ML18085A373
| ML18085A373 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 12/11/1980 |
| From: | Midura H Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML18085A374 | List: |
| References | |
| NUDOCS 8012160445 | |
| Download: ML18085A373 (26) | |
Text
Public Service Electric and Gas Company P. 0. Box #168 Hancocks Bridge, New Jersey 08038 December 11, 1980 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 In compliance with section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following monthly operating reports for the month of November 1980 are being sent to you.
LKM:vd Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Summary of Safety Related Maintenance Operating Summary Refueling Information Sincerely yours, H. J. Midura Manager -
Salem Generating Station cc:
Mr. Boyce H. Grier Director of U.S. NRC Off ice of Inspection and Enforcement Region I 631 Park Avenue King of Prussia, PA 19406 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosures Page 1 of 26 8-l-7.R4 The Energy People
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95-2189 (5M) 10-79
ID NTH November 1980 AVERAGE DAILY UNIT POh1:R. LEVEL 50-272 OOCKET NO.
---:::S~a~le-m--,,#~1~~~~
December 11, 1980 L. K. Miller 609-365-7000 X507 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL 1
2 3
4 5
6 7
8 9
10 11 12 13 14
- 15.
16 Pg.2 Of 26 8.1-7.Rl (MWe-NET) 0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
(MWE-NET) 17 0
18 0
19 0
20 0
21 0
22 0
23 0
24 0
25 0
26 0
27 0
28 0
29 0
30 0
31
- 1.
I
- OPERATIOO CA.TA REPORI' OPERAT.IN; STATUS
- l. unit Naill!:
Salem Ill Notes:
- 2.
Reporting Period:
November 1980
- 3.
Licensed 'llleznal. Pc:M!r (~):
3338
- 4.
Na!Ieplate Rating (Gmss M-e):
1135
- 5.
Design Electrical Rating (Net Mltle):
1090
- 6.
Maximllm Dependable capacity "(Gross Mi:!):
1124
- 7.
Maximllm Dependable capacity (Net MWe) :
10 7 9 e
~
~.:
50-272
~
December 11, 1980 a:z.JPIZl'ID BY: L. K. Miller
'lEIEPB:NE: 609-365-7000 X507
- 8. If Changes Occur in Capacity Ratings (Items Nllllter 3 'lbmugh 7) Since Iast Report, Give Reason:
NONE
- 9.
Power Level To Which Restricted, If Arr:f (Net l+lel:
NONE
- 10.
Reasons For Restrictions, If Aey: _____ N_O_N"""E-----------------------
'Ibis ~th Year to Date
- 11.
Hours In ReI:orting Period 720 8,040
- 12.
Nul1iJer Of a:iurs Reactor Was Critical 0
6,097.9
- 13.
P.eactor Reserve Shuta::iwn H:Jurs 0
0
- 14.
Hours Generator On-Line.
5,946.3
- 15. Unit Reserve Shutdown Hours 0
0
- 16.
GtOSs ~
Energy Generated (lffi) 0 18,205,037.8
- 17.
Gross Electrical Energy Generated (MWH) 0 5,935,090
- 18.
Net Electrical Energy Generated(M>IH)
(2 '812) 5,658,279
- 19. unit Service Factor o*
74
- 20. Unit Avanamlity Factor 0
74
- 21. Unit capacity Factor (Using Mr:C Net) 0 65.2
- 22. Unit capacity Factor (Using DER Net) 0 64.6
- 23. Unit Forced Outage Rate 0
5.8
- 24.
Shutdowns Scheduled over Next 6 M:nths (Type, Date, and Duration of Ea.ch) :
Refueling September 20, 1980 - December 25, 1980
- 25.
If_ Shut Down At End of Report Period! Estimated Date of Startup:
December 25, 1980
- 26.
Units In Test Status (Prior tc Camercial. Cperation) :
S-l-7.R2 Pg. 3 of 26 INITIAL CRI'l'ICALI'IY INITIAL EUX:TRICITY'
~OPERATION Forecast 09/30/76 11/01/76 12/20/76 CU!mllati ve 30,001 16,185.9 22.7 15,477. 4 0
45,741,334.8 15,102,590 14,282,619 51.6 51.6 44.1 43.7 35.2 Achieved 12/11/76 12/25/76 06/30/77
- 00.
DATE 80-210 9/19/80 1
F:
Forced s: Sdteduled Page 4 of 26 8-1-7.Rl TYP~
s 2
UNIT Slll.mXMNS l\\ND PCMER Rfilx:TIONS REPORI' MJNI'H November 1980 MIITIKID OF OORATICN REASON2 SmmIOO LICENSE SYSTEM CXM:'CNFNl' (IDJRS) r::om EVENT COOE4 COO ES REACTOR REPORI' I 1729.86 c
4 RC FUEL XX Reason:
A-Fl:)ui[mmt Failure(EKplain)
B-Maintenance or Test C-Refueling O-Regulato:ry Restriction E--Operator Training & License Examination F-Administrative
~ational Error(EKplain)
H-other (Explain) 3
~thod:
1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther 50-272 DOCKET NO.:
~~~~~~~~~~
UNIT !NAME:
Sa}em 11.1 DATE:
December 11, 1980 COMPLETED BY:
L. K. Miller TELEPHONE:
609-365-7000 X507 CAUSE /\\ND CURRECl'IVE ACTION TO PREllENI' RIDJRRER:E Annual Refueling Outage.
4 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (I.ER) File (NUREX}-0161) 5 Exhibit 1-Sarre Source
MAJOR PLANT MODIFICA4t'NS REPORT MONTH NOVEMBER 1980
- DCR NO.
PRINCIPLE SYSTEM lEC-0454 Service Water lEC-0559 Control Room lEC-0614 Instrumentation lEC-0667 Protection System lEC-0713 Protection System 1EC-0766A Auxiliary Feedwater lEC-0921 Residual Heat Removal lEC-0924 Fire Protection lEC-0983 Fire Protection lEC-1003 Fire Protection lEC-1036 Main Steam lEC-1042 Main Generator lEC-1043 Safety Injection lOD-0031 Security System lPD-0085 115 VAC lPD-0134 Radiation Protection lPD-0167 Main Turbine lSC-0010 Component Cooling
- DESIGN CHANGE REQUEST 8-1-7. Rl Page 5 of 26 DOCKET N" 50-272 UNIT NAM\\
Salem 1 DATE:
December 11, 1980 COMPLETEn BY:
L. K. Miller TELEPHONE:
609-365-7000 X507 SUBJECT TGA Service Water Bypass Control Console Main Transformer Vacuum Switch Revise Steam Generator Ventilation Reset Circuitry Modify lAFl Modify #12 RHR Pump Electrical Penetration Fire Barrier Walls Switchgear Room Main Steam Demand Valve Circuit Modify Stator Cooling Containment Pressure Transmitters Security for Manhole Install Outlet Box Plant Vent Add Computer Input From S.D. Control Circuit Relocate PL0197 and PL0200 Install Tee in Drain Line
50-272 MAJOR PLANT MODIFICATI~
DOCKEWO.:
UNIT
~:
Salem Ill
~~~~__;.;...~~~~~~~
DATE:
December 11, 1980 REPORT MONTH November 1980
- DCR NO.
lEC-0454 lEC-0559 lEC-0614 lEC-0667 lEC-0713 1EC-0766A lEC-0921 lEC-0924 lEC-0983 lEC-1003 lEC-1036 10CFRSO. 59.
COMPLETED BY:
L. K. Miller TELEPHONE: 609-365-7000 X507 SAFETY EVALUATION This design change does not affect any presently performed safety analysis nor does it create any new safety hazards.
The bases of the technical specifications are not affected.
This is not a safety related change and does not affect the operation of safety related equipment.
This change is on non safety related equipment and does not affect safety margin or analysis.
A USQ is not involved since a setpoint change is being made to maintain the margin dictated by the safety analysis.
In addition, there is neither a system, functional nor logic modification.
A USQ is not involved as this change does not alter function or reliability of safety systems.
This change provided additional operator information.
The change enhances the auxiliary feedwater system reliability by totally precluding c1osure of this common suction valve.
This change was discussed with the NRG and has their approval.
No UEQ is involved because it does not change the operating characteristics of the auxiliary feedwater system.
The installation of impeller lock nut kits on the No. 11 and 12 RHR pumps doesnot pose an unreviewed safety question as implementation of this change will forestall a loosening of the impeller lock nuts as noted on NRG IE circular No. 79-19.
Implementation of this charige will not affect the function or operation of any system other than to improve system reliability, therefore, an unreviewed environmental question is not involved.
Additions of fire barriers between MCC and pressurizer heater switchgear does not impact any safety function, analysis or mar-gin.
No USQ is present.
Change involves installation of fire barrier assemblies between 4 KV vital switchgear per NRG Fire Protection SER of 11/20/79.
No safety function, margin.or analysis will be adversely affected.
Therefore, no USQ is present.
Addition of fire barriers between 460 ~olt & 125 Volt D.C. switchgear on Elevation 84' will not affect safety margin, analysis or function.
No USQ is present.
The design change assures compliance with the original intent and does not functionally change the system operation.
Page 6 of 26
- DES!GN CHANGE REQUEST
MAJOR PLANT MODIFICATI~
REPORT MONTH November 1980 DOCKET_.l0.:
50-272 UNIT NllE:
~-sa_l_e_m __ #_l __________ _
DATE:
December li, 1980
- DCR NO.
lEC-1042 lEC-1043 lOD-0031 lPD-0167 lSC-0010 lPD-0085 lPD-0134 10CFRS0.59 COMPLETED BY:
L. K. Miller TELEPHONE:
609-365-7000 X507 SAFETY EVALUATION This modification to the hyd~ogen cooling of the generator has been done in accordance with Westinghouse recommendations and approved procedures.
No safety function, analysis or margin will be adversely affected.
No USQ is present.
This design change involves the change of the fill fluid of the containment pressure transmitters in the Safety Injection system from distilled water to a high temperature Dow Corning oil. It will produce a more stable transmitter signal under extreme environmental conditions and in turn improve the system performance.
It does not alter or change either the functional requirements or the technical specifications.
This DCR covers the addition of magnetic switches to certain manhole covers for security purposes.
This DCR will not affect any safety function of the system involved.
The proposed changes do not involve any of the criteria associated with an unresolved safety question as per 10CFR50. 59.
This DCR is issued to relocate two local pressure gages due to excessive vibration. It is not safety related and does not require a change to any technical specification.
No additional safety anal¥sis is required.
This DCR adds only one drain and one vent connection to C.C. side of boric acid evaporator condenser.
This will not make any change to the functioning of the system.
System not safety related.
DCR provides a receptacle on the plant vent duct platform.
Design change to monitor operation of the steam dump system.
The change does not impact present system design.
Page 7 of 26
- DES!GN CHANGE REQUEST
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'.\\i nERCPJPTTON OF PROPLFM, RTATllS LTGHT FOR lA VITAL RUR !9 LlJMINATED CORPECTIVE ACTIQ~,
_REPLACE[) DTOnE. JN RP. PANEL 10 M
JMSTPU, !R REC DERCRJPTTON OF PPORLFM, TRnUALE ALARM
~ON'T RESET cnRRECTTVE ACTinN,
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---~----------~---
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SALEM GENERATING_ STATION..... __
SAFETY fffL~.TFll Er:llJTPMf:NT wnRK nROER Lnr:;
DEPARTMENT, WORK ORDFR Nn.
DEPT EOUTP~ENT !OENTTFTCATTON Ill II
- CAUSE, cnRREr.TTVF ACTION, r.ALIRRATFn RFCnRnER TA003f, Q_Q_Q____e_ _____ V.ALV E_, ___ LCVJ ____________ ---------------- __.. _______,, ________ ------.. -* ________ -----*-- ___________ -----------..
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!---------------------~
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cnRRECTTVF ACTION, HANDWHFEL ARACKET ROTTOM SCREW HnLES WERE
- r------------------------------------------- _ _____ _____ _
~~~~~~r -~~Mci~~~~ILLFI xrn WHILE NEW_______________________ __________
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sn Page 21 of 26
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l'JRDE R NUMA FR DEPT EDUIPMENT IDENTTFTcnTTON DESCRIPTTON nF PRORLFM, FXPLANAlTON nF wnRK PERFnRMED LOSS OF VOLTA~F ALARMING cnRRECTIVF ACTION, Q2A512 p
VALVE, 11RF1'l ADJUSTED LOSS nF DFTFCTOR VOLTA~E TO REQIJtRFD pnJ NT i
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?G cnRQEr.TTVF flCTJnN, REMOVF.:n, CLEANFD cnNTACT~. AND REPLACEO 1--------------------------------*---------
_. -----*.A61 Q __ MEMORY _ 8011 RD __ IN.DFMlJL TI~LEXER JI"
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11 OESCt;>IPTTON nF PROALEM, llli\\RM CONOITTDN i
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16
.11 cnRPFCTTVF flCTION, TNSTllLLED NEW POS!TIONER /IND LIMIT SWITCH "1-------------------- ------------------ -
*-- ---*----- -------------------------- ---*-* ------------------------*-------------------- -----.------*----~ r~-- :;.:
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Page 22 of 26
>--------------~
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RAFETY ffFLATFU EQUTP~ENT ~nRK nRnEP LO~
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lR 19
~*o OE~CPIPTTON OF PRnRLFM, r.liANNFI OUT nF CAL TRRATtnN
***---. *--- -------*--~-- ------ -- -*- -- --*-*---- - - *-**--*--*-*-*---*--------------
cnRREr.TtVF ACTTnN, TNSTALLEO NEW CONTROLLER
"____9_.3_qll_u__ __ __e ______ H1STRU, ___ 1P..l5.3b.... _____________________________________________ _
1J 75 OESCRTPTTON nF PPORLFM, r.HANNEL OUT nF CALTRRATJn~
f---------'--------------------------------- - ---* --*- ------------------------------------------------------
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AUTO STATinN FllILEn INSTALLED MANUALIAUTD __ STATION,... lNSTALLED --
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Page 23 of 26 1**1 i---,
- 11.
CORRfCTTVF ACTJnN, IMSTRll, 1FM512A
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SALEM GENERATING STATIUN
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SAFETY RFLATFI) flJUTPr~o*r 111np1< n1rnfQ 1_nr, nROER NUMBER OEPT E~UTPMENT rnENTTFTCATlON EXPLANATION "F wnRK PERFnRMEO cnRRECTIVF ACTinN, REPL4CFO J~OL~TOR 1FM512A
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ENTER COMMANOS
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RECOROFR FAJLEO HIGH SATURATE!).HIGH TN~TALLEO NHI TRAM!'IMITTER FROM SllPPL TE!'I
_____ SUF'PORLINSTALL
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TN!'ITALl.fn HANO SFNOER ANO STROKEO VALVE I
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Page '24 of 26
11/1 thru Refueling Outage.
11/30 Page 25 of 26 SALEM UNIT Ill OPERATING
SUMMARY
NOVEMBER 1980
~REFUELING INFORMATION
- November 1980 DOCKET NO. :
50-2 72 UN IT:
Salem 111 DATE:
December 11, 1980 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 Ext. 507
- 1.
Refueling information has changed from last month:
YES NO x
- 2.
Scheduled date of next refueling:
September 1981
- 3.
Scheduled date for restart following refueling:
November 15
- 1981
- 4.
A.
Will Technical Specification changes or other license amendments be required?
YES NO NOT DETERMINED TO-DATE November 1980 B.
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO x
If no, when is it scheduled?
August 1981
- 5.
Scheduled date(s) for submitting proposed licensing action:
August 1981 (If Required)
- 6.
Important licensing considerations associated with refueling:
NONE
- 7.
Number of Fuel Assemblies:
193 A.
In-Core B.
In Spent Fuel Storage
- 104
- 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 26 of 26 8-l-7.R4 September 1982