ML18079A826
| ML18079A826 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/10/1979 |
| From: | Miller L Public Service Enterprise Group |
| To: | |
| Shared Package | |
| ML18079A824 | List: |
| References | |
| NUDOCS 7908200367 | |
| Download: ML18079A826 (12) | |
Text
AVERAGE DAILY UNIT POWER LEVEL V.ONT'n July 1979 DAY AVERAGE DAILY POWER LEVEL 1
2 3
4 5
6 7
8 9
10 11 12 13 14
- 15.
16 Pg. 2 of 13 8.1-7. PJ.
(MWe-NET) 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
OOCKET NO. 50-272 UNIT Salem #1 DATE August 10, 1979 CQ.\\IPLETED BY L. K. Miller TELEPHONE 609~365-7000 X507 DAY AVERAGE DAILY POWER LEVEL (MWE-NET) 17 0
18 0
19 0
20 0
21 0
22 0
0 23 24 0
25
-0 26 0
27 0
28 0
29 0
30 0
31 0
- l. omt Naire:
Salem #1
- 2.
Beportinq Period:
July 1979
- 3. Licensed T.hemal PolEr (~) : __
__;;3~3.;:;3.;:;8 ____ _
- 4.
Naaeplate Rat:inq (GJ:Css Wle) : ___
1_1_3_5 ____ _
- s.
I::esign Electrical Rating (Net MWel:....-1..;.0.;;..9.;;.0 ____ _
- 6. MaxinUlln Dependable Capad.ey (Gmss M'le) =----=l::..li=2~4.___
- 7. - JAiiximlm* Depend,able ~tir (Net MNe) : ___
1_0_7_9 __
Notes:*
OCCKET ro. :_5_0_-_27_2 _____ _
CATE : _Au_.:;;.gu_s_t_l_0..;.1_1_9_79 __
a:::MPimED BY: L. K. Miller,
~:
609-365-7000. X507
- 8. If Changes O:cur in Capacity Ratings (Item Nlllri::er 3 'lmcugh 7) Si.nee Last ~:ct, Give Reason:
NONE
- 9.
l?ower Level. To Which ~cted, If Arr:f* (Net me): _____
NO_NE _______________ _
lO.
Beascns For Restricticns, If krrf': _____
...;N:;..:;O~!NE~--------------------
This M::lnth Year to Date Ctm.tlative 744 5,087.
18,288
- u. 5:Jw:'S L"l ~q Period
- u. Nlllltler Of 5:Jw:'S Reac<-..or Was Critical 0
2,184.5 9,841.4 l3. Reactor Reserve Shut.Ccwn Hours 22.7 22.7
- 14.
Hours Generator On-Line.
0 2,161.3 9,459.3 lS. Unit Reserle Sh'lltdcMn ~
- o 0
0
- 16.
Gross TheJ:mal Energy Generated (mti) 0 6,482,491 27,467,227
- 17.
GJ:Css Electrical Energy Generated a-Hi) 0 2,181,770 9,154,580
- 18. Net Electrical Energy Generated (Mm)
(3~174) 2,076,105 8,663,085 l9. Unit Service Factor 0
42.5 51.7
- 20. Unit Availahilit<J Factor 0
42.5
- 51. 7 2l. Unit Capaciey Factor (Usinq MOC Net) 0 37.8 43.9
- 22. Unit Capacity Factor (Usi.nq DER Net) 0 37.4 43.5
.23. Unit Forced Outage Rate 0
3.0 31.3
- 24.
Shlit:dcwns Scheduled Over Next 6 M:nths (Type, Date, arid Duration of Each):
NONE
- 25. If Shut Down At E!ld of Report Period! Estimated Date of Startup: ___
S_ep_u_ember 3_,_1_9_7_9 ___ -..._,__ ___
- 26.
Units In Test Status (Prior to Ccmrercial Operation) :
8-l-7.R2 Pg. Jof 13 Forecast 9/30/76 11/01/76 12/20/76 Achieved 12/11/76 12/25/76 6/30/77 l
NO.
DATE 79-194 6/27/79 79-195 6/27/79 1
F: Forced S: Scheduled Page 4 of 13
. 8-1-7. Rl TYPEl s
s 2
UNIT Slll11.1xHIS AND roiER mrix:r!ONS REroRr M:MI'i1 July 1979 DOCKET NO.: 50-272
--~~~~~~~~-
- UN l T 'NAME: Salem #1 MlmOO OF OORATIOO
~
SlllJITIOO (lams) rum RF.AC'IDR 744 c
4B 744 A
4B Reason:
A-Equipient Faliure(Explain)
B-Maintenance or Test C-Refueling LICl!NSE iMNr REPORI' I D-Re<Ju).a tocy ReStriction E~ator Training & Lioense Examination F-.Administrative
~ational Error(Explain)
It-Other (Explain)
SY~ cX:MPcmNr O'.JDE O'.JDE~.
~~~~~~~~~
DATE: August 10, J 979 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507 CAUSE AND CORREX:TIVE ACTIOO 'ID J.>IUM:Nl' REDJRRER:E RC FUELXX.
Annual Refueling outage HA TURBIN Low Pressure Turbine Blading j
4 r-i:!thod:
1-Manual 2-Manual Scram.
3-Aut:anatic Scram.
4--0ther (Explain)
A.
load Reduction B. ',Contmuation of Pr~vious Outage Exhibit G - Instructions
- for Preparation of Data Eilt:J:y Sheets for Licensee Event Report(LER) File (NUREG-0161) 5 Exhibit 1-Sane Source
MAJOR PLANT MODIFI~ONS REPORT MONTH July 1979 DOCKET~:~~~5_0_-_2_7_2~~~~~~
UNIT N!I!:
Salem 1
~~~~~~~~~~~~~
DATE:
August 10, 1979
- DCR NO.
lPD-0080 lSC-0148-12 lED-0057 lED-0096 lED-0113 lED-0121 lED-0161 lED-0198 lED-0209 lED-0210 lED-0236 lED-0253 lED-0280
~~~~~~~~~~~~~
COMPLETED BY:
L. K. Miller
~~~~~~~~~~~~~
TELEPHONE:
609-365-7000 X507
~~~~~~~~~~~~~
PRINCIPLE SYSTEM SUBJECT Battery Instrumentation Add Battery Ammeter Test Switches Component Cooling Pumps Replace Internals with Stainless Steel in No. 12 Component Cooling Pump The following DCR's are being reported as the result of an internal audit.
The majority were completed prior to the initiation of reporting all completed DCR's, both major and minor.
L.P. Turbine Rotors Modify L.P. Turbine L-4 Row Grouping Main Steam Modify MSIV Control Circuit to prevent Hydraulic Lock on Operator Containment Ventilation Install Narrow Range Containment Pressure Indicator on Control Room Console Circulating Water Setpoint Change -
C.W. Strainer Lighting Recircuit Relay Room Lighting to Place Fixtures on Emergency Lighting Roadway Lighting Reposition Roadway Lighting to Clear "B" Building Radiation Monitoring Replace 1VC7 Through 1VC14 with Masoneilan Valves Heating Steam Replace Internals in 1HS49 to Full size NSSS Stator Cooling Water Radiation Monitoring Replace Force Motors in Porter &
Fischer Transmitters Modify Starot Water Thermostat Circuit for Cold Weather Operation Setpoint Change -
Rl8
- DESIGN CHANGE REQUEST 8-1-7. Rl Page 5 of 13
- ~JOR PLANT MODIFICtt10NS REPORT MONTH July 1979 DOCKET NO:
50-272 UNIT N~:~~~S-a_l_e_m~l~~~~~~-
DATF.:
August 10, 1979
- DCR NO.
lED-0359 lEC-0473 lEX-0005 lEX-0008 lOD-0059 lSC-0036 lMD-0071 lMD-0075 lPD-0011 lPD-0020 PRINCIPLE SYSTEM Yard Main Turbine Vibration Monitoring
~~~~~~~~~~~~~
COMPLETEn BY:
L. K. Miller
~~~~~~~~~~~~-
TELEPHONE:
609-365-7000 X507
~~~~~~~~~~~~~
SUBJECT Install Turbine Balancing Slab in South Yard Setpoint Change - Turbine Vibration Service Water, Auxiliar1 Special Test Using AF40 Valves Feed Water and Chemical Volume Control Circulating Water Special Test - Circulating Water Flow Characteristics Main Steam Valve Position Change -
MS28 Valves Univac Computer Code Computer Program Change (1D043A.:
TOTE)
Chiller Unit Compressor Replace Chiller Compressor Pressure Switch Main Turbine Replace Main Turbine L.P. Rotor Blades in accordance with AIB7703 SSPS Modify SSPS Power Supply Wiring Radiation Monitoring Provide Separate Power Supply to RMS Recorders
- DESIGN CHANGE REQUEST 8-1-7. Rl Page 6 of 13
'DOCKET NO. :
~5~0~--=2~72=-------
MAJOR PLANT MODIFICA.NS REPORT MONTH July.J..979 UNI-'1.&'1E :
DATE:
August 10, 1979 COMPLETED BY:
L.K. Miller TELEPHONE:~6_0_9_-_3_65_-_7_o_o_o~xs--o_7_
- DCR NO.
10CFRS 0. 59.
SAFETY EVALUATION
- -*--* *---- 1-----~-------------------------------t lPD-0080 lSC-0148-12 lED-0057 lED-0096 lED-0113 lED-0121 lED-0161 lED-0198 lED-0209 lED*-0210, lED-0236 lED-0253 lED-0280 Change does not affect any safety related equipment.
The alternate change in material from carbon steel (and hard chrome steel) to 316 stainless steel does not present an unreviewed safety question as the functionability remains the same.
A change to the Tech. Specs. will not be required as this item is not addressed in the Tech. Specs.
Change does not affect any safety related equipmerit.
Equipment performs same function and meets all applicable requirements.
The safety related system will not be affected.
Change does not affect any safety related equipment.
System not safety related.
This DCR takes some aisle lighting fixtures off regular lighting circuits and-puts them on emergency lighting circuits.
System not safety related.
This DCR removes one roadway lighting fixture and wiring to clear an area for construction of new service facilities.
This DCR does not represent a functional change in equipment.
The valves presently installed via DCR lED-0008 meet all applicaple design requirements.
The original Masoneilan valves were modified with 3/4" internals under this DCR and now beco~e spares.
No safety analyses and TSch. Specs. are affected.
Not safety related.
Does not affect any safety related systems.
Transmitter reliability will be imp:roved without change to its basic design or function.
This is not safe~y related and doe~ not affect any safety related systems.
Revision of radiation channel Rl8 setpoint based upon result of radiochemical analysis of waste hold up and/or monitoring tanks.
Setpoint shall be in accordance with the Salem Environmental Technical Specifications.
DOCKET NO. :
50-272
_.;::;"'""-.::..:..=-~~~~~~-
MAJOR PLANT MODIFICA~ONS RF.PORT MONTH July --~79 UNreNA.i.\\1E:
Salem #1
- DCR NO.
lED-0359 lEC-0473 lEX-0005 lEX-0008 lOD-0059 lSC-0036 lMD-0071 lMD-0075 lPD-0011 lPD-0020 10CFRSO. 59.
DATE:
August 10, 1979 COMPLETED BY:
L. K. Miller TELEPHONE:
609-365-7000 X507 SAFETY EVALUATION This is a non safety related structure.
The concrete will be constructed outside the Turbine building.
It is not related to or interfering with any other system.
Functional operation is unchanged.
The design change is not safety related, nor does it affect the operation of any safety related systems.
This subject test does not constitute an unreviewed safety question.
Operational modes to be used will simulated modes actually experienced in normal system operation and are within system design bases.
These flow measuring devices do not require penetration of any piping; the sensing transducers only clamp to outside surfaces.
The implementation of this test does not affect any presently performed safety analysis, nor does it create any new hazards.
The basis of the Technical Specifications are not affected.
The subject design change to lock close the Nos. 11, 12, 13, 14 MS128 valves at all times is not safety related, nor do they affect the operation of any safety related systems.
This DCR alters only the output heading format and data printing resolution of the Tote program.
It does not affect plant safety or shutdown capability.
No new hazards are created nor are any presently analyzed accidents aggravated.
The bases of the Tech. Specs. are unaffected.
Equipment performs same function and meets all applicable requirements -
System operability is improved.
Functional operc~:tion is unchanged.
Design change will improve reliability.
No change in system function & no failure modes would be created which could cause or increase the potential for accidents or malfunctions.
Change will improve operational reliability.
Equipment performs same function and meets all applicable requirement~.
Change only provides new power feed for recorders which do not perform a safety related function.
I
..__~~~~~..._~~~~~~~~~~~~~~~~~~~~~~~~~P~a~g~e~-o-o~o~t~l~~J~~~~~-
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L
SUMMARY
OF SAFETY RELATED MAINTENANCE MAINTENANCE DEPARTMENT REPORT MONTHI JULYr 1979 WORK START END ORDER DATE DATE NUMBER EQUIPMENT DESCRIPTION 903795 061379 061479 COOLERr 11 CHARGING PUMP 903802 062179 070679 PUMPr 11 COMPONENT COOLING 904315 061979 062279 VALVE, 10CV054 904316 061979 062479 VALVE, 10CV081 904317 061979 062479 VALVE, 10CV082 904320 062279 063079 FAN, 13 REACTOR NOZZLE SUPPORT VENTILATION 904439 061979 062279 VALVE, 10CV056 904461 062779 062279 FILTER' 14 AUXILIARY BUILDING VENTILATION 905251 071379 071379 PUMP, 12 BORIC ACID TRANSFER 905579 062679 062979 UNIT, 13 CONTAINMENT FAN COIL 905920 061979 072679 STRAii"ER' 14 SERVICE WATER PUMP 905923 061979 072679 STRAINER, 15 SERVICE WATER PUMP 906003 062079 070379 UNIT, 12 CONTAINMENT FAN COIL 906024 062679 062E179 GENERATOR, 12 STEAM 906025 062679 062479 GENERATOR, 12 STEAM 906027 062679 062979 GENERATOR, 13 STEAM 906028 062679 0629"79 GENERATOR, 14 STEAM 906113 071179 072579 FAN, 12 FUEL HANDLING BUILDING EXHAUST Page.. 9 of 13 DOCKET NUMBER 50-272 SALEM UiHT
.I.
COMPLETED BY: L. K. MILLER TELEPHONE NUMBER: 609-365-7000 SALEM EX 507*
SHEET 001 OF 002 SHEETS FAILURE/JOB DESCRIPTION ACTION TAKEN INSTALL TEMPORARY DEMINERALIZED WATER TEMPORARY COOLING SYSTEM INSTALL-COOLING SYSTEM. REMOVE WHEN NORMAL COOLING ED. REMOVED WITH THE RETURN TO SYSTEM IS RETURNED TO SERVICE.
SERVICE OF THE NORMAL COOLING SYSTEM+
REPLACE CARBON STEEL IMPELLER WITH A STAINLESS STEEL IMPELLER+
REPACK.
INSPECT VALVE INTERNALS.
INSPECT VALVE INTERNALS, MOTOR RUNS, FAN DOES NOT RUN.
REPACK.
INSTALL 20 NEW CHARCOAL FILTERS.
SUSPECT PUMP FROZEN WITH SOLDIFIED BORIC ACID.
REPLACED IMPELLER.
REPACKED.
DISASSEMBLED, REWORKED INTERNALe AND REASSEMBLED.
DISASSEMBLED, REWORKED INTERNALS AND REASSEMBLED.
REPLACED DRIVE BELTS.
REPACKED.
INSTALLED NEW FILTER CATRIDGES.
CLEARED SUCTION AND DISCHARGE LINES OF SOLIDIFIED BORIC ACID.
REPAIR SERVICE WATER LEAK ON COOLING COIL. REPLACED FLANGE GASKET.
INSPECT INTERNALS, REPAIR AS NECESSARY+
INSPECT INTERNALS, REPAIR AS NECESSARY.
REPLACE EXPAi"SIOi" JOiiH
- M~ICHii"E Ii-IBCJARD SECONDARY MANWAY COVER.
MACHINE OUTBOARD SECONDARY MANWAY COVER.
MACHINE OUTBOARD SECOi'-!Dr:iR*r Mr*~i-IWAY COVER.
MACH HIE INBOr:'.\\RD SECOi'-IDARY MAi'1Wr'iY COVER, REPLACE EXF'ANS I ON SHEETING.
STRAINER CLEANED, WORN COMPONENTS REPLACED AND F:EASSEMBLED
- STRAINER CLEANED, WORN COMPONENTS REPLACED AND REASSEMBLED.
REPLACED EXPANSION JOINT.
MACHINED SURFACES.
MACHINED SURFACES.
MACHINED SURFACES.
MACHINED SURFACES.
REPLACED EXPANSION JOINTS,
SUMMARY
OF SAFETY RELATED i*ir~ I NTENAl>JCE MAINTENANCE DEPARTMENT REPORT MONTH: JUL Yr 1979 WORK START END EQUIPMENT DESCRIPTION ORDER DATE DATE NUMBER 90<'>113 071179 072579 FANr 11 FUEL HANDLING BUILDING EXHAUST 906123 071279 071679 PUMPr 11 COMPONENT COOLING 906125 071179 071879 GENERATORr 12 STEAM 90<'>125 071179 071879 GENERATORr 11 STEAM 906125 071179 071879 GENEF~ATOR r 13 STEAM 906125 071179 071879 GENERATORr 14 STEAM 906130 071379 071479 PIPEr 12 STEAM GENERATOR FEEDWATER NOZZLE REDUCER 906137 071779 072079 TRACEr 11 BORIC ACID PUMP HEAT 906139 071779 072079 TRACEr 12 BORIC ACID PUMP HEAT Page 10 of 13 DOCKET NUMBER 50-272 SALEi'i UNIT 1
FAILURE/JOB DESCRIPTION REPLACE EXPANSION SHEETING.
COMPLETED BY: L+ K. MILLER TELEPHONE NUMBER: 609-365-7000 SALEM EX 507 SHEET 002 OF 002 SHEETS ACTIOi>l TAl\\EN REPLACED EXPANSION JOINTS.
INVESTIGATE CAUSE OF HIGH VIBRATION.
TIGHTENED BASE BOLTS.
PREF'f'-iRE OUTBOr-~RD MANI.JAY GASKETS+
PIREPARED MANI.JAY GASKETS.
PREPARE OUTBOr'iRD MANI.JAY GASKETS.
PREPARED MANWAY GASl\\ETS+
PREPARE OUTBOARD HANWAY GASKETS.
PREPARED MAi'llJ~iY Gr~SKETS+
PREPARE OUTBOARD MANI.JAY GASKETS+
PREPARED MAi'lWAY GASl\\ETS+
MACHINE NElJ lJELD END PREPr:.iRATIONS
- MACHINED i>JElJ WELD ENDS+
REPAIR+
REPLACED HEAT STRIP.
REPAIR.
REPLACED HEAT STRIP+
L
SUMMARY
OF SAFETY RELATED MAINTENANCE PERFORMANCE DEPARTMENT REPORT MONTH! JULYr 1979 WORK START END ORDER DATE DATE NUMBER EQUIPMENT DESCRIPTION 904253 061479 061479 INSTRUMENTr 1PC0948 904259 070379 070379 INSTRUMENTr 1FT0425 904421 061879 061879 INSTRUMENTr 1TC0421C/D 905331 071979 072079 VALVEP 10CV179 905506 061779 062979 VALVE OPERATORr 10CV018 905568 062579 070379 VALVE OPERATORr 14AF011 905589 062879 062979 VALVE OPERATORP 10CN018 905601 062879 070279 DAMPER OPERATORr 1CAA33 905601 062879 070279 DAMPER OPERATOR* 1CAA32 905601 062879 070279 DAMPER OPERATORr 1CAA31 905601 062879 070279 DAMPER OPERATORr 1CAA18 906016 062179 021779 INSTRUMENTr 1PL0309 Page 11 of 13
~
COMPLETED BY: L, K, MILLER.
DOCKET NUMBER 50-272 SALEM UNIT 1
TELEPHONE NUMBER: 609-365-7000 SALEM EX 507 SHEET 001 OF 001 SHEETS FAILURE/JOB DESCRIPTION ACTION TAKEN OUT OF CALIBRATION, CALIBRATED, OUT OF CALIBRATION, CALIBRATED, OUT OF SPECIFICATION.
CALIBRATED, FAILED STROKE TIME TEST, STROKE TIMED, CHECK LIMITSr VALVE DOES NOT OPERATE, CALIBRATED CONTROLLER, CHECK AND REPAIR OPEN LIMIT SWITCH, ADJUSTED LIMIT SWITCH, DOES NOT CONTROL PROPERLY, REPAIR, CALIBRATED CONTROLLER.
SOLENOID STACK CAUSING IMPROPER OPERATION. REPLACED SOLENOIDS SV690r SV691, SOLENOID STACK CAUSING IMPROPER OPERATION, REPLACED SOLENOIDS SV690r SV691, SOLENOID STACK CAUSING IMPROPER OPERATION. REPLACED SOLENOIDS SV690r SV691, SOLENOID STACK CAUSING IMPROPER OPERATION, REPLACED SOLENOIDS SV690r SV691, GAUGE GLASS MISSING, REPLACED BROKEN GAUGE GLASS,
SALEM UNIT I OPERATING
SUMMARY
JULY 1979 7-1 thru 7-31 Annual Refueling Outage.
Page 12 of 13
REFUELING INFORMATI~
DOCKET N0.:_5_0_-_2_1_2 ______ ~
UNIT: Salem #1 DATE : August _10, 1979 -
COMPLETED BY: L.K. Miller TELEPHONE: 609-365-7000 X507 MONTH:
July 1979
~--~--~~~~------------~-
- 1.
Refueling information has changed from last month:
YES NO x
- 2.
Scheduled date of-next refueling:
March 29,.1980 May 25, 1980
- 3.
Scheduled date* for* restart-following refueling: ~~~~~~~~~~~-
- 4.
A.
Wil.l Technical_ Specification changes or other. license amend.men ts be- -required?.
YEs**
NO __ _
NOT DETERMINED TO-DATE __
_.J_u..... l.... v---.1.._9.._7.._9 __
- B-.. - -H*as the-reload*.fue'l design. been reviewed. by the Statiqn Operating Review Committee'?
YES NO x ---
If no, when is *it scheduled'?
Fe:Pruary 1980
- 5.
Scheduled date(s) for submitting proposed licensing action:
February 1980 (If Required)
- 6.
Important licensing considerations associated with refueling:
NONE
- 7.
Number of Fuel Assemblies:
A.
In-Core B..
In Spent Fuel Storage*
- 8.
Present licensed spent fuel storage capacity:
Future spent fuel storage capacity:
- 9.
Date of last refueling that can be discharged pool assuming the present licensed capacity:
Page 13 of 13 8-l-7.R4 193 0
264 1,170 to the spent fuel April 1982