ML18078A503

Monthly Oper Rept for Nov 1978

ML18078A503
Person / Time
Site:	Salem
Issue date:	12/11/1978
From:	Miller L Public Service Enterprise Group
To:
Shared Package
ML18078A502	List: ML18078A501 ML18078A503
References
NUDOCS 7812150244
Download: ML18078A503 (13)

Text

DJCKET NO. 50-272

~~~~~~~~-

UN IT Salem # 1 DATE December 11, 1978 CQvfPLETED BY L. K. Miller TELEPHONE 609-365-7000 X507 MONIH November 1978 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY Prnff.R LEVEL (MWe-NET) (j>Il'iE-NET)

I 0 17 984 2 0 18 1,102 3 0 19 995 4 0 20 965 5 0 21 978 6 0 22 1,097 7 0 23 1,105 8 0 24 1,120 0 25 1,036 9

0 1,101 10 26 11 0 27 191 12 0 28 0 13 112 29 0 14 556 30 406

15. 752 .. 31 - - -

676 16 I

Pg. 2 of 14 8.1-7.Rl

~ID.: :__...;..;.....=~-.....,,....,,.--,,.~

50-272 CATE*: December 11, 19 7 8

~ SY: L. K. Miller

~: 609-365-7000 X507 i.* TJnit Nane:. Salem #1 Notes: ..

_ _r_l_9_7_8_ _ _ _ _ __

2. P.eport:l.nq Period:_*_N_o_vernbe..;..*

3. . r.; censed 'llleml Pa..er (M'it) : _3~3_3_8_______ _

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-_:--.- -

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 * ~cted, If Aey* (Net l-lie) :. *--..::.:N~ONE=-----------------

10. Rea.sons For Restricti.cns,. u* ~ ________N_O_NE _ _ _ _- _ _ _ _ _ _ _ _ _ _ _ __

Year to Date Qm1lat'ive 720 8,016 12,457 ll. Ei:lurs. In P.eportinq Period 12.. Numer Of Hours Reactor Was CritiCal 377.2 4 I 557

• 0. 7I100

• 2

---

.,..-~-

• l3.

• Reactor Reserve Shutdown ~urs 0.0 0. 0 0.0 aours Generator On-Line, *4,344~~P. 6,774.6 14.

. 15. unit Reserve Shutdown Hours o.o . 0.0 -------- 0.0 l6. . Gross 'IheJ:mal Energy- Generated (Mm) 1,002,926 12,714,590 19,409,810

17. Gross Electtical EMrgy Generated cz.HI) '331,770 4,251,130 6,437,440

18. Net Electrical~ Generated(!-H!)* *311,316 4,020,141 6,078,359

19. crnit.ServiceFactor* 49.8 54.2 54.4 49.8 54.2 54.4 20 *. Unit\AvailahHity _Factor

21. Unit capacity Factor (Using' MCC Net) 40.l -------

_ _ _ _._4;;.,;6;,, ,;.__5_____._..._4.;;,,,;5;..;*. ;. 2__

22~ Unit capa.city Factor (Us:lnq CER Net) . 39.7 50

• 2 46.0 45.8 . ------- 44.8 37.3 23.

24.

Unit :E'Orced* Outage Rate Sht.tt:dcwns Scheduled Oller NeXt: 6 ~ths (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 Camercial,~tion):

Forecast* Achieved

. 9/30/76 12/11/76 11/01/76 12/25/76 a-l-7.R2 Pg.;3 of 14 12/20/76 6/30/77

UNIT SllUTIXMNS 1\ND PCMER REDUCl'IONS DOCKET NO. =~5~0~--2_._72~-----

REPORI' MJNrH Noveniber UNIT 'NAME: _S_a_l_em

__~#_l_ _ __

DATE: December 11, 1978 COMPLETED BY: L.K. Miller TELEPHONE: 609-365-7000 X507 I

METHOD OF OORATION SHUIT'ING LicENSE SYS'J.'EM a:MPONEm' CAUSE AND CORRECTIVE NO. DATE TYPE1 (HOURS) ~ IXMN EVENT CODE4 CODES ACTION 'ID REAC'IDR REPORT # PREVENT ROCURRENCE

.78-252 10/21/78 F 290.7 A 4B - - - - CB PUMP XX Failure of Seals on 13 RCP 78-253 11/13/78 F 3.5 A 3 - - HI HTEXCH * #14 Steam Generator High Level 78-255 11/13/78 F 0.0 B 4A - - - - EB zzzzzz Safe-Guard Errergency Control 78-257 11/14/78 F 0.0 B 4A - - - - :IE zzzzzz Flux Mapping Surveillance 78-261 11/15/78 F o.o B 4A - - -

~

- IE zzzzzz. - Flux Mapping Surveillance 78-268 11/19/78 F 0.0 B 4A - - - - HH FILTER #11 Steam Generator Feed Pump Strainer 78-277 11/27/78 F 67.1 A 3 - - - - EB GENERA lB Vital Instrurrent Inverter Failure l

I i

I I

Page 4 Of 14 B-1-7.Rl

DOCKET NO.: 50-272

. MAJOR PLANT MODIFI~IONS . U~ NAME: Salem #1

'REPORT MONTH November, 197-3 DATE: December 11, 1978 COMPLETED BY:~L~*~K_.~M_i_l_l_e_r~~-

TELEPHONE: 609-365-7000 x 507

• DCR NO. PRINCIPLE SYSTEM SUBJECT PD-0128 s. G. Feed & Cond. Relocate 115VAC Governor (115VAC) Control Power Supply

• DESIGN CHANGE REQUEST Page 5 of 14 8-1-7.Rl

DOCKET NO.: 50-272

.MAJOR PLANT MODIFI~IONS Salem #1 UN- NAME:

REPORT MONTH November, 197-8 December 11, 1978 DATE:

COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 x 507

• DCR NO. 10CFRS0.59. SAFETY EVALUATION PD-0128 This design change does not functionall change the system operation. It will increase system reliability.

Page 6 of 14

• DESIGN CH_Z\NGE REQUEST

DOCKET NO.: 50-272 Sylv'.!MAR:l OF SAFETY RELATE.INTENANCE UNIT ,.ME: ~-=.:~:...:...='--~~~~~~~~

Salem #1

=TE: December 11, 1978 DEP A,RT:V.i.ENT Maintenance/Perforrnahce ~~~~~~~_:._~~~~~

L. K. Miller REPORT MONTH November 1978 WOR...1< ORDER EQUIPMENT FAILURE DESC~!PTION CORRECTIVE ACTION NO.

I MD-3206 100' Elev.* Air Ibck Worn Inner Door Bearings. Replaced Bearings.

OD-10697 12 Safety Injection Internally Damaged. Replaced Pump.

Pump OP-0495 11 & 12 Containment Low Flow., Cleaned Suction Strainers.

Sump Pumps OP-0479 !Valve _lONT031 Install Valve per DCR Installed Valve.

PD-0125.

--- **-1c12sv--Bat.*tel:y Rcx:>m rnOperable. Repaired Centrifical Switch.

Verit Fan.

OD-10576 Kralve 12SW092 - ~Will Not Close. Replaced Diaphragm.

1j I

t-'

PD-5141 tRMS 1R13E Erroneous Alarm. Replaced Bistable Drawer.

OD-10742 !Valve 10CV018 No Open Indication. Adjusted Limit Switch.

OD-10813 Valve 10PR002 Valve Does Not Close. Replaced SV-760.

I

! OD-10697 13 Service Water Pump.

Motor Bearing Cooler Malfunctioning.

Replaced Cooler.

OD-10732 14 Service Water High Temperature Alarm From Replaced Cooler Coil and Pump Upper. MotGr Bearing Cooler. Bearings.

• OD.,...10865 ~4 Service Water Shear Pin Broken. Replaced Distributor Barrel Pump Strainer. Seals, & Shear Key.

OD-10612 [4 Steam Generator Packing Leaking on Pressure Replaced Valve.

Tap Valve.

Page 7 of 14 8-1-7.Rl

DOCKET NO.: . 50-272

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

UNIT 1*..M.E;_S_a_l_ern

__#_l_ _ _ _ _ _ __

S~~.!M?~~Y OF SF..FETY RELATE~INT~NANCE TE: December 11, 1978 DEF j\RTMENT Maintenance/Performance ----------~~~

L. K. Miller REPORT MONTH November 1978 TELEPHONE: 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCrtIPTION CORREC:TIVE .?.CT ION NO.

I OD-10853 Valve 10CV056 Packing Leak. Repacked Valve.

r I

PD-5182 Channel N42 NIS Out Of Spec. Adjusted Isolation A:rrp Gains.

OD-10743 1LC500 B/J Level Deviation Alann ... Replaced Capacitors.

Not Accuated.

OP-0437 Valve 10CV078 Valve Leaking. Seal Welded Diaphragm.

OD-10864 Valve 11SW024 Leaks Through. Replaced Diaphragm.

OD-10845 Valve 10WL099 Does Not Close . Repaired Solenoid Valve.

OD-10147 Channel lC $ *.El. C. . - Alarm Will Not Reset. Replaced Logic Card.

ri OD-10895 Valve llMS171 Petcock Valve is Leaking. Replaced Petcock Valve. - ..

OD-10921 Valve 14BF019 Bezel Indicator in Control Equalized Transmitters.

Room swinging.

OD-10670 Valve 14SW065 Flange Leaks. Welded Flange.

i MD-3225 Channel lC S.E.C. Will Not Reset. Replaced Printed CircUit Cards.

PD-5175 Solenoid Valve Rework Solenoid. Rebuilt Solenoid Valve.

SV398.

PD-5205 Channel N43 NIS Upper Flux Recorder Out of Adjusted Isolation Anp.

Spec.

OD-10481 15 Service Water Flex Hose Leak. Replaced with Copper Tubing.

Purrp.

Page 8 of 14 8-1-7.Rl

- -DOCKET NO. : _;.J.J50u::...2""'7'"""'2~-------

SV.M..1'1A...~Y OF S?..FETY RELATE~~INTENANCE

.TE: __

TJNIT 1Ti1..ME: Salem #1 D_e_c_e_mb_e_r__l_l_,_1_9_7_8~~-

DEP A.RT.MENT Maintenance/Perfgrrrance COM.PLETED BY:_L_._K_.__Mi_'_l_le_r________

REPORT MONTH November 1978 TELEPHONE: 609-365-7000 X507 WORK ORDER EQUIPMENT FAILURE DESCRIPTION CORRE~TIVE ACTION NO. I I 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

I RE-196 il.FA0118 Out of Spec. Calibrated.

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 Spikes~ Replaced Bistable.

i

S~ETY

---

nocxEmT.~N~a~.-:-_--=5~....

o~-~2::1::2::~~~~~~~~::~~----*--~-==

I SlJMMARY OF RELATE.l\INTE?:JANCE UNIT IME: Salem #1.

_TE: December 11, 1978 DEP ]?.RTMENT Maintenance/Perfo.r:rnance CO.MYLETED BY: L. K. Miller REPORT MONTH November 1978 ~~~~~~~~~~~~-

TELEPHONE: 609-365-7000 X507 WOR..1< ORDER I

EQUIPMENT F;.~ILURE '~scnpm10N

_,r.. _, __ l - j CORRE~TIVE ACTION NO.

I I

PD-5217 1LC527C Corrparator Out of Spec. I Replaced Comparator. I 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 Out of Spec. *Adjusted.

OD-11130 lL Service Water Upper Bearing Motor Cooler Replace Pipe Fitting~

Pump. Leaking.

• Page 10 of 14 8-1-7.:Rl

SALEM UNIT I OPERATING

SUMMARY

NOVEMBER, 1978 11-1 The unit has been shutdown due to inspection and thru replacement of #13 RCP No. l Seal and routine plant 11-11 maintenance activities.

11-12 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.

11-13 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%.

11-14 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.

11-15 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.

11-16 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) established.

The f 1 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.

11-17 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.

11-18 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.

11-19 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%.

11-20 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.

11-21 Unit load remained greater than 99%.

thru 11-23 Page 12 of 14

11-24 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.

11-25 Unit load remained greater than 98%.

thru 11-26.

11-27 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.

11-28 Unit shutdown for maintenance.

11-29 The Reactor went critical at 1458, .. and on line at 2350.

Load was held below 10% for the remainder of the day.

11-30 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

• .RE~UELING 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. In-Core .~ 1 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 14 of 14 8-l-7.R4