ML19030A335

Submit Monthly Operating Report for the Month of March 1978 for Salem No. 1

ML19030A335
Person / Time
Site:	Salem
Issue date:	04/10/1978
From:	Heller H Public Service Electric & Gas Co
To:	NRC/IE, Office of Nuclear Reactor Regulation
References
Download: ML19030A335 (14)

Text

PS~G*

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 Conunission 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 Sununary of Safety Related Maintenance Operating SUJ.llI!lary Refueling Information Sincerely yours,

~10~

H. ~  ;:ller Manager - Salem Generating Station JMZ: jcm cc: Mr. Boyce H. Grier Director of U. S. NRC Off ice of Inspection and Enforcement Region I 631 Park Avenue King of P:::-ussia,. PA 19406 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 1

r------ -.

Enc. 7::;: 1. 10(1():37 Pageh~ ro'f2riJJ~ People 8-1-7. R4 95-2189 (2M) 10-76

OPERATING DATA REE'ORI' r::cc:-<ET NJ.: _ _50-272 _ _ _ _ _ _ __

DATE : __;;.Ap=r=i::.l_,1::.,:0;:..i,~1""'9_,_7.:=.8_ _

COMPLETED BY:_J_._M_._Z_up-=--k_o....;,_J_r_._ _

TELEPHONE: 609-365-7000 X507 OPERATING STATUS 1.

2.

unit Narre:

Reporting Pericd:

Salem No. 1 March,.;..._1978 ~

Notes:

3. Licensed Thei:nal ~r (MVI:): _;;;.3;;;.3.;;.3.;;.8----'----

4. Narreplate Rating (Gross MWe): _1_1_3_5_______

5. Design Electrical Rating met MWel: _l_0_9_o_____

6. Maximum Dependable Capacity (Gross I-Me):

• 1124

7.  !>l.axixm.lm Depe.11dable Capacity (Net r.we) : _---::-1=0:7:9~======

8. If Changes Occur in Capacity Ratings (Item:; Number 3 Through 7) Since Last Rei_:ort, Give Reason:

None None

9. Power Level To Which Restricted, If Any (Net ~e): - - - - - - - - - - - - - - - - - - - - - -

10. Reasons For Restrictions, If Any:-----------------------------

This 1'bnth Year to Date Cumulative 744 2160 6601

11. Hours In Rei_:orting Pericd.

12. Number Of Hours Reactor Was Critical 354.2 1522.7 4065.9

13. Reactor Reserve Shut:Ccwn S:iurs 0 0 0

14. Hours Generator On-Line 352.6 1460.l 3890.7

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Th.ennal Energy Generated (MWH) 1,080,163 4,505,479 11,200,699

17. Gross Electrical Energy Generated (MWH) JZ4,Q9Q 1,548£500 3,734,810

18. Net Elect..-::ical Energy Generated (MWH) 354!613 1!475,405 3,715,333

19. Unit service Factor 47.4 67.6 58.9

20. Unit Availability Factor 47.4 67.6 58.9

21. Unit Capacity Factor (Using MCC Net) 44.2 63.3 52.1

22. Unit capacity Factor (Using DER Net) 43.:Z 62.7 51.6

23. Unit Forced outage Rate 52.6 32.4 21.3

24. Shutda.oms Scheduled over Next 6 t-mths (Type, Date, and Duration of Each):

None

25. If Shut ~ At End of P.ei_:ort Pericd~ Esti.TTiated Date of Startup: _ _ _ _5._;./_2_1._;./_7_8__________

26. Units In Test Status (Prior to Cormercial Operation):

Forecast Achieved INITIAL CRITICALITY 9/30/76 12/11/76 INITIAL ELECTRICI'IY 11/1/76 12/25/76 8-l-7.R2 CCMMEFCIAL OPEFATION 12/20/76 6/30/77 Page 2 of 14

e AVERAGE DAILY UNIT POWER LEVEL e

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 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) (MWE-NET) 1116 0 1 17 1115 0 2 18 3 1057 19 0 4 758 20 0 5 1042 21 0 c-,. ~

409 0

'C 6 t **** 22 7 835 23 0 8 1090 24 0 9 1054 25 0 1117 0 10 26 1115 0 11 27 1103 0 12 28 1023 0 13 29 14 1059 30 0 15* 1010 31 0 16 9

( ,.

~- . . ,

8.1-7.Rl.

Page 3 of 14

UNIT SHUTIXMNS AND IUVER REDUCTIONS DOCKET NO.: 5 o- 272

~-------~

REPORT MJNI'H March, 1978 UNIT :NAME: Salem No. 1 DATE: April 10, 1978 COMPLETED 13Y: J.M. Zupko, Jr.

TELEPHONE: 609-365-7000 X507 MIIDIOD OF OORATION SHlTITING LICENSE SYSTEM m1PONENT CAUSE AND mRRECrIVE NO. DATE TYPE! (HOURS) RF./\SON2 lXMN EVENT moE4 CXIDES ACTION 'ID REACIDR REPORT # PREVENI' REUJRRENCE 78-32 3-3-78 F 0 A 4 (A) -- HH Filter Clean Cond. and Sbn.Gen. Feed Pump Suction Strainers.

78-33 3-5-78 F 0 A 4 (A) -- HA Instru Frozen feeler line on turbine impulse pressure channel.

78-34 3-6-78 F 10.9 G 3 -- HA BBB BBB Turbine - Reactor Trip caused by per-sonnel error during routine trouble-shoot~of turbine alann .. and trip circui

• 78-35 3-8-78 F 0 A 4 (A) -- HH Filter Clean 11, 12, 13 Cond.Pump Suction Strainers.

78-36 3-12-78 '.F 0 B 4 (A) -- HA BBB BBB Turbine valve test.

78-37 3-13-78 F 0 A 4 (A) -- HH Filter Clean 11 Cond Pump Suction Strainer.

78-38 3-13-78 F 0 A 4 (A) -- HH Filter Clean 11 Cond Pump Suction Strainer.

1 2 3 4 5 F: Forced Reason: M'!thod: Exhibit G - Instructions Exhibit 1-Sarre S: Scheduled A-Equipment Failure (Explain) I-Manual for Preparation of Data Source B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File D--Regulatory Restriction 4-0ther (Explain) (NUREG-0161)

E-Operator Training & License Examination F-Administrative 8-l-7.R2 G-Operational Error(Explain) NCYI'ES: A. load Reduction II-Other (Explain) B. Continuation of previous outage.

Page 4 of 14

UNIT SII\J'l'CO'lNS rum PO'JER REDUCrlONS 50-272 DOCKET NO.: ~~~~~~~-

REPORT MJN'l'll March / 19 7 8 UN IT *NAME: Salem No. 1 DATE: April 10, 1978 COMPLETED BY: J.M. Zupko, Jr.

'l'ELEPllONE: 609-365-7000 X50_7 MITTllOD OF DURATION SllU'ITING LICENSE SYSTEM a:MPONENr CAUSE AND CORRECT IVE NO. DATE 1 RE1\SON2 TYPE (HOURS) IXH1 EVENT CODE4 CODES ACfION 'ID REACIDR REPORT II PREVENT 78-39 3_;;14-78 F 0 A 4(A) -- HA Turbin High vibration, Main Turbine Bearing No. 3.

78-40 3-15-78 F 380.5 A 1 -- HA Turbin .. High vibration, Main Turbine Bearing No. 3. Unit shut-down to make nee-essary turbine repairs.

8-1-7 .R2 Page 5 of 14

DOCKET NO.: 50-272

.MAJOR PLANT MODIFIC~ONS Salem #1 UNI-AME:

REPORT MONTH March, 1978 DATE: April 10, 1978 COMPLETED BY: J.M. Zupko, Jr.

TELEPHONE: 609-365-7000 X507

• DCR NO. PRINCIPLE SYSTEM SUBJECT ED-0051 Computer Inverter Replace Power Supply ED-0077 Heating Steam Add Atmospheric Vent to Condensate Receiver.

ED-0124 Safety Injection Stiffen Baseplate on No. 12 S.I. Pump Motor ED-0129 Part Length Rods Remove Annunciator D241 ED-0138 Plumbing Add Float Switch Alarm in Relay Room Pipe Enclosure.

OD-0010 Auxiliary Alarm Change State of Sampling System Valve Alarm.

Pg.6 of 14

• DESIGN CHANGE REQUEST R-1-7 Pl

DOCKET NO.: 50-272

.MAJOR PLANT MODIFIC~NS UNI~AME: Salem #1

. REPORT. MONTH March, 1978 DATE: April 10, 1978 COMPLETED BY:~__ J_._M_.__z_u_p_k_o__1__J_r_._

TELEPHONE: ____

6_0_9_-_3_6_s_-_7_o_o_o__

x_s_o7

• DCR NO. 10CFRSO. 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.

ED-0051 Safety related equipment will not be affected.

ED-0077 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.

ED-0124 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.

ED-0129 Safety related equipment will not be affected.

ED-0138 This design change does not in any way alter the function of the pipe enclosure. An unreviewed safety question is not involved.

OD-0010 Safety related equipment will not be affected.

Pg.7 of 14

• DESIGN CHANGE REQUEST

DOCKET NO.: 50-272

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

SUMMARY

OF SAFETY RELAT~INTENANCE UN IT . E : ___s_a_l_e_m---"#'--1_ _ _ _ __

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

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 #13 Chiller Check temperature Verified Controller set-Temp.Controller control. point.

PD-4545 Valves 12SW92 & Re stroke valves. Restroked valves.

12SW93.

OD-8309 #13 Aux. F.W. Disch.p,ress. i'ndica- Replaced transmitter power Pump. tion n'6t working. switch.

OD-8231 N.I.S. N-47 Redundant *iecorder 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 capaci t6:ts * &

& 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.

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

of spec.

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

DOCKET NO.: 50-272 UN IT . E : _ _s_a_l_e_m_#_l_-_ _ _ _ __

SUMMARY

OF SAFETY RELATaMAINTENANCE DEPARTMENT Performance DATE: __A_.._p~r~i=l;__:;l~0~,,:-..:1~9:;_.;...7~8---

COMPLETED BY: J.M. Zupko, Jr.

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

OD-8479 2 8 Volt DC Bus Ground on 2 8 VDC Bus.. Repaired grounded relay.

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

PD-4612 Module lFC-435 Comparator out of spec Recalibrated.

on functional test.

PD-4559 11 Stm. Gen. Operation of speed Replaced operating station Feed Pump. *control incorrect.

PD-4316 13 Fan Coil Check out alarm. Verified alarm.

Unit.

OD-8497 ContainmAnt Redundant channels do: Recalibarated Transmitter Channel I not agree. PT948D.

Press.

Pg. 9 of 14 8-1-7.Rl

DOCKET NO.: 50-272

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

SUMMARY

OF SAFETY RELAT~MAINTENANCE UN I T~E=~~S_a~l_em~_#_l~~~~~~

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

TELEPHONE: 609-365-7000 X507

'*I 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.

Containment ed roller.

Air Lock

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

Snubber. leaking.

OD-8439 1A28V DC Bus Ground on lA 28VDC Bus Repaired pin on lamp cir-::c cuit .

OD-6054 #12 Waste Gas Motor appears burnt Installed new motor.

Comp. out.

MD-2517 Valve 12 *& 1.4 Packing leak. ~epacked valves.

MS168 MD-2526 Valve 12MS199 Packing leak. Repacked valve.

OD-8307 Valve 11MS18 Grease plug leaking. Welded grease plug in body MD-2571 Valve 1SJ12 & Packing leaks. Repacked valves.

1SJ13.

OD-8793 Boric Acid Evap. condenser leak- Plugged vent cond. tube.

ing.

OD-8601 lA Diesel No alarm indication Replaced fuse in Annuncia-on local annunciator tor Panel.

local panel.

OD-8589 15 Water Pump Packing leak. Repacked pump.

Pg. 10 of 14 8-1-7.Rl

50-272

~

SUMMARY

OF SAFETY RELAT~MAINTENANCE UNIT~E:~_s_a_l_e_m~#_l~~~~~~~

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

REPORT MONTH March, 1978 TELEPHONE: 609-365-7000 X507

/ '

WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRECTIVE ACTION NO.

OD-8595 15 Service Water Strainer shaft packing Repacked strainer.

Pump-Strainer. leak.

MD-2527 11 Component Repair tube leaks. Plugged leaking Hx. Tubes.

Cooling Hx.

OD-8777 Valves 13RC16, Packing leaks. Repacked valves.

17, 18.

t Page 11 of 14 8-1-7.Rl

4t MONTHLY OPERATING SALEM I MARCH, 1978 SUMMA~Y

• 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.

4t 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

4

• REFUELING INFORMATION

• DOCKET NO. : 50-272 UN IT: Salem No. 1 DATE: April 10, 1978 COMPLETED BY: J. M. Zupko, Jr.

TELEPHONE: 609-365-7000 X507 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 Review Committee? YES NO X If no, when is it scheduled? N;,.;.;o;...;Vi;...;:ernber=c=~'-=19::;..7"-'8'°--_ _ _ _ _ _ _ _ _ _ __

5. Scheduled date(s) for submitting proposed licensing action:

December, 1978 if reqµired.

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