ML19030A331

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Submit Monthly Operating Report for the Month of May 1978 for Salem No. 1
ML19030A331
Person / Time
Site: Salem  PSEG icon.png
Issue date: 06/09/1978
From: Midura H
Public Service Electric & Gas Co
To:
NRC/IE
References
Download: ML19030A331 (16)
v • d • e


Text

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In compliance with sec~ion 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of May, 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,

~ #.: J.4*... -.--1_

/~-: ~

y H. J. Midura Manage~ -

Salem Generating Station L&"l'vl: jcm cc:

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

19406 Director, Office of Management Information and Program Control mo:itI~{S:/ Nuclear Regulatory Commission

~_,:1Sir-ington, D.C.

20555

.\\llSOI' Enc*

nnrn Pa1;e l of 16 8-l-7,P4 95-2189 (4M) 3-78

MONTH May, 1978 I e e

AVERAGE DAILY UNIT POWER LEVEL IX)CKET NO.

50-272 UNIT. Salem No. J DATE 6/9/78 ~

COMPLETED BY L. K. Miller TELEPHONE 609-365-7000 X507 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET)

(MWE-NET) 1 0

17 0

2 0

18 0

3 0

19 0

4 0

20 0

5 0

21 0

(.-,:.,,,."

\\' ; 6 0

22 0

--.......,,./

7 0

23 0

8 0

24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

J',,.

\\.~/ Page 2 of 16 8.1-7.Rl

e OPERATmG DATA REPORI' OPERATING STATUS L

Unit Nam:i:

Salem No. 1 Notes:

2.

Reporting Period:

May; 1978

~---~---................ ---------........ ~

3.

Licensed Thental ~

(MVt):

. 3338

4.

Narreplate Rating (Gross MVe):

1135

5.

Design Electrical Rating (Net MVe): 1090

---~......... ------......... ------

6.

Maxill!um Dependable capacity (Gross MVe): 1124

7.

Maximum Dependable Capacity (Net MWe):

1079 e

I:X:CI<E'I' N). :

5 0-2 72 DATE :

6/9/78 COMPIEl'ED BY:

L. K. Miller TELEPHONE: 609-365-7000 X507

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report, Give Reason:

None

9.

Power Level To wnich Restricted, If AwI (Net MWel:

None

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

10.

Reasons For Restrictions, If Any:

This 1-bnth Year to Date 744 3623

11.

Hours In Reporting Periad

12.

Number Of P.ours Reactor Was Critical 0

1522.7

13.

Reactor Reserve Shuteown Hours 0

0

14.

Hours Generator On-Line 0

1460.1

15.

Unit Reserve Shuteown Hours 0

0

16.

Gross Thental Energy C--enerated (M-111) 0 4,505,479

17.

Gross Electrical Energy Generated (MWH) 0 1,548,500

18.

Net Electrical Energy Generated (MWH)

{3,Si2J 1,467,159

19.

Unit Service Factor 0

40.3

20.

Unit Availability Factor 0

40.3

21.

Unit Capacity Factor (Using MCC Net) 0 37.5

22.

Unit capacity Factor (Using DER Net) 37.2

23.

Unit Forced Outage Rate 100 59.7

24.

Shut.dcwns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

None

25.

If Shut eown At End of Report Period! Estimated Date of startup:

June 17' 1978

26.

Uni ts In Test Status (Prior to Camercial Operation) :

8-l-7.R2 Fage 3 of 16 INITIAL CRITICALITY INITIAL ELECTRICITY CCMMERCIAL OPERATION Forecast 9/30/76 11/1/76 12/20/76 Cumulative 8064 4065.9 0

3890.7 0

11,200,699 3,734,810 3,525,377 48.3 48.3 40.5 40.1 39.3 Achieved 12/11/76 12/25/76 6/30/77

NO.

DATE TYPE1 78-40 3-15-78 F

1 2

F: Forced S:

Scheduled B-1-7.R2

'Page -4 *of 16 I

UNIT SHUT!XMNS AND.Pa'IBR REDUCI'IONS REPORI' MJNI'H METHOD OF DUMTION REl\\SON2 SHU'lTING (HOURS) ocmN REJ\\croR 744.0 B

1 Reason:

A-Equiprrent Failure(Explain)

B-Maintenance or Test C-Refueling D-Regulatory Restriction LICENSE EVENT REPORT II 3

E-Operator Training & License Examination F-Administrative

~,-Operational Error(Explain)

!I-Other (Explain)

MAY, 1978 SYSTEM CCH'ONENT CODE4 CODES HA IT'urbine Method:

1-Manual 2-Manual Scram.

3-Autanatic Scram.

4-0ther (F_,xplain)

DOCKET NO.:

50~272

~

UNIT *NAME:

Salem No. 1 DATE:

6/9/78 COMPLETED BY:

L. K. Miller TEI.EPHONE:

609-365-7000 X507 CAUSE AND CORRF.cl'IVE ACTION 'ID PREVENT REx:::tIBPENCE High Vibration, Main Turbine Bearing No. 3, Unit Shut Down to make necessary turbine repairs.

4 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report(LER) File (NURID-0161) 5 Exhibit 1-Sane Source

MAJOR PLANT MODIFICA~S REPORT MONTH

. May, 1~8

  • DCR NO.

PRINCIPLE SYSTEM ED-0009 Liquid Waste Disposal ED-0074A Main Steam -

MS 167's ED-0146 Reactor Coolant -

13RCP ED-0169 Station Power -

SPT ED-0204 Auxiliary Annunciator ED-0206 Main Stearn -

MS 169

& 17l's.

ED-0212

~lectrical -

500kV ED-0243 Pressurizer Spray -

PS 2 & 4.

DOCKET NO.:

50-272 UNIT*=

DATE:

Salem 1

-6/9/78 COMPLETED BY:

L. K. Miller TELEPHONE: 609-365-7000 X507 SUBJECT Replace BFD Relays Install Heavy Wall Tubing Modify No. 3 Seal - Seal Ring Install Watt Transducer Revise Alarm Program Modify Control Air Piping Remove NHC Relay Replace Valve Topworks ED-0272 Main Stearn -

11MS167, 13MS167, Install Keelavite Check Valve in

& 14MS167.

Hydraulic Line ED-0297 Diesel Generator -

lB Modify Fuel Lines ED-0326

VCS -

1CV4 ED-0328

irculating Water ED-0332

~irculating Water ED-0347 Main Stearn EX-0009 Reactor Coolant -

RCP's EX-0010

irculating Water EX-0013
irculating Water MD-0133 Bleed Stearn & Header Drains OD-0052
ondenser Air Removal PD-0019A :ornponent Cooling PD-0025
VCS -

BIT

  • DESIGN CHANGE REQUEST 8-l... 7. Rl Install Valve in C.A. Line Modify Floor Grids in Waterboxes Relocated Outlet RTD's Install Test Connections Conduct Starting Current Tests Conduct Waterbox and Valve Tests Conduct Waterbox and Valve Tests Install Split Bearing in No. 12 H.D. Pump Install Low Point Drain Modify Control Air Piping for 1CC215 Relocate lSJ6 Page 5 of 16

DOCKET NO.:

50-272 MAJOR PLANT MODIFICAT~S

.REP-ORT MONTH May, ~7 8 UNIT -~1E:

DATE:

Salem Unit #1 6/9/78 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507

  • DCR NO.

10CFR50. 5 9.

SAFETY EVALUATION ED-0009 This is a change in brand of equipment and not a change in design concept.

Criteria for an unreviewed safety question are not met.

EC-0074A Modification does not downgrade any safety related equipment, aggravate any previously analyzed accident, or change the basis of any technical specification.

An unreviewed safety question is not involved.

ED-0146 There is no fundamental change to seal design or function.

The change enhances service life.

The criteria for an unreviewed safety question are not met.

ED-0169 Safety related equipment will not be affected.

ED-0204 Change does not affect safety function of system.

Relocation required to improve system performance.

Criteria for an unreviewed safety question are not met.

ED-0206 The equipment performs same function and meets all applicable requirements.

The change increases reliability.

An unreviewed safety question is not involved.

ED-0212 Safety related equipment will not be effected.

ED-0243 ED-0272 ED-0297 Replacement of valve top works with stronger parts, does not downgrade any safety related equipment, aggravate any previously analyzed accident or change the basis of any technical specification.

Installation of actuator hydraulic tubing check valves does not downgrade any safety related equipment, aggravate any previously analyzed accident, or change the basis of any technical specification.

This modification will not reduce the,rnargin of safety in any Technical Specification, cause an accident or malfunction not previously analyzed in the FSAR, nor increase the probability of occurrence or consequences of such an accident.

.. ~. DESIGN CHANGE REQUEST Page 6 of 16

MAJOR PLANT MODIFICAT~S

.REPORT MONTH May, 19 7 8

  • DCR NO.

10CFR50.59.

DOCKET NO.:

50-272 UNIT.E:

Salem #1 DATE:

6/9/78 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507 SAFETY EVALUATION ED-0326 The equipment performs the same function and meets all applic-able requirements.

The Containment Isolation function and fail safe design of valve 1CV4 is not affected by design change ED-0328 The modification of this system does not affect any presently performed safety analysis nor does it create any new hazards.

The basis of the technical specifications are not affected.

ED-0332 Safety related equipment will not be affected.

ED-0347 This design change does not affect any presently performed Safety Analysis nor does it create any new safety hazards.

The basis of the technical specifications are not affected.

System is non-safety related.

EX-0009 The performance of this test does not create any abnormal operating condition which could invalidate existing analysis or create new conditions which reduce margins of safety or violate technical specifications basis.

The performance of safety related equipment will not be affected.

EX-0010 The implementation of this test does not affect any presently performed safety analysis nor does it create any new hazards.

The basis of the technical specifications are not affected.

EX-0013 The implementation of this test does not affect any presently performed safety analysis nor does it create any new hazards.

The basis of the technical specifications are not affected.

MD-0133 Safety related equipment will not be affected.

on~oo52 This modification does not change any function of the presently designed system, nor does it create apy additional hazard.

Criteria for an unreviewed safety question are not met.

PD-0019A This design change does not change the existing function of the system.

The criteria for unreviewed safety question are not 1

involved.

PD-0025 This change necessitates relocating valve 15J6 to a more acceptable area.

The definition of an unreviewed safety question has not been met.

  • DESIGN CHANGE REQUEST

.Page 7 of 16

DOCKET NO.:

50-272

SUMMARY

OF SAFETY RELATED~INTENANCE UNIT -1E:

Salem #1 DEPARTMENT Performance DATE:

6/9/78 REPORT MONTH May, 1978 COMPLETED BY:

L. K. Miller TELEPHONE: 609-365-7000 X507 I

WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

PD-4608 1PC936G Instrument out of spec Recalibrated PD-4708 1LI931 Indication out of spec Recalibrated PD-4704 1PC937B-F Instrument out of _spec Recalibrated OD-7836 1LT529 Redundant channels do Recalibrated 1LT529 not agree.

OD-8671 Valve 1CV132 Open time out of spec.

Recalibrated valve positioner.

PD-4729 Valve 12SW58 No open indication Adjusted limit switch PD-4717 PI-936B Indication out of spec Replaced meter movement PD-4716 1PI937C Instrument out of spec Recalibrated PD-4713 PI-937A Indicator out of spec Recalibrated PD-4683 TC412E-F Fuse holder broken Replaced fuse holder

/

PD-4610 PT3450 Instrument out of Recalibrated I

spec PD-4609 11, 13 nozzle Leaking solenoids Replaced SV912 and 914 support vent fans Valves OD-8783 11,12,13, 14 Valve demand indicator Recalibrated demand AF 21 does not agree with -

indicator feed flows.

OD-8784 AF Press Over Interlocks operate at Recal. llAFP disc press ride interlock various pressures trans.

OD-8810 R.M.S. 1Rl5 Spiking Recalibrated detector Page 8 of 16

DOCKET~.:

50-272

SUMMARY

OF SAFETY RELATED~INTENANCE UNIT E:

Salem #1 DEPARTMENT Performance DATE:

6/9/78 REPORT MONTH COMPLETED BY:

L. K. Miller:*

May, 1978 TELEPHONE: 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

OD-8827 Valve 1WL12 Will not open Replaced 20X relay coil.

OD-8838 Service Wtr.

Reads f::,,p with pump out Blew out line for bubbler 16 Pump Screen of service f::,,p PD-4721 TE944A High reading.

Recalibrated PD-4743 TM412C No output change Replaced OD-8374 Tre.f Indicator Reading High @ 100%

Tref Recorder out of Rx Power calibration OD-8754 12 BAT Heater Remains energized Replaced bulbs in heater

~200°F contactor panel OD-8807 1TC944 Read 115° with all Replace TC944 contact heaters off assembly OD-8861 Service Wtr.

Screen diff. reading Blew back feeler line 15 Pump downscale OD-8883 Valve 1CH30 No open indication Rebuilt SV761

,,,.---~--.

OD-8902 TM-412C Loop 11 OTl::,,T Set Pt.

Replaced summator pegged high MD-2678 Valve 1SJ79 Valve disassembled Stroked valve Page 9 of 16 I

DOCKET NO.:

50-272 RELATED~INTENANCE UNIT a1E:

Salem #1

SUMMARY

OF SAFETY DEPARTMENT Maintenance DATE:

6/9/78 REPORT MONTH May, 1978 COMPLETED BY:

L. K. Miller TELEPHONE:

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

OD-4995 Valve 1SJ13 Packing leak Repacked valve OD-8105 Valve 1CV68 Packing leak Repacked valve OD-5844 Valve 18J908 Drain valve & line Unplugged valve plugged OD-5838 Valve 1WR70 Diaphragm leaks Replaced diaphragm OD-4996 Valve l8Jl2 Packing leak Repacked valve OD-8559 Valves 118Jl36 Packing leak Repacked valves and 137 MD-2572 Valves l8Jll7 &

Boron hardened gland Repacked valves 74 OP-260 Valve 11CV108 Packing leak Repacked valve OP-255

!Valves 11 &

Packing leak Repacked valves 128Jl4, ll8Jl5, 136 and 137 MD-0784 Pu el Handling Walkway binds Repaired walkway

/

i

/

MD-2535 Valve l8J7 Drain valve plugged Unplugged valve OD-8410

~alve 188107 Valve bonnet leaks Replaced bonnet gasket OD-3007 valve 1CV8 Valve leaks through Repaired. valve OD-3931 Valve 13SW24 Valve binding closed Repaired valve OD-7247 Valve 1CV6 Flange leak Repaired valve

  • ~,

Page 10 of 16 I

I

DOCKET *.

50-272 SUMMAJ3.Y OF SAFETY RELATED"INTENANCE UNIT E:

Salem #1 DEPARTMENT DATE:

6/9/78 Maintenance COMPLETED BY:

L. K. Miller REPORT MONTH May, 1978 TELEPHONE:

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

MD-2454 Valves 12 and Packing leak Repacked valves 13 BF23 MD-2635 PD6214 & 6215 Out of calibration Calibrated PD3399 & 3400 PD3401 & 3402 I

I MD-2636 PD-2731 Out of calibration Calibrated I

MD-2637 LD-2455 Out of calibration Calibrated LD-3601-1 OD-8848 Service Wtr.

Shear pins snapped Replace shear pins 14 Strainer OD-8774 Main Steam Gen.

Inspect for oil leaks Repaired oil leaks OP-304 MD-2686 lAl 28V Repair lAl 28VDC bat.

Replace control boards Bat. Chgr.

chgr.

MD-2691 lB __ Vital Failed during test of Replac~d fuse Fl Inverter vital bus OD-8931 Valve llSJ40 Unable to open from Replaced aux. contact control room.

OD-8926 Service Wtr.

Only runs in "INCH" Lubricated switch 11 Screen MD-2690 ID Vital Failed test of vital Replaced fuses...

Invertor bus OD-8872 11 Fan Coil Unit Low Speed Bkr.cannot Tack welded positioning be racked out gear MD-2565 Valves 1SS48 Repacking leak Repacked valves and 63 Page 11 of 16

DOCKET *.

50-272 RELATED~INTENANCE UNIT E:

Salem #1 SUMMA~Y OF SAFETY 6/9/78 DATE:

DEPARTMENT Maintenance REPORT MONTH May, 1978 COMPLETED BY:

L. K. Miller TELEPHONE:

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

I I

OD-8922 Service Wtr.

Broken shear key Replaced shear key and i

14 Strainer buttom guide feet.

I MD-2698

  1. 12 Reactor Remove 100 shims from Removed __ shims I

Coolant Pump

  1. 3 seal OD-8935 Service Water Packing leak Repacked pump I

15 Pump OD-8923 Valve lSJl Unable to open from Replaced burnt motor and control room overloads MD-2716

  1. 1 Emerg. Air Calibrate agastat Recalibrated Compressor MD-2441 Valves 1CV2, 5, Packing leaks Repacked valves 75, 79 I

MD-2707 SJ,RH,CV,SW &

Install motor Installed motor CS Motor of VA'~

MD-2675 Polar Crane Machine pinion shaft Machined shaft OD-8934 Valve 1SJ7 Line plugged Unplugged line i

I Page 12 of 16

DOCKET NO.:

50-272

SUMMARY

OF SAFETY RELATE~INTENANCE UNIT &E:

Salem #1 DEPARTMENT Maintenance DATE:

6/9/78 REPORT MONTH May, 1978 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

OD-8717 Service Wtr.

Broken shear key Replaced shear key lS Strainer OD-8745 lCCDC Deion #39 When open, ground on Pin wir~ on solenoid valve lB & lC 125VDC bus repaired wire.

clears OD-8734 Valve 11CC2 Packing leak Repacked valve OD-8732 11 Chiller Auto-Run light out Replaced CMC switch OD-8833 Valve 1RH26 No closed indication Readjusted rotor contact OD-8844 Service Wtr.

Broken shear key Replaced shear key 16 Strainer OD-8744 lA Diesel Jacket Wtr. heater Recalibrate TD-7333 and does not open TD-6464 OD-8276 Valve 11CC3 Packing leak Repacked valve OD-8815 11 Chrg. Pump Pump runs continuously Replaced #3 operator Aux. Oil Pump

/~

)

OD-8876 Boric Acid Rupture disc. blown Replaced rupture disc Evaporator OD-8735 Valve 12CC8 Packing leak Repacked valve MD-7537 Valve 12CCHX Inspect tubes Plugged 10 tubes.

OD-8814 lC Diesel Trips on overcrank Lubricated governor MD-2521 11 Reactor Inspect seals Replaced #2 and #3 seal Coolant Pump Page 13 of 16

DOCKET NO.:

50-272 RELATED~INTENANCE UNIT -E: Salem #1 SUMMA.RY OF SAFETY 6/9/78 DATE:

DEPARTMENT Maintenance COMPLETED BY:

L. K. Miller REPORT MONTH May, 1978 TELEPHONE:

WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

QD..,.8619 Valve 12CV163 Ruptured diaphragm.

Replaced diaphragm OD-8556 Valve 11MS2 Packing leak Repacked Valve OD-5148 11 & 12 RH29, 3( Valves leak through Repaired valve and 44 12RH16 1RH26 OP-257 Valves 12SJ21 Packing leak Repacked valves and 26 11 and 13 SJ21 OP-258 Valves 11, 12 Packing 1eak Repacked valves and 14 SJ23 OP-259 Valve 12 SJ266 Packing leak Repacked valve.

OP-262 Valve 1SJ312 Packing leak Repacked valve MD-2570 Valve 1SJ4 Packing leak Repacked valve MD-1654 Valve 12RC20 Valve leaks through Repacked valve

____.-/~

/

OD-8636 Valves 1SJ4 & 5 Valves leak through Increased Torque Switch setting OP-281 Valve 11CV160 Inspect for foreign Removed center piece of a material diaphragm from cage OD-8708 Valve 11SW122 Packing leak Repacked valve OD-8771 Line between Line plugged Unplugged line MD-2659 Valves 11SJ136 Valves leak through Tightened packing gland.

Page 14 of 16

5/1-31 MONTHLY OPERATING

SUMMARY

SALEM I

. MAY, 1978 The unit was out the entire month due to the continuation of outage for the purpose of making turbine repairs.

Estimated date of startup is June 17, 1978.

Page 15 of 16

. ~

.REFUELING INFORMATION DOCKET NO.:

50-272 UNIT: Salem No. 1 DATE:

~~~--~-----

COMPLETED BY: L.K. Miller TELEPHONE: 609-365-7000 Ext. 507 MONTH:~ ___

M.._;;.;;a.y.,___,.;;;1~9-7_8:;.._ ______________ ~

1.

Refueling information.* has changed from last month:

2.
3.

.4.

YES NO X

Scheduled date of next refueling:

April 1, 1979 Scheduled date for restart following refueling:

May 29, 1979 A.

  • Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO-DATE May, 1978 B.

Has the reload fuel design been reviewed by the Station Operating Review Cornmi ttee?

YES NO X ---

If no, when is it scheduled?

January, 1979

5.

Scheduled date(s) for submitting proposed licensing action:

February, 1979 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:

1,170

~----:.-..~~--....,....------~~

9.

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

April,. 1982 Page 16 of 16

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