ML18078A503
ML18078A503 | |
Person / Time | |
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Site: | Salem |
Issue date: | 12/11/1978 |
From: | Miller L Public Service Enterprise Group |
To: | |
Shared Package | |
ML18078A502 | List: |
References | |
NUDOCS 7812150244 | |
Download: ML18078A503 (13) | |
Text
DJCKET NO. 50-272
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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
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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 - - -
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- 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
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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. lOCFRS0.59. 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
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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.
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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
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.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.
. -
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i-OD-11010 fJalve 12MS131 Leaking. Furrnanited.
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MD-3246 Valve 11 HW211 Leaking. Repacked Valve.
OD-11030 valve 10CV059 Will Not Close. Replaced Stem & Handwheel.
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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.
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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.
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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
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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
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- 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?
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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
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- 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