY:

J.M. Zupko, Jr.

TELEP 110 NE:

609-365-7000 X507 MF.TIDD OF OORJ\\'l'ION REl\\SON2 SHlTrI'Itx; LICENSE SYS1'EM ~

CAUSE AND CX:lRRECl'IVE (HOURS) i::xmN RFJ\\CTOR 0

A 4 (A) 0 A

4 (A) 10.9 G

3 0

A 4 (A) 0 B

4 (A) 0 A

4 (A) 0 A

4 (A)

Reason:

A-Equiprent Failure (Explain)

B-Maintenanoe or *rest C-Refueling 0-Regulatory Restriction EVEm' REPORT I E-Operator '!'raining & Lirense Examination F-1\\dminis t ra ti ve G-Operational Error(Explain)

II-Other (F'..xplain) 3 rooirt rooES HH Filter HA Instru HA BBB BBB HH Filter HA BBBBBB HH Filter HH Filter f>hthod:

!-Manual 2-Manual Scram.

3-Autanatic Scram.

4-0ther (F'..:xplain)

N<YI'ES:

A.

B.

ACrION 'lU Piu:.vENr REOJRI'J'NCE Clean Cond. and St:rn.Gen. Feed Pump Suction Strainers.

Frozen feeler line on turbine impulse pressure channel.

Turbine - Reactor Trip caused by per-sonnel error during routine trouble-shoot~of turbine alarm and trip c1rcu1 Clean 11, 12, 13 Cond.Pump Suction Strainers.

Turbine valve test.

Clean 11 Cond Pump Suction Strainer.

Clean 11 Cond Pump Suction Strainer.

4 Exh.ibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report(LER) File (NURF&-0161)

Load Reduction 5

Exhibit ! -Sane Souroe Continuation of previous outage.

NO.

DATE 78-39 3-14-78 78-40 3-15-78 8-l-7.R2 Page 5 of 14 TYPE!

F F

OORATIOO RE1\\SON2 (HOURS) 0 A

380.5 A

UNIT Sllll'I.'ra'INS rum FOOER REDUCTIONS REPORT MJ~tm March, 1978 METIOO OF s1nnTn>K; LICENSE SYS1'EM ~

ro'IN EVEN!'

OJDE4 mo ES REl\\C'lDR REPORT I 4 {A)

HA Turbin 1

HA Turbin 50-272 DOCKET NO.: --------

UNIT*NAME:

DATE:

COMPLE'fED BY:

TELEPHONE:

Salem No. 1 April 10, 1978.

J.M. Zupko, Jr.

609-365-7000 X507 CAUSE AND OJRR

  • ECl'IVE ACrION 'ID PREVENI' High vibration, Main Turbine Bearing No. 3.

High vibration, Main Turbine Bearing to make nee-No~ 3.

Unit shut-down essa:r:y turbine repairs.

MAJOR PLANT MODIFICAT~S REPORT MONTH March, 1978

  • DCR NO.

PRINCIPLE SYSTEM ED-0051 Computer Inverter ED-0077 Heating Steam ED-0124 Safety Injection ED-0129 Part Length Rods ED-0138 Plumbing OD-0010 Auxiliary Alarm 1g.6 Of 14

  • DESIGN CHANGE REQUEST DOCKET NO.:

50-272 UNITr:

Salem #1 DATE:

April 10, 1978 COMPLETED BY: J.M. Zupko, Jr..

TELEPHONE: 609-365-7000 X507 SUBJECT Replace Power Supply Add Atmospheric Vent to Condensate Receiver.

Stiffen Baseplate on No. 12 S.I. Pump Motor Remove Annunciator D241 Add Float Switch Alarm in Relay Room Pipe Enclosure.

Change State of Sampling System Valve Alarm.

?g.7 of 14 DOCKET NO.:

50-272 MAJOR PLANT MODIFICATil!iNS UNI~:

Salem #1

  • REPORT MONTH March, ~

7 8 DATE:

April 10, 1978

  • DCR NO.

ED-0051 ED-0077 ED-0124 ED..:.0129 ED-0138 OD-0010 COMPLETED BY:~ __

J_._M_. __

z_u~p_k_o_, __ J_r __._

TELEPHONE: ____

6o_9_-_3_6_s_-_1_o_o_o __

x_s_o7 10CFRS0.59.

SAFETY EVALUATION Unless indicated otherwise, no change to the FSAR or Technical Specifications are involved nor does the Design Change involve an Unreviewed Safety Question.

Safety related equipment will not be affected.

This design change does not effect any presently performed safety analyses nor does it create any new hazards.

The Bases of the Tech. Specs. are not affected.

Change will reduce vibrations but will not effect other performance characteristics.

Performance of motors' safety function will not be affected by this change.

Therefore, the criteria of an unreviewed safety question is not satisfied.

Safety related equipment will not be affected.

This design change does not in any way alter the function of the pipe e.nclosure.

An unreviewed safety question is not involved.

Safety related equipment will not be affected.

i

~UMMA~Y.OF SAFETY RELATE~INTENANCE UNIT ~E:

Salem #1

!JP!rE:

April 10, 1978 COMPLETED BY: J. M. Zupko, Jr.

DEPARTMENT Performance REPORT MONTH March, 19 7 8 TELEPHONE: 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

PD-3807 S.S.P.S. Relays Verify correct relays Verified as instructed.

installed.

PD-4540

  1. 13 Chiller Check temperature Verified Controller set-Temp.Controller control.

point.

PD-4545 Valves 12SW92 & Re stroke valves.

Restroked valves.

12SW93.

OD-8309

  1. 13 Aux. F.W.

Disch.press. i ndica-Replaced transmitter power Pump.

tion not working.

switch.

OD-8231 N.I.S. N-47 Redundant :focorder Recalibrated recorder.

channels do not agree.

OD-8129 1st Stage Redundant channels do Recalibrated indication.

Pressure not agree.

Indication.

OD-8408 11 Batch Tank Level indication Increased air flow to fluctuates.

bubbler.

PD-4558 1FT523 Transmitter found out Recalibrated lFT-523.

of spec.

PD-4569 Module 1FC521A 1FC521A&B found out of Replaced capacitors &

& B.

spec on functional recalibrated.

test.

PD-4579 Valve 12SW58 Open indication not Adjusted limit switch.

working.

PD-4581 Module 1PC456B& 1PC456B & D found Adjusted set points.

D.

out of spec. on functional test.

I PD-4590 N.I.S. N-43 Functional test out Recalibrated.

of spec.

Pg. 8 of 14 8-1-7. Rl

IJUCKE r NU * :

50-272

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

su"MMARy* OF SAFETY RELATE.INTENANCE DEPARTMENT Performance REPORT MONTH March, 19 7 8 UNIT ~: Salem #1

""TE:~_A_pi.....;;;..r_i_l___;;;l~0~.,-""'1_9~7~8'"--~~-

COMPLETED BY: J.M. Zupko, Jr.

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

OD-84 79 28 Volt DC Bus Ground on 28 VDC Bus..

Repaired grounded relay.

PD-4614 lFC-415 1FC415 out of spec.

Recalibrated lFC-415.

PD-4612 PD-4559 PD-4316 OD-8497 Pg. 9 of 14 8-1-7.Rl Module lFC-435 Comparator out of spec Recalibrated.

on functional test.

11 Stm. Gen.

Feed Pump.

13 Fan Coil Unit.

Containm"'!nt Channel I Press.

Operation of speed control incorrect.

Check out alarm.

Replaced operating station Verified alarm.

Redundant channels do Recalibarated Transmitter not agree.

PT948D.

.1..1v...,..n.1.:1.1.

~~v **

Ju-..:.1.i:.

SUMMARY

OF SAFETY RELATE~INTENANCE UNIT£:

Salem #1 TE:

April 10, 1978 DEPARTMENT Maintenance REPORT MONTH 1978 COMPLETED BY: J. M. Zupko, Jr.

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

OD-8462 15 Service 4KV breaker spring Repositioned striker plate Water Pump won't charge.

OD-8443 11 Chiller Head gasket leaking.

Replaced head gasket.

MD-2559 Valve 1CV18 Packing leak.

Tightened packing gland.

OD-8375 4KV Relay Plastic relay case Replaced relay.

Enclosure broken.

OD-8438 Elev. 130 Inside door has crack-Replaced roller bearing.

r Containment ed roller.

Air Lock

. OD-8268 Steam Generator Tank sight glass Tightened all sight glass*.

Snubber.

leaking.

. c--

OD-8439 -*

1A28V DC Bus Ground on lA 28VDC Bus Repaired pin on lamp cir-cuit.

OD-6054 MD-2517

  • MD-2526 OD-8307 MD-2571 OD-8793 OD-8601 OD-8589 Pg. 10 of 14 8-1-7.Rl
  1. 12 Waste Gas Comp.

Valve 12 '& 14 MS168 Valve 12MS199 Valve 11MS18 Valve 1SJ12 &

1SJ13.

Boric Acid lA Diesel 15 Water Pump Motor appears burnt Installed new motor.

out.

Packing leak.

~epacked valves.

Packing leak.

Repacked valve.

Grease plug leaking.

Welded grease plug in body Packing leaks.

Repacked valves.

Evap. condenser leak-Plugged vent cond. tube.

ing.

No alarm indication Replaced fuse in Annuncia-11 on local annunciator tor Panel.

I:

local panel.

11 Packing leak.

Repacked pump.

I i

SUMMARY

. OF SAFETY RELATE~INTENANCE DEPARTMENT Maintenance Salem #1 UNIT jiME:

"'TE:--=A~p~r~i~*l~l~0~,-=1~9~7~8~~~~

COMPLETED BY:~_J_. __

M_. __

z_u_p_k_o_, __

J_r_*~--~

REPORT MONTH March, 1978 WORK ORDER NO.

OD-8595 MD-2527 OD-8777 I

Page 11 of 14

11 Component Cooling Hx.

Valves 13RC16,.

17, 18.

TELEPHONE: 609-365-7000 X507 FAILURE DESCRIPTION CORRECTIVE ACTION Strainer shaft packing Repacked strainer.

leak.

Repair tube leaks.

Plugged leaking Hx. Tubes.

Packing leaks.

Repacked valves.

I

INTHLY OPERATING

SUMMARY

tt SALEM I MARCH, 1978 3-1 The unit operated at full load until 3-3.

3-3 At 1744 a load reduction of 5% per hour was initiated to reduce load to 50% to clean feed and condensate pump suction strainers.

3-4 At 1140 a load increase of 5% per hour was initiated.

The unit reached 100% load at 2200.

3-5 At 0211 the unit experienced a load rejection from 100% to 68% when a sensing line for turbine first stage pressure froze.

The unit was returned to full power at 1130.

3-6 At 0836 a reactor/turbine trip occurred from 100% power, when an electrician trouble shooting a turbine thrust bearing alarm shorted out two contacts in the auto-stop oil circuit.,

The reactor was taken critical at 1800 and the unit synchronized at 1923.

3-7 The unit reached 100% load at 1800.

3-8 At 1929 a load reduction of 5% per hour was initiated to reduce load to 70% to clean condensate pump suction strainers.

3-9 At 0115 a load increase of 5% per hour was initiated.

The unit reached 100% load at 0722.

The unit stayed at full power until 3-12.

3-12 At 0001 the unit started a load reduction to 89% to perform a periodic turbine valve test.

The unit returned to full power at 0630.

3-13 At 1558 a load reduction was initiated to reduce load to 70% to clean condensate pump suction strainers.

At 2305 began to return Page 12 of 14

to full load.

The unit reached 100% load at 0500 on 3-14.

3-14 At 1858 a load reduction was started to reduce load to 82%

due to high vibration in No. 3 Main Turbine Bearing.

3-15 The unit reached 100% load at 0430.

At 1830 a load reduction at 10% per hour was initiated to take the unit off the line due to high turbine bearing vibration.

3-16 The unit was taken off the line at 0327.

An outage was started to make turbine repairs.

Page 13 of 14

e REFUELING INFORMATION DOCKET NO. :

50-272 UNIT:

Salem No. 1 DATE: April 10, 1978 COMPLETED BY: J. M. Zupko, Jr.

TELEPHONE: 609-365-7000 X507 MONTH:

March, 1978

1.

Refueling information has changed from last month:

YES NO X

2.

Scheduled date of next refueling:

February 6, 1979

3.

Scheduled date for restart following refueling:

April 3, 1979

4.

A.

Will Technical Specification changes or other license amendments be required?

YES NO ---

NOT DETERMINED TO-DATE March, 1978 B.

Has the reload fuel design been reviewed by the Station Operating 1

Review Conunittee?

YES NO X

If no, when is it scheduled?

N~o-~-ember;;.;=-=-~'-1~9~7~8 ______________________ __

5.

Scheduled date(s} for submitting proposed licensing action:

December, 1978 if required.

6.

Important licensing considerations associated with refueling:

None

7.

Number of Fuel Assemblies:

A.

In-Core 193 B.

In Spent Fuel Storage 0

8.

Present licensed spent fuel storage capacity:

264 Future spent fuel storage capacity:

1170

9.

Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

April, 1982 Page 14 of 14

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