ML18087A546
| ML18087A546 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 04/10/1981 |
| From: | Midura H Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| Shared Package | |
| ML18087A547 | List: |
| References | |
| 8-1-7.R4, NUDOCS 8211040341 | |
| Download: ML18087A546 (10) | |
Text
r-:-:-.
e PS~G Public Service Electric and Gas Company P. 0. Box #168 Hancocks Bridge, New Jersey 08038 April 10, 1981 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555
Dear Sir:
MONTHLY OPERATING REPORT SALEM NO. 2 DOCKET NO. 50-311 In corrpliance with section 6.9, Reporting Requirements for the Salem Technical Specifications, 10 copies of the following rronthly operating reports for the month of March 1981 are being sent to you.
LKM:pl Average Daily Unit Power Level Operating Da.ta Report Unit Shutdowns and Power Reductions Major Plant Ivbdification Surmnary of Safety Related Maintenance 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, Off ice of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosures Page 1 of 10 8-l-7.R4 The Energy People 95-2189 (5MI 10-79
K>NTH March 1981 AVERAGE DAILY UNIT POWER LEVEL IX)CKET NO.
50-311
~~~~~~~~
UNIT Salem /12 DATE April 10, 1981 COMPLETED BY L. K. Miller TELEPHONE 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 10
.8.1-7.Rl (MWe-NET)
(MWE-NET) 0 17 0
0 18 0
0 19 0
0 20 0
0 21 0
0 22 0
0 23 0
0 24 0
0 25 0
0 26 0
0 27 0
0 28 0
0 29 0
0 30 0
0 31 0
0
50:...311 OCCKE.T ro.: _________ _
CM'E : _Ap...._r_i_l_l_0_,,..._1_9_8_1 __
CCM'IEIED BY:_L~.K~*-M~1~*1~1~e~r.__ __ _
'lEIEPB:NE:
609-365-7000 X507
- l. llnit Nane:
Salem /12 Notes:
- 2.
Reporting Pericd:_.... M
.... a_.r_,c_,h.._. =1~9....
81-..... ________ _
- 3. Licensed 'nlei:nal Poler (!+lt): _
___,.3_4..,..11 _____ _
- 4.
Ncmeplate Rating (Gmss.!fi!) : __
1_1_6_2 _____ _
- 5.
Design Electrical Ratinq (Net Mi'1e) :
1115
- 6.
Max:im1lm. Dependable Capacity '(Gross.!fi!) :_1...,1_4.,..9 ___ _
- 7.
Maximum Dependable Capacity (Net Mi'1e) : _1_1_0_4 __ _
- 8. If Changes Occur :ill Capacity Rat:illgs (Item NUll'ber 3 ~
- 7) Since Last Report, Give Reason:
NONE
- 9.
Power Level To Which Restricted, If Arr.I (Net Mi'1el: __
5~%._..T....,h....
e..,.r...,m..,.a..,J ______________
- 10.
Reasons For Restrictions, If Aey:
Pending Full Powe.r Operating Listense
'lb.is Month Year to Date CUmulati ve ll. Hours In Reporting-Period 744 2160 8329
- 12.
Nul?Cer Of lbJrs Reactor Was Critical 0
0 268.2
- 13.
P.eactor Reserve Shutlbm Ii:lurs 0
0 0
- 14.
Hours Generator On-Line.
0 0
0 lS. llnit Reserve Shutdown Hours 0
0
- 16.
Gross 'lllennal Energy Generated (K-m) 0 0
0
- 17. Gross Electrical Energy Generated~)
0 0
0
- 18.
Net Electrical Energy Generated (!fili) 0 0
- 19. lJnit Service Factor 0
0 0
- 20.
lJnit Avanam lity Factor 0
0 0
- 21. lJnit Capacity Factor (Usinq MOC Net) 0 0
0
- 22. lJnit Capacity Factor (Using DER Net) 0 0
- 23. lJnit Forced Outage Rate 0
0 0
- 24.
Shutdowns Scheduled over Next 6 Mcnths (Type, Date, and Duration of Each) :
- 25. If Shut Down At End of Report Period! Estimated Date of Startllp: ___ N_/ A ____________ _
- 26. lJnits In Test Status (Prior to camercial. Cperati.on):
B-l-7-R2f 10 Pg. 3 0 INITIAL CRITICALI'!Y INITIAL EUX:'l'RICI'l.Y
~
OPERATION Forecast 6/30/$0 9/01/80 NA Achieved 8/2/80 NA NA
NJ.
1 DATE F: Forced s: Scheduled Page 4 of 10 8-1-7.Rl TYP~
2 UNIT SHll'l1XMNS l\\ND PCMER RElXx:rIONS REPORI' MJ!mI March 1981 ME:l'lOO OF OORATIOO
~
SHIJITI~
(IDJRS)
['(MN IU!'J\\C'IDR Reason:
A-Equiptent Failure(Explain) a-Maintenance or Test C-Refueling t>-Regulatory Restriction LICENSE EVEN!'
REPORI' I E-q;>erator Training & Lioonse Examination F-1\\dministrative G-<l>erational Error(Explain) ff-other (Explain)
SYSTEM Cilll'OOENI' roDE4 rooE5 3
~thod:
1-Manual 2-Manual Scram.
3-Automatic Scram.
4-Continuation of Previous Outage 5-Load Reduction 9-0ther 4
N/A DOCKET NO.: 50-311
~---------
- UNIT 1NJ\\ME: -.;=.S=a=l=e=m'-"-#..,_2 ____ _
DATE: April 10, 1981 COMPLETED BY: L.K. Miller TELEPHONE: 609-%'1-7000 X'l07 CAUSE 1\\ND alRRECI'IVE ACTION 'ID PRE.VENI'~
5 Exhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (IER) File (NUREG-0161)
Exhibit 1-Sane Source
MAJOR PLANT MODIFIC~ONS REPORT MONTH March 1981
- DCR NO.
'2ET-0760 2ET-0917 2EC-0940 2EC-1049 2ET-1120 PRINCIPLE SYSTEM Auxiliary Feedwater Condensate Polishing Main Generator Structural Safeguard Equipment Control
- DESIGN CHANGE REQUEST 8-1-7.Rl Page 5 of 10 DOCKET NO:
=i0-31L.
UNIT N~:--~S-a-l~e-m--2--~----~~--~
DATE:
April 10, 1981 COMPLETEn BY:
L.K. Miller
~----~------------~,..--
- J:
TELEPHONE:
609-365-7000 X507 SUBJECT Perform 48 Hour Endurance Test Install Upper Interface Sight Glass Weld Aluminum Plates on Terminal Box for Overheating Problem Add Structural Reinforcing in Block Walls Modify Auto Test Feature
MAJOR PLANT MODIFICATI~
DOCKET~O. :
50-311 UNIT ~:
~s_a_l_e_m_..#_2~~~~~
DATE.:
April 10, 1981 REPORT MONTH~~M~a~rc~h
........ 1~9~8~1~~~~~-
- DCR NO.
2ET-0760 2EC-0917 2EC-0940 2EC-1049 2ET-1120 10CFRSO. 59.
COMPLETED BY:
L.K. Miller TELEPHONE:
609-365-7000 X507 SAFETY EVALUATION This DCR provides for the running of the auxilary feedwater pumps for a 48 hr. endurance test as required by the NRC.
It does not involve either an unreviewed safety or environmental question.
This change involves the installation of an additional sight glass in the condensate polishing system cation regeneration vessel~ This modification does not involve an unreviewed safety question.
The installation does not constitute a new hazard not previously analyzed.
This is a non-safety related system and as such the modification will not affect safety margin or have any safety implications.
Issuance of the DCR provides structural reinforcing to existing block wall in order to protect safety related equipment in the event of an earth quake.
Installation will not affect safe shut down of NSSS equipment or building integrity adversely.
This testing DCR improves reliability of a circuit test functio~, circuit function is not affected.
Does not involve any unreviewed safety or envirpnmental question.
(
Page 6 of 10
- DES!GN CHA.i.~GE REOUEST
WORK ORDER NUMBER 919907 920509 e
939636 939643 942276 942278 942290 942478 942512 DEPT MD MD MD MD MD MD MD MD MD 942513 MD Page 7 of 10 Sl\\Ll!:M GENERATING STATION
. ~ _a f\\.,,.,.,_ "
SAFETY RELATED EQUIPMENT WORK ORDER LOG
- 1vh-,I*\\ 0 l EQUIPMENT IDENTIFICATION 2A SEC Afo.rm Valves, 2csl2 & 13 Pump, No. 24 Service Water Heat Trace Circuit HC-2109 valve, 2NT5
/'
Valve, 2NT26 Hanger Support 2-RHRH-22-34 Valve, 21SJ44 Vital Heat Trace -
ECCS Vital Heat Trace -
ECCS UNIT 2 EXPLANATION OF WORK PERFORMED Descriptiori of Problem
- Trouble alarm will not clear Corrective Action Taken - Vendor did modification on card file Uescription of Problem Leaking Corrective Action Taken - Replaced valves Description of Ptoblc~
Motor upper bepring tcropernture lo high con:oct:..i.vo i\\r.:Uon 'l'nkcn - Oil wan chnngcd Des_cription of Problem Temperature indicators are. below specs Corrective Action Taken -
Replaced.primary and secondary heat tapes De.scription of Problem
- Valve inoperable due to broken li.ahdwheel
~orrective Action Taken -
Replaced valve Description of Problem Failed leak rate test Corrective Action Taken - Applied new disc Description of Problem
- East snubber failed manual stroke test corrective Action Taken - Installed new snubber
.Description of Proble~ -
Leakage Corrective Action Taken Repaired stem limit switch Description of Problem Love controller 2633A, wire #81 indicates zero amps with contactor closed Corrective Action Taken -
Replaced heat tape Description of Problem
- tove controller 26108, wire #17 indicates zero amps with contactor closed Corrective Action Taken -
Replaced heat tape
1.-*
,}..
WORK ORDER NUMBER 942617 942720 942722 e
944392 944393 944435 947562 910671 928261 928262 DEPT MD MD MD MD MD MD MD.
- Page s" of 10 EQUIPMENT IDENTIFICATION 2A SEC Alarm Cabinet Valve, 21SJ134 Valve, 2SJ135
- 21 Boric Acid Transfer Pump j~22 Boric Acid Transfer Pump
- 21 Boric Acid Transfer Pump Valve, 2CS17 Rad Monitoring Valve, 2SW169 Channel 2TM-4125 No; 24 Steam Generator Stearn Dump, 2PT-546B EXPLANATION OF WORK PERFORMED Description of Problem
- Alarm will not clear Corrective Action Taken -
Changed chassis Description of Problem Valve will not close from Control Room Corrective Action Taken -
Replaced torque switch Description of Problem
- Will not close from Control Room Corrective Action Taken - Valve blocked open electrically Description of Problem
- Heater element is not operating Corrective Action Taken -
Reconnected wiring and installed insulation Description of Problem
- Heater element is energized at all times Corrective Action Taken - Thermostats tagged off Description of Problem
.I
- Strip heaters are burned out corrective Action Taken -
Reconnected wiring and installed insulation Description of Problem
- Not operating correctly Corrective Action Taken -
Replaced female disc Description of Problem Repair portabli connection box. #39 connector in containment Corrective Action Taken -
Replaced connector Description of Problem
-. Solenoid valve appears to be stic~ing Corrective Action Taken -
Stroked valve Description of Problem Out of calibration Corrective ~ction Taken -
Replaced 2 capacitors C23 and C24 Description of Problem Channel out of calibration Corrective Action Taken -
Removed controller 40-149 and installed 238
1
~ WORK ORDER NUMBER 932593 939612 939646 942298 942712 942866
-42879 942927 9'14515 DEPT PD
~ -
EQUIPMimT IDEN'rJc-fICATIO!J_
Valve, 22CV160 PD Pump, 21 Charging PD Valve, 21CV160 PD Valve, 22MS10 PD Monitor, 2R5 PD.
RMS 2Rl7A/2Rl7B PD Valve, 22SW57 PD Vn1ve, 21SW49 PD V.:ilve, 2VC11 Pp.ge 9,.of 10 EXPLANATION OF WORK PERFORMED Description of Problem
- Operation is sluggish Corrective Action Taken -*Replaced servo amp Description of Problem Gear drive is leaking oil* out of local temperature indicator Corrective Action Taken -
Tightened temperature well Description of Problem Limit switch not making up Corrective Action Taken - Adjusted limit switch Description of Problem Leaking diaphram Corrective Action Taken -
Replaced diaphram Description of Problem Monitor is alarming with very low reading Corrective Action Taken -
Changed micro processor (MC-6800) and reprogramed 2P.5 J
Description of Problem
- Fail/ackn flashing locally.
Unable to clear "no scan" on CRT Corrective Action Taken -
Replaced damaged pin on back plane of 2Rl7A and cleared RAMS on 2Rl7B
_Description of Problem
- Fails to open Corrective Action Taken - Recalibrated transmitter (PA1634Z)
Description of Problem
- Valve will not respond to increase in header pressure in auto mode COJ"l'.l")(!tlvo /\\ctJ.011 'l'tllrnn -
~l<Jl: controllo1: to contr"l at 130 psi Description of Problem
- Failed leak rate test Corrective Action Taken Reworked operator and limit switches
REFUELING INFORMATION 50-311 DOCKET NO.:
~~
UNIT: Salem 112 DATE: April 10, 1981 COMPLETED BY: L. K. Miller TELEPHONE: 609-365-7000 X507
- 1.
Refueling information has changed from last month:
YES NO X
- 2.
Scheduled date of next refueling:
December 4, 1982
--~~~~~~~~~~~~~~~~~
- 3.
Scheduled date for restart following refueling:
February 27, 1983
- 4.
A.
Will Technical Specification changes or other license amendments be required?
YES.
NO NOT DETERMINED TO-DATE February 1981 B.
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled?
November 1982
~~~~~~~~--~~~~~~~
- 5.
Scheduled date(s) for submitting proposed licensing action:
November 1982 (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 10 of 10 8-l-7.R4 193 0
1,170 1,170 to the spent fuel March 2000