ML18082A717

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Monthly Operating Rept for June 1980
ML18082A717
Person / Time
Site: Salem 
Issue date: 07/10/1980
From: Miller L
Public Service Enterprise Group
To:
Shared Package
ML18082A716 List:
References
NUDOCS 8007150604
Download: ML18082A717 (10)
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Text

AVERAGE DAILY UNIT FOWER. LEVEL OOCKET NO *--=5...._0-_.,2...._7=2 ___ _

UNIT SALEM #1 DATE JULY.10, 1980 COMPLETED BY L.K. MILLER TELEPHONE 609-365-7000 EXT. 507 M:>NTH JUNE, 1980 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 11 8.1-7.Rl (MWe-NET)

  • 1075 1096 1059 1109 1101 1104 1120 367 0

0 355 376 201 347 1105 1081 8007150604 (M.WE-:t-.i'ET) 17 1074 18 1059 19 1117 20 1079 21 1091 22 1121 23 1121 24 1056 25 1104 26 1084 27 1093 28 1120 29 1105 30 1052 31

~ ---------------

~~

0 r:x:;ean-ro. :_5_0_-_2_7....,2 _ __,_-----

CATE : _JUL Y._1_0...;..,_1_9_8_0 __ _

a:ME'LETEDBY:_L_.K_._MI_LLER

'IErEPECNE:

609-365-7000 EXT. 507

l. UnitNane: __________

SALEM

___ #_l ___ _

Notes:

2.

Beportinq Period: _______

JUNE

, _1_9_8_0 __

3. Licensed Therml Power (Molt):

3338

4.

Nal!E!p.late Rating (Gmss M'lel:

1135

s.

Design Electrical Ratinq (Net M'le):

1090

6. Maximmn Dependable capacity '(Gross MWe):

1124

7.

Max:imlml Dependable Capacity (Net MWe):

1079

a. If Olanges Occur :in. Capacity Ratings (Itel!B Nmber 3 Thl:ou;ih 7) Since Last Report, Give Reason:

NONE

9.

Power Ievel To Which :Restricted, If p.ey (Net MWel: -~N~O~!NE.;;;..;.------------------

10.

Reasons For Restrictions, If Aey:

NONE

'!his M:lnth Year to Date CU!mlla.tive ll. Hours In Reporting Period 720 4367 26328 l2.

Nulrber Of Hcurs Reactor was Critical 645.4 4178

. 14266 l3. React:cr Reserve Shuta:iwn :!burs 0

0 22.7

14.

Hou.rs Generator On-Line.

632.3 4058 13,589.1

15. Unit Reserve Shutdown Hours 0

0

16.

Gmss 'lbeJ::mal Energy Generated~)

119831626.4 12,534,328.8 40,070,625.8

17. Gross Electrical Energy Generated (Mm) 671,320 412541340 13,421,840
18.

Net Electrical Energy Generated (?-Ni) 6401941 4,071,530 12,701,120

19. Unit Service Factor 87.8 92.9 51.6
20.

Unit Ava;iahility Factor 87.8 92.9 51.6

21. Unit Capacity Factor (Using MOC Net) 82.5 86.Lt 44.7
22. Unit capacity Factor (Using DER Net)
81. 7 85.5 44.3
23. Unit Forced outage Rate 12.2 7.1 37.3
24.

Shutdowns Scheduled OVer Next 6 M'.:nths (Type, Date, and Duration of Each):

REFUELING - 9/20/80 - 12/7/80

25. If Shut Down At End of Report Period! Estimated Date of Startup:----------------
26. Units In Test Status (Prior to Comercial <:peration):

8-l-7.R2 Pg. 3 of 11 Forecast 9/30/76 11/01/76 12/20/76 Achieved 12/11/76 12/25/76 6,130/77

ID.

DATE 80-120 6-08-80 80-122 6-09-80 80-124 6-11-80 80-128 6-12-80 80-130 6-13-80 80-132 6-14-80 80-134 6.,-15-80 80-136 6-25-80 1

F: Forced S: Scheduled Page 4 of 11 8-1-7.Rl TYPE1 F

F F

F F

F F

F 2

UNIT SllUI'ro'lNS 1\\ND PCMER REOOcrIONS REPORT ID!mI JUNE, 1980 METllOD OF OORATIOO

~

SlltJITIOO

{llXJRS)

IXMN RFJ\\C'IDR 29.25 A

3 39.41 A

4 0

B 5

4.76 H

3 8.90 H

3 5.39 A

3 0

A 5

0 A

5 Reason:

A-Equipient Failure(Explain) a-Maintenance or Test C-Refueling l>-Regulatory Restriction LICENSE SYSTEM ~

EVEN!'

CODE4 CODES REPORT I CH INSTRU AA.

BI..a\\IER CB zzzzzz IA INSTRU EB CKTBRK CH PUMP XX HF FIL'IER HF FIL'IER 3

~thod:

1-Manual E-q>erator Training & License Examination F-J\\dministrative 2-Manual Scram.

3-Automatic Scram.

4-Continuation of Previous Outage 5-Load Reduction 9-0ther G-<lJerational Error{Explain) ff-other {Explain)

DOCKET NO.: 50-272

~~~~~~~~-

UN IT 1NAME:

SALEM #1

~~~~~~~~

DATE:

JUL~ 10, 1980

~~~~====~~-

C 0 MP LET ED BY: L. K. MILLER

~~~~~~~~-

TELEP 110 NE: 609-365-7000 EXT. 507

~~~~~~~~

CAUSE 1\\ND CORROCTIVE ACTIOO 'IO PREVENI' REDJRREOCE INSTRUMENTATION FAILURE DUE TO LIGHTING (S/G CHANNEL PRESSURE CONTROL).

REPAIR #11 FAN COIL UNIT.

REACTOR COOLANT SYSTEM LEAK 'IEST.

TECHNICIAN ERROR DURING FUNOTIONAL 'IES'l OF N INSTRUMENTATION CHANNEL.

lA VITAL 4160 VITAL BUS TRIP.

  1. 12 STEAM GENERATOR PUMP TRIPPED DUE TO IDiJ LEVEL IN GENERATOR.
  1. 12 B CIRC. WA'IER PUMP OUT OF SERVICE DUE TO BROKEN CHAIN DRIVE ON TRAVELING SCREEN.

HIGH DIFFERENTIAL PRESSURE ON #12A

...,IRCUIATOR.

4 EKhibit G - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (Ult) File (NURID-0161)

A.

LOAD REDUCTION 5

Exhibit 1-Sane Source B.

CONTINUATION OF PREVIOUS OUTAGE.

MAJOR PLANT MODIFICAT.NS REPORT MONTH June 1980

  • DCR NO.

PRINCIPLE SYSTEM lED-0079 Chilled Water lED-0261 MSR lED-0306 Ventilation lED-0339 Solid Radwaste lEC-0522 Air Conditioning lEC-0620 Miscellaneous lET-0960 Main Steam lOD-0017 Condenser Air

  • DESIGN CHANGE REQUEST 8-1-7. Rl PAGE 5 of 11 Hanger Removal DOCKET N~ 50-272

---~~~~~~~~~~~~

UNIT NAME:

Salem 1

~~~~~~~~~~~~~

DATE:

JULY 10, 1980

~~~~~~~~~~~~~

  • COMPLETEf1 BY:

L. K. MILLER

~~~~~~~~~~~~~

TELEPHONE:

609~365-7000 EXT. 507 SUBJECT Modify Chilled Wat~r Pump Strainer Modify 13E MSR Install Ventilation Drumming Area Retrofit the Power Control Cables Admin. Building Modify Hangers Per 79-07 Remove #14 Main Steam Flow Ann.

Add Manual Control Valve AR25

NAJOR PLANT MODIFICATWS REPORT MONTH JUNE l~O

  • DCR NO.

10CFR50.59 DOCKET NO.:

50-272 UNIT em:

SALEM # 1 DATE:

JULY 10, 1980 COMPLETED BY:

L.K. MILLER

~~...;..;;"-=-....;..;;.;;;..::;.;;:;;.;;;;,.;;.;.~~~

TELEPHONE:

609-365-7000 EXT.

507 SAFETY EVALUATION r---=-----t-------------------------*~--~--*---------+

lED-0079 New design (functional) has been reviewed and determined not to create new potential malfunctions or increase the probabil-ity of previously analyzed malfunctions or accidents.

lED-0261 All the changes proposed in this DCR are in non-safety related systems and do not interface with any safety related system, therefore, it will not affect the safety evaluation of any other system.

lED-0306 The subject change does not affect any presently performed safety analyzer, nor does it create any new safety hazards.

The bases of the technical specifications are not affected.

lED-0339 The design change will,,increase the l;t.fe expectancy of the crane conductor cables.

It will not change tlle intent of existing technical specification requirementsi contribute to the potential of an.accident, or jeOpaTdize SAR safety analysis made on this system.

lEC-0522 This DCR covers the installation of a new chiller for the Administration Building.

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 per 10 CFR 50.59, lEC-0620 This DCR incorporates design changes to implement provisions of NRC Bulletin IE 79-07 which requires utilities to re-analyze piping systems using algebraic summation to combine earthquake loads.

This DCR is in fact verification of all pipe supports based on criteria mentioned in the above bulletin and, therefore, does not present any unreviewed safety question as a result of changes to pipe support and installations.

lET-0960 The test will not involve the protection system nor other safeguards relative to reactor or plant safety.

lOD-0017 Not safety related and does affect any safety related system.

PAGE 6 f 11

=-**~***-. *'*""--**---~

  • DESIGN CHANGE REQUES'r

SUMMARY

OF SAFETY RELAT. MAINTENANCE UNIT aE:

Salem #1 DEPARTMENT Maintenance REPORT MONTH June 1980 WORK ORDER NO.

906099 912938 912943 912944 912969 913523 914257 914759 194845 915724 917915 918029 918032 920729 EQUIPMENT Spool, Servicewater Pump, 11 Service Water Pump Discharge Spool Airlock, 130 Elevation Valve, 11GB4 lA Sa~eguard Equip-ment c6ntroller Fan, 12 Control Rod vent

,A.nchor, A-CWA-2 Pipe, ;Reactor Coolant Sample Line Da:mper, 1CAA4 Valve, 1 presaure

.Relief 1 Valve, 1 service

. water* 277 Valve, 1SW277 Pump,,Allx.;Ll.;Lary Chem;t.ca,l Feed *

,Alc;i._rm, 13 Reactor Coolant Delta T PAGE 7 of 11 DATE:

July l:o, 1980 COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 FAILURE DESCRIPTION Erosion Corrosion Downstearn of Valve Expansion Joint Cracked on Discharge Spool Air Leaks Past Seals Stearn Leak by Lubricator lA SEC Failed Failed to Get Stop Indication. Fan Did Stop Sleeves Need Grouting Reactor Coolant System Hot Leg Sample Line Had Broken the Seal Weld Between Itself and Its Penetration Sleeve Goes to Midposition and Stops Flex Tubing and Pipe Thread on Valve Needs to be ;Rethreaded Check Valve Stuck Shut Leaking Thru pump Blowing '.Fuses Console Alarm For Loop 13 Deviation Delta T Will Not Corne Up When Bistable 1TC431K/J Output No.

1 is Tripped CORRECTIVE ACTION Coated with Belzona, Replaced to Original State Installed New Expansion Joint Reversed Seals on Inner Door and Adjusted Seals Remove Lube Line and Installed Pipe Plug Replaced lA SEC with

  1. 2C Position Adjusted Limit Switch on Damper 1CAA007 Anchor A-CWA-2 Was Grouted Sample Line Cut Bet~

ween Int. Containment Isolation Valve and Penetration Sleeve and Line Capped and Seal Welded Reset Louver to Fully Close and Make Up Limits, Oiled Hinged Parts Installed Flex Tubing Cleaned Valve Disassembled Check Valve. Cleaned Valve Parts. Reassembled.

Replaced Fuses to Operate Pump. New Motor on Order.

Replaced Board Jll

~*

~MMARY OF SAFETY.RELAT.MAINTENANCE UNIT Salem #1 DEPARTMENT Maintenance DATE

July LO, 1980 REPORT MONTH June 1980

~~~~~~~~~~-

COMPLETED BY:

L. K. Miller TELEPHONE:

609-365-7000 X507 WORK ORDER NO.

EQUIPMENT 935202 Pump, 16 Service Water 935228 Pump, 13 Service

  • Water 935249
  • Valve, 13MS168 935258 Pump, 11 Boric Acid Tra.nst,er 935368 Air Conditioning, Control Room 935452 Condenser, l2 Chiller 935597 Condenser, 12 Chi.ller 935630 Condenser, 12 Ch:;i:ller 936058 Valve, 12M$167 936146 Pump, ll R,HR Sump Pwqp PAGE 8 of 11 FAILURE DESCRIPTION Packing Leak Vibration of Lower Pump Bearing Packing Leak Base Mounted Strip Heaters Failed Abnormal Pushbutton Indication. No Light When Depressed and other Lamps Get Dimmer While Button is Depressed. Faulty Rela,y Replace Weld Neck Flange Below Valve 12SW93, in Conjunction with Detlciency Report MD0766 Replace Weld Neck Flanges on Service Water Inlet and Out-let to 12 Chiller Condenser Repair Weld Neck Flange Weld. Welded Originally With E-7018. Should be E-6010 Valve Did Not Close in the Required 5 Sec.

Sump Pump Way Below Capacity CORRECTIVE ACTION Repacked Rebuilt Lower Bowl Assembly Adjusted Packing Chipped Up Boric Acid and Replaced Strip Heaters Replaced Operate/

Reset Dunco Relay for Control Room Air Conditioning Cleaned and Welded with 7018 Wire As Instructed Cut Out Old Weld and Rewelded Added 11 Gallons of Oil Pulled Sump Pump, Cleaned Suction Screen

~~MMARY OF SAFETY RELAT.MAINTENANCE UNIT N.E:

Salem #1 DEPARTMENT Perf or.mance DATE:

July i'G 198 O REPORT MONTH June 1980

~~~~~~~~~~-

COMPLETED :J3X:

L. K.. Miller TELEPHONE:

609-365-7000 X507 WORK ORDER NO.

911529 913599 914744 914825 920726 920727 93 53 65 EQUIPMENT Instru., 1FE499A Valve, 13SW223 Valve, 14SW223 Valve, 13MS007 ln$tru.ment, 1LC527C 12 Stea.m Gene:r;-ator,

Feedwater Flow Doric Point 134 PAGE 9 of 11 FAILURE DESCRIPTION Flange Leak Flexatallics Worn When 13 Fan Coil Unit Stopped Overhead Annunciator Did Not Alarm When 14 Fan Coil Unit Stopped Overhead Annunciator Did Not Alarm Regulator Indicates 90 PSIG While Other Valve CllMS7 )_

Indicates 32 PSIG While Performing Procedure lPD-2.2.043 on 12 Steam Generator Level Channel IV, the Trip point Was Found to be Lower Than Technical Specif ica-tion Limits Alarm Delayed 2-3 Mins After Bi Stable Tripped Doric Alarming for Circuit 201 at 130 Degrees F CORRECTIVE ACTION Replaced Both Flexatallics Replace Limit Switch Adjusted Limit Switch Replaced Regulator Diaphragm Replaced Capacitors in Power Supply Changed AN078 Card Replaced Thermocouple

6/1 thru 6/7 SALEM UNIT #1 OPERATING SUMMA.RY JUNE 1980 Load stabilized at 100%.

6/8 Rx trip, S.I. at 0845.

First out indica,tion wa,s stean:i diff. pressure.

Received reports of lightning striking containment dome.

6/9 thru 6/10 6/11 6/12 6/13 6/14 thru 6/15 6/16 thru 6/30 Reactor remained in shutdown condition~ Mode 3.

Load escalated to 50%.

Turb. trip, Rx trip @ 1906 while performing surveilance on OT~T.

Rx critical @2100 and began escalating load.

Load escalated to 69% until Rx trip at 1506 while performing surveilance on SEC cabinets.

Rx critical at 2332 and commencing load escalation.

Load escalation continued until approximately 1000 on 6/15/80, load was stabilized at 100%.

Load stabilized at 100%.

PAGE 10 of 11

~UELING INFORMATION DOCKET NO. :.... 5~0'--.... 2""'72.._ ___ _

UNIT: SALEM #1 DATE: JULY 10, 1980 COMPLETED BY: L. K. MIILER TELEPHONE: 609-365-7000 EXT. 507 MONTH:

JUNE 1980

1.

Refueling information has changed from last month:

2.
3.
4.

YES NO x

Scheduled date of next refueling:

SEPTEMBER 20, 1980 Scheduled date for restart following refueling:

DECEMBER 7, 1980 A.

Will Technical Specification changes or other license amendments be required?

YES NO ---

NOT DETERMINED TO-DATE JUNE 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 1980

~----------------~------~----

5.

Scheduled date(s) for submitting proposed licensing action:

SEPTEMBER 1980 (IF REQUIRED)

6.

Important licensing considerations associated with refueling:

NONE

7.

Number of Fuel Assemblies:

A.

In-Core.

193 B.

In Spent Fuel Storage 40

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:

SEPTEMBER 1982 Page 11 of 11 8-l-7.R4

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