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{{#Wiki_filter: | {{#Wiki_filter:DJCKET NO. 50-272 | ||
i.* TJnit Nane:. Salem #1 Notes: .. 2. P.eport:l.nq Period:_* | ~~~~~~~~- | ||
_N_o_vernbe..;..* | 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 | |||
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-_:--. | I | ||
-- | .,-__ | ||
Pg. 2 of 14 8.1-7.Rl | |||
Giw Reason: NONE 9. Power Leval 'lb Mlich | |||
* If Aey* (Net l-lie) :. | * | ||
: 10. Rea.sons For Restricti.cns,. | ~ID.: :__...;..;.....=~-.....,,....,,.--,,.~ | ||
u* | 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. | * l3. | ||
* Reactor Reserve Shutdown | * 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~----- | ||
609-365-7000 x 507 | REPORI' MJNrH Noveniber UNIT 'NAME: _S_a_l_em | ||
.MAJOR PLANT REPORT MONTH November, 197-8 *DCR NO. lOCFRS0.59. | __~#_l_ _ __ | ||
PD-0128 This design change does not operation. | DATE: December 11, 1978 COMPLETED BY: L.K. Miller TELEPHONE: 609-365-7000 X507 I | ||
It will increase | 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 | ||
* DESIGN CH_Z\NGE REQUEST DOCKET NO.: 50-272 | .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 | |||
12 Safety Injection Internally Damaged. Pump 11 & 12 Containment Low Flow., Sump Pumps !Valve _lONT031 Install Valve per DCR PD-0125. | -* | ||
I | |||
" | |||
Repaired Centrifical Switch. OD-10576 | 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. 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 | |||
-'-----------~--- | |||
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. | Not Accuated. | ||
Valve Leaking. Seal Welded Diaphragm. | OP-0437 Valve 10CV078 Valve Leaking. Seal Welded Diaphragm. | ||
Leaks Through. Replaced Diaphragm. | OD-10864 Valve 11SW024 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. | 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. | Room swinging. | ||
Flange Leaks. Welded Flange. Will Not Reset. Replaced Printed CircUit Cards. Rework Solenoid. | OD-10670 Valve 14SW065 Flange Leaks. Welded Flange. | ||
Rebuilt Solenoid Valve. Upper Flux Recorder Out of Adjusted Isolation Anp. Spec. Flex Hose Leak. Replaced with Copper Tubing. | ' | ||
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 | |||
UNIT IME: Salem #1. _TE: December 11, 1978 CO.MYLETED BY: L. K. Miller REPORT MONTH November 1978 TELEPHONE: | |||
609-365-7000 X507 | |||
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 | * Out of Spec | ||
* calibrated. | * calibrated. | ||
l PD:-:5224 | . - | ||
::.IBS539A | l PD:-:5224 ::.IBS539A Out of Spec. *Adjusted. | ||
Upper Bearing Motor Cooler Replace Pipe Leaking. | - -* | ||
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== | ==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 hours 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. | 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. | ||
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* | 11-12 The Reactor was critical at 1750. Two Reactor trips occured before 2400 hours 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. | ||
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) | 11-13 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. | * 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%, | |||
* 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. | 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. | At 1830, load was increased at 2% per hour. The unit load was 84.8% at 2400. | ||
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. | 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. | ||
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. | 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. | ||
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 | 11-19 Unit load was maintained at greater than 99% until 1330. | ||
, 11-24 | 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 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. | 11-20 Unit load is being reduced to approximately 50% to allow | ||
Unit remained shutdown for the remainder of the day. Unit shutdown for maintenance. | *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. | ||
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 | 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 | |||
.. | .. | ||
* INFORMATIO | * .RE~UELING INFORMATIO* | ||
DOCKET NO.: 5 o- 2 12 | |||
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: | UNIT: Salem #1 DATE: December 11, 1978 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 Ext. 507 MONTH: November, 1978 | ||
March. 31;. 1979 3 *. Scheduled date for restart: following. | ~~..---..-..----...-..-..-..-...-~..-...-- | ||
refueling: | : l. Refueling information has changed from last month: | ||
June 23, 1979 4. A.. Will Technical Specification changes or other license | YES X NO | ||
* 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? | : 2. Scheduled date of next refueling: March. 31;. 1979 3 * . Scheduled date for restart: following. refueling: June 23, 1979 | ||
YES NO X | : 4. A.. Will Technical Specification changes or other license | ||
February 1979 5. Scheduled date(s) for submitting* | * amendments be- required? YES** NO | ||
proposed licensing action: March, 1979 if reguired. | ----- | ||
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: | 6.. Importan.t licensing consid13rations associated with refueling: | ||
NONE 7. Number of Fuel Assemblies: | NONE | ||
A. | : 7. Number of Fuel Assemblies: | ||
A. In-Core .~ 1 B. In Spent Fuel Storage* 0 | |||
1, 170 ..--------..--..--..-..-- | : 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: | ..--------..--..--..-..-- | ||
Page 14 of 14 8-l-7.R4 | : 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}} |
Revision as of 16:46, 21 October 2019
ML18078A503 | |
Person / Time | |
---|---|
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
~~~~~~~~-
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 - - -
~
- 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 I
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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
-'-----------~---
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
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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.
- 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