ML18078A503

From kanterella
Revision as of 18:31, 17 June 2019 by StriderTol (talk | contribs) (Created page by program invented by StriderTol)
Jump to navigation Jump to search
Monthly Oper Rept for Nov 1978
ML18078A503
Person / Time
Site: Salem PSEG icon.png
Issue date: 12/11/1978
From: Miller L
Public Service Enterprise Group
To:
Shared Package
ML18078A502 List:
References
NUDOCS 7812150244
Download: ML18078A503 (13)


Text

MO NIH November 1978 DAY AVERAGE DAILY POWER LEVEL I 2 3 4 5 6 7 8 9 10 11 12 13 14 15. 16 Pg. 2 of 14 8.1-7.Rl (MWe-NET) 0 0 0 0 0 0 0 0 0 0 0 0 112 556 752 .. 676 DJCKET NO. 50-272 UN IT Salem # 1 DATE December 11, 1978 CQvfPLETED BY L. K. Miller TELEPHONE 609-365-7000 X507 DAY AVERAGE DAILY Prnff.R LEVEL 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 (j>Il'iE-NET) . .,-__ I 984 1,102 995 965 978 1,097 1,105 1,120 1,036 1,101 191 0 0 406 ---

i.* TJnit Nane:. Salem #1 Notes: .. 2. P.eport:l.nq Period:_*

_N_o_vernbe..;..*

__ r_l_9_7_8

______ _ 3. . r.; censed 'llleml Pa..er (M'it) :

_______ _ 4. NaIIep.late Ra.t:!.nq (GJ:Css. me1: ____ 1;:;.;-l:;.;;-3;;.;;:5::..__

_____ _ s. Cesign* Electrical..

Rating: (Net: l-lie): 1090 6. . Maxlmlm* Dependable Capa.c:i:l:y (Gross. l-lie) : 1124 1. Ma..vinnm-Cependable*

capacity* (Net !-H!): -,-, .,,..io.,.7""'9-_:--.

--*

50-272 CATE*: December 11, 19 7 8 SY: L. K. Miller 609-365-7000 X507 a. If Changes OccJr ill Capacity Ra.tings <Item* Ntm:er* 3 Throa;h 7} SJ.nee Last P.eport,.

Giw Reason: NONE 9. Power Leval 'lb Mlich

  • If Aey* (Net l-lie) :.
10. Rea.sons For Restricti.cns,.

u* ________ N_O_NE ____ -____________

_ ll. Ei:lurs. In P.eportinq Period 12.. Numer Of Hours Reactor Was CritiCal

  • l3.
  • Reactor Reserve Shutdown
14. aours Generator On-Line, . 15. unit Reserve Shutdown Hours l6. . Gross 'IheJ:mal Energy-Generated (Mm) 17. Gross Electtical EMrgy Generated cz.HI) 18. Net Generated(!-H!)*
19. crnit.ServiceFactor*

20 *. Unit\AvailahHity

_Factor . 21. Unit capacity Factor (Using' MCC Net) Unit capa.city Factor (Us:lnq CER Net) . 720 377.2 0.0 o.o 1,002,926

'331,770 *311,316 49.8 49.8 40.l 39.7 23. Unit :E'Orced*

Outage Rate 50

  • 2 Year to Date Qm1lat'ive 8,016 12,457 4 I 557
  • 0. 7I100
  • 2
0. 0 0.0 6,774.6 --------. 0.0 0.0 12,714,590 19,409,810 4,251,130 6,437,440 4,020,141 6,078,359 54.2 54.4 54.2 54.4 -------____ ._4;;.,;6;,,,,;.

__ 5 ___ __._..._4.;;,,,;5;..;

  • ..;..2 __ 46.0 44.8 -------45.8 . 37.3 -------24. Sht.tt:dcwns Scheduled Oller NeXt: 6 (Type, Date, arid Duration 0£ Each) : Unit Refueling 3/31/79:-6/23/79 25.
  • If Shut D::lwn At Ecd of. Report Period! Estimated oate .of* Startup: . 26. emits rn* Test StatlJs(Ptior to a-l-7.R2 Pg.;3 of 14 Forecast* . 9/30/76 11/01/76 12/20/76 Achieved 12/11/76 12/25/76 6/30/77 NO. .78-252 78-253 78-255 78-257 78-261 78-268 78-277 DATE 10/21/78 11/13/78 11/13/78 11/14/78 11/15/78 11/19/78 11/27/78 Page 4 Of 14 B-1-7.Rl TYPE 1 F F F F F F F OORATION (HOURS) 290.7 A 3.5 A 0.0 B 0.0 B o.o B 0.0 B 67.1 A UNIT SllUTIXMNS 1\ND PCMER REDUCl'IONS REPORI' MJNrH Noveniber METHOD I OF SHUIT'ING LicENSE SYS'J.'EM a:MPONEm' IXMN EVENT CODE4 CODES REAC'IDR REPORT # 4B ----CB PUMP XX 3 --HI HTEXCH
  • 4A ----EB zzzzzz 4A ----:IE zzzzzz 4A ----IE zzzzzz. -4A ----HH FILTER 3 ----EB GENERA l I " i I I DOCKET NO.

UNIT 'NAME: _S_a_l_em

__

___ _ DATE: December 11, 1978 COMPLETED BY: L.K. Miller TELEPHONE:

609-365-7000 X507 CAUSE AND CORRECTIVE ACTION 'ID PREVENT ROCURRENCE Failure of Seals on 13 RCP #14 Steam Generator High Level Safe-Guard Errergency Control Flux Mapping Surveillance Flux Mapping Surveillance

  1. 11 Steam Generator Feed Pump Strainer lB Vital Instrurrent Inverter Failure -* '

. MAJOR PLANT . 'REPORT MONTH November, 197-3 *DCR NO. PRINCIPLE SYSTEM PD-0128 s. G. Feed (115VAC)

  • DESIGN CHANGE REQUEST 8-1-7.Rl & Cond. DOCKET NO.: 50-272 NAME: Salem #1 DATE: December 11, 1978 COMPLETED TELEPHONE:

609-365-7000 x 507 SUBJECT Relocate 115VAC Governor Control Power Supply Page 5 of 14

.MAJOR PLANT REPORT MONTH November, 197-8 *DCR NO. lOCFRS0.59.

PD-0128 This design change does not operation.

It will increase

  • DESIGN CH_Z\NGE REQUEST DOCKET NO.: 50-272 UN-NAME: Salem #1 DATE: December 11, 1978 COMPLETED BY: L. K. Miller TELEPHONE:

609-365-7000 x 507 SAFETY EVALUATION functionall change the system system reliability.

Page 6 of 14 DOCKET NO.: 50-272 Sylv'.!MAR:l OF SAFETY RELATE.INTENANCE DEP A,RT:V.i.ENT Maintenance/Perforrnahce REPORT MONTH November 1978 UNIT ,.ME: Salem #1 =TE: December 11, 1978 L. K. Miller 1 j I t-' I ! WOR...1< ORDER NO. MD-3206 OD-10697 OP-0495 OP-0479 EQUIPMENT I FAILURE 100' Elev.* Air Ibck Worn Inner Door Bearings.

12 Safety Injection Internally Damaged. Pump 11 & 12 Containment Low Flow., Sump Pumps !Valve _lONT031 Install Valve per DCR PD-0125. CORRECTIVE ACTION Replaced Bearings.

Replaced Pump. Cleaned Suction Strainers.

Installed Valve. ---**-1c12sv--Bat.*tel:y Rcx:>m rnOperable.

Repaired Centrifical Switch. OD-10576 PD-5141 OD-10742 OD-10813 OD-10697 OD-10732 *OD.,...10865 OD-10612 Page 7 of 14 8-1-7.Rl Verit Fan. Kralve 12SW092 tRMS 1R13E !Valve 10CV018 Valve 10PR002 13 Service Water Pump. 14 Service Water Pump Service Water Pump Strainer.

-

Not Close. Erroneous Alarm. No Open Indication.

Valve Does Not Close. Motor Bearing Cooler Malfunctioning.

Replaced Diaphragm.

Replaced Bistable Drawer. Adjusted Limit Switch. Replaced SV-760. Replaced Cooler. High Temperature Alarm From Replaced Cooler Coil and Upper. MotGr Bearing Cooler. Bearings.

Shear Pin Broken. Replaced Distributor Barrel Seals, & Shear Key. [4 Steam Generator Packing Leaking on Pressure Replaced Valve. Tap Valve.

DOCKET NO.: . 50-272 OF SF..FETY DEF j\RTMENT Maintenance/Performance REPORT MONTH November 1978 UNIT 1* .. M.E;_S_a_l_ern

__ #_l _______ _ TE: December 11, 1978 L. K. Miller ' i r i WORK ORDER NO. OD-10853 PD-5182 OD-10743 OP-0437 OD-10864 OD-10845 OD-10147 OD-10895 OD-10921 OD-10670 ' MD-3225 PD-5175 PD-5205 OD-10481 Page 8 of 14 8-1-7.Rl EQUIPMENT Valve 10CV056 Channel N42 NIS 1LC500 B/J Valve 10CV078 Valve 11SW024 Valve 10WL099 Channel lC $ *. El. C. Valve llMS171 Valve 14BF019 Valve 14SW065 Channel lC S.E.C. Solenoid Valve SV398. Channel N43 NIS 15 Service Water Purrp. TELEPHONE:

609-365-7000 X507 FAILURE DESCrtIPTION CORREC:TIVE

.?.CT ION I r Packing Leak. Repacked Valve. I Out Of Spec. Adjusted Isolation A:rrp Gains. Level Deviation Alann ... Replaced Capacitors.

Not Accuated.

Valve Leaking. Seal Welded Diaphragm.

Leaks Through. Replaced Diaphragm.

Does Not Close . Repaired Solenoid Valve. . -Alarm Will Not Reset. Replaced Logic Card. Petcock Valve is Leaking. Replaced Petcock Valve. -.. Bezel Indicator in Control Equalized Transmitters.

Room swinging.

Flange Leaks. Welded Flange. Will Not Reset. Replaced Printed CircUit Cards. Rework Solenoid.

Rebuilt Solenoid Valve. Upper Flux Recorder Out of Adjusted Isolation Anp. Spec. Flex Hose Leak. Replaced with Copper Tubing.

OF S?..FETY

--DOCKET NO. :

TJNIT 1Ti1..ME:

Salem #1 .TE: __ D_e_c_e_mb_e_r

__

' COM.PLETED BY:_L_._K_.

__ Mi_'_l_le_r

_______ _ DEP A.RT.MENT Maintenance/Perfgrrrance REPORT MONTH November 1978 TELEPHONE:

609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION I

ACTION I NO. I i OP-519 Containment Fan Perform Work I.A.W. DCR Completed DCR. Coil Units. lEC-0448.

MD-3221 125VDC lB BUS F'aulty

  • Ground.* Tightened Loose Brush Holder. OD-11053 Valve 13SW167 Handwheel Cannnot Be Locked. Replaced Set Screw. OD-11068 Valve 10CV057 Reach Rod Inoperable.

Replaced Pin. OD-10657 1B Diesel Ruptured Jacket Water --Replace Both Heaters, Repaired Heater & Shorted Pre-Lube Motor & Tenp. Controller.

Oil Pump Motor. OD-11009 !Valves 12 & 14 MS168 Leaking. Furrnanited. . -.. i-OD-11010 fJalve 12MS131 Leaking. Furrnanited.

' -. MD-3246 Valve 11 HW211 Leaking. Repacked Valve. OD-11030 valve 10CV059 Will Not Close. Replaced Stem & Handwheel.

' MD-3108 valve 12SW025 Leaking. Weld Repair. l I RE-196 il.FA0118 Out of Spec. Calibrated.

I OD-10898 LLAS424IC Channel D Level Indicator Calibrated Indicator.

Out of Spec. OD-10740 llFIT157A Lo Flow Indicator Pegged Cleaned Indicator.

High. I OD-10571 il.FT416 Several Bistable Replaced Bistable.

i I SlJMMARY OF RELATE.l\INTE?:JANCE DEP ]?.RTMENT Maintenance/Perfo.r:rnance

.... __

UNIT IME: Salem #1. _TE: December 11, 1978 CO.MYLETED BY: L. K. Miller REPORT MONTH November 1978 TELEPHONE:

609-365-7000 X507 ORDER I EQUIPMENT j

ACTION WOR..1< _,r.. _, __ l -NO. I PD-5217 1LC527C Corrparator Out of Spec. I Replaced Comparator.

PD-5218 1 Air Particulate Seized Pump. Replaced Pump. Detector.

PD-5231 Channel N41 NIS Functional Testing of NM-Adjusted Isolation Amps. 306 & NM307 OD-11129 *.1LT460 Reading 10% High.* Recalibrated.

OD-11114 lB Vital Instrurrent Visible Srroke. Replaced Resistor R3 & Output: Inverter.

Transformer 781118. . PD-5232 _l'IC530A/B

  • Out of Spec
  • calibrated.

l PD:-:5224

.IBS539A OD-11130 *Page 10 of 14 8-1-7.:Rl lL Service Water Pump. . -Out of Spec. *Adjusted.

Upper Bearing Motor Cooler Replace Pipe Leaking. I I --*

11-1 thru 11-11 11-12 11-13 11-14 11-15 11-16 SALEM UNIT I OPERATING

SUMMARY

NOVEMBER, 1978 The unit has been shutdown due to inspection and replacement of #13 RCP No. l Seal and routine plant maintenance activities.

The Reactor was critical at 1750. Two Reactor trips occured before 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> due to low and high steam generator water levels. The first trip occured at 2105. The unit then went critical at 2225 and tripped at 2340. The Reactor was critical at 0028 and tripped at 0251 from 12% power due to a high steam generator water level. Reactor was critical at 0340 and on line at 0621. Power increased to 15% by 0700. A load increase was commenced at 1525 at 3% per hour. At 2400, the unit load was 44%. Load is being increased at 3% per hour. At 0800, the unit load was 63%. Unit load was increased to 65% by 0900 and maintained at 65%.until 1130. Load was increased at 3% per hour to 70% by 1320. Load was held at 70% while maintenance was being performed on the circulating water pumps.for the remainder of the day. Load is being held at 70% due to maintenance activities on the traveling screens of the circulating water system. At 0350, the load was reduced to 61% due to a decrease in vacuum in th main condenser.

Vacuum was restored and load increased to 70% by 0525. Load was held at 70% for the remainder of the day.for maintenance activities ori the circulating water system and in preparation of three>>flux*

maps to be taken for incore/excore calibration data. Unit load is being held at 70% while flux maps are being taken and plant conditions for the flux maps are Page 11 of 14 11-16 (can't) 11-17 11-18 11-19 11-20 11-21 thru 11-23

  • established.

1

  • The f ux mapping was completed by 0915 and the axial flux restored with+/-n:the target band by 1050. Load increase was commenced at 1105 from 71%, but limited due to axial flux difference considerations.

At 1830, load was increased at 2% per hour. The unit load was 84.8% at 2400. Unit load is being increased but limited due to axial flux difference considerations for the previous .day's testing. By 0800, unit load was 94%. At 1230, unit load reached 98% and remained greater than 98% for the remainder of the day. Unit load remained greater than 98% until 2025 when a load reduction was made to 95.5%. The load reduction was made, after 13B Circulator had an emergency trip, in order to limit condenser back pressure.

Unit load was restored to greater than 98% by 2155 and remained so for the remainder of the day. Unit load was maintained at greater than 99% until 1330. A unit load reduction was commenced at 1300 at 3% per hour to allow cleaning of 11 & 12 Generator Feedwater Pump Suction Strainers.

At 2400, unit load was 62%. Unit load is being reduced to approximately 50% to allow *the cleaning of #11 & #12 Steam Generator Feedwater Pump Suction Strainers.

Unit load was reduced to 52.'5% by 0200 and is *being held while the steam generator feedwater pump suction strainers are being cleaned. Load increase commenced at 0400 at 3% per hour. By 1705, the unit load was 98%oand remained at 98% for the remainder of the day. Unit load remained greater than 99%. Page 12 of 14

, 11-24 11-25 thru 11-26. 11-27 11-28 11-29 11-30 *

  • Unit load was greater than 99% until 0640 when load was reduced to 98% due to axial flux difference alarm. The instrumentation was corrected by the Performance Department and load increased to greater than 99% by 0905. Unit load remained greater than 99% for the remainder of the day. Unit load remained greater than 98%. Unit load remained greater than 99% until 0445 when the Reactor tripped after the failure of Vital Bus lB Inverter.

Unit remained shutdown for the remainder of the day. Unit shutdown for maintenance.

The Reactor went critical at 1458, .. and on line at 2350. Load was held below 10% for the remainder of the day. Load increase above 10% commenced at 0010 at a rate of 3% per hour. At 1030, load was stabilized at approximately 46%. At 1520, load increased to approximately 52%. At 2130, a load increase was commenced at 3% per hour. By 2400, the unit load was 59%. Page 13 of 14

..

  • INFORMATIO
  • DOCKET NO.: 5 o-2 12 UNIT: Salem #1 DATE: December 11, 1978 COMPLETED BY: L. K. Miller TELEPHONE:

609-365-7000 Ext. 507 MONTH: November, 1978

l. Refueling information has changed from last month: YES X NO ---2. Scheduled date of next refueling:

March. 31;. 1979 3 *. Scheduled date for restart: following.

refueling:

June 23, 1979 4. A.. Will Technical Specification changes or other license

  • amendments be-required?

YES** NO -----NOT" DETERMINED TO-DATE November, 1978 B. Has the reload*: fuel design been reviewed by the Station Operating Review Committee?

YES NO X ---If no, when is it scheduled?

February 1979 5. Scheduled date(s) for submitting*

proposed licensing action: March, 1979 if reguired.

6.. Importan.t licensing consid13rations associated with refueling:

NONE 7. Number of Fuel Assemblies:

A. B. In-Core In Spent Fuel Storage* 8. Present licensed spent fuel storage capacity:

1 0 264 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:

Page 14 of 14 8-l-7.R4 April, 1982