ML18086A493

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Apr 1981
ML18086A493
Person / Time
Site: Salem PSEG icon.png
Issue date: 05/11/1981
From: Miller L
Public Service Enterprise Group
To:
Shared Package
ML18086A492 List:
References
NUDOCS 8105180179
Download: ML18086A493 (12)
v • d • e


Text

    • .*.. -.

MONTH April 1981..

AVERA.GE DAILY UNIT POWER LEVEL DOCKET NO. 50-272.*

UNIT Salem #i DATE May 11, 1981 CQ\\IPLETED 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 13 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

29 267 30 852 31

l. Unit Nane:

Salem lfl

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

. 2.

Reporting Period:

April 1981

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

3. Licensed 'nlerl!al Power (!fit):

3338

~-----

4.

Nalleplate Ratinq (Gmss !<fie):

1135

---=~'------

5.

Design El.ectrical Rating (Net !<fie):

1090

6. Max:inun Dependable Capacity 1Gross !<fie): 1124
7.

Maxim1Jm Dependable Capaci. ty (Net K'le) : 0-7 9----

Notes:

DATE :

May J J, 1 QRl ca-lPIEl'EDBY: L.K. Miller

~:

609-365-7000 X507

8. If Changes Occur :in Capacity Ratings (Itel!B NUl!Cer 3 'lmotJ;h 7) Since Last Report, Give Reason:

NONE

9.

Power Level To Which Restricted, If Mr:! (Net I-fie) : _ ___;N;.;.O.;;.;N:..:.:E=-------------------

10.

Reasons For Restrictions, If Aey: __

N_;/_A _______________________ _

This M:lnth Year to Date Ctmll.ati ve

11.

Hours In Reporting Period 719 2,879 33,624

12.

Numer Of Hours Psactor Was Critical 60.7 1,960.l 18,389.1

13.

Reactor Reserve Shutcbm :Ei:>urs 592.3 682.2 704.9

14.

Hours Generator On-Line.

4.0.2 1,878.0 17,487.2

15. Unit Reserve Shutdown Hours O.Q a.a 0.0
16. Gross 'IMcmal Energy Generated(mH) 94,25Q 5,669,9Z~

SL 577

  • 201. 8
17.

GJ:Css Elect:rical Energy Generated cz.Ni) 292000 129022450 17,0482170

18. Net Elect:rical Energy Generated(MWH) 20,862 1,809,938 16,118,761
19. Unit Service Factor 5.6 65.2 52.0
20.

Unit Avaj Jam Ji ty Factor 5.6 65.Z 52.0

21. Unit Capacity Factor (Using MOC Net) 2.7 58.3 44.4
22. Unit Capacity Factor (Using DER Net)
2.

57.Z 44.0

23. Unit Forced OUtage Rate 94.4 34.8 35.0
24. Shutdowns Scheduled over Next 6 M::l'lths (Type, Date, and Duration of Each) :

Refueling, 10/31/81, 8 Weeks

25. If Shut Dcwn At End of Report Period! Estimated Date of Start1Jp: ---------------.---
26.

Units In Test Status (Prior to camerci.al Q;leration):

S-l-7.R2 Pg. 3 of 13 Forecast 09/30/76 ii/Ol/76 12/20/76 Achieved 12/11/76 12/25/76 06/30/77

NJ.81-071 81-073 81-075 1

lll\\TE.

3/28/81 4/29/81 4/30/81 F:

Forced SI Scheduled Page 4 of 13 8-1-7.Rl TYP~

F F

F 2

UNIT SllU'ltX)iNS l\\ND PrnER RErix:TIONS REPORr KXmIApril 1981 ME:l1DD OF WRATION

~

SHlJlTIOO LICENSE SYSTliM CI:Ml'CMNl' ooms>

lXMN RFJIC'IDR 670.9 A

4 7.9 A

.3 0.0 A

5 Reason:

A-Equipient Failure(EKplain)

&-Maintenance or Test C-Refueling D-Regulatory Restriction EVm1' REPORr I E-Q?erator Training & Lioense Examination F-Mninistrative

~ational Error(EKplain)

IHJther (Explain) c:mE4

. CXDES HA TURBIN CH VALVOP HH FILTER

~

3 Mathod:

1-Manual 2-Manual Scram.

3-Automatic Scram.

4-Con*tinuation of Previous Outage 5-Load Reduction 9-0ther DOCKET NO. :_5_0_-_2_7_2 _____ _

Salem /fl UNIT'NAME:

DATE:

May 11, 1981 COMPLETED BY: L.K. Miller TELEPHONE: 609-365-7000 X507 CNJSE Ml> <DRml:TlVE l\\CTION 'ID PREVml' RmJRREJCE

  1. 13 Low Pressure Turbine Blade Repair Main Feed Regulator Valve Malfunction Causing LOW~Low Level In #11 Steam Generator Clean Condensate Pump Suction Strain~...
  • ers 4

Exhibit G - Instructions for Preparaticm of Data Entry Sheets for Lioensee Event Report (Int> File (NURm.0161>

5 Exhibit 1-Saaoo Source

'. I

)

f II l

.1

\\

i l

'l MAJOR PLANT MODIFICA'4tiNs REPORT MONTH April 1981

  • DCR NO.

PRINCIPLE SYSTEM 1ED-0102A Steam Generator Drains lED-0170 Air Conditioning lED-0259 Reactor Coolant lED-0299 lEC-0403 lEC-07 53 lEC-0973 lEC-0996 lEC-1091 Emergency Lighting Circulating Water Residual Heat Removal Sampling System Steam Generator Feed-water Electrical Power 1SC-0080A Demineralized Water lSC-0453 Reactor Coolant

  • DESIGN CHANGE REQUEST 8-1-7. Rl Page 5 of 13 609-365-7000 X507 SUBJECT Recovery of Continuous Blowdown Replace Control Room Intake Duct Addenda to Steam Generator Instruction Manual Install Battery Pacs Install a Strainer at 13B Circulating Water Traveling Screen Modification to RHR Sump Revise Sample Lines Thru Contain-ment Wall Plug Top Threaded Conax Connection on No. 13 Steam Generator Feed Nozzle Remove Resistor Rl8 from all Tranistat Thyristor Firing Circuits Modify Discharge of Mixed Bed Acid Pump Authorize use of Westinghouse Coupling

50-272 DOCKETJj.:

UNIT N

~MAJO~ PLANT MODIFICATIOAt Salem Ill

  • DCR NO.

1ED-0102A lED-0170 lED-0259 lED-0299 lEC-0403 lEC-0753 lEC-0973 lEC-0996 lEC-1091 1SC-0080A lSC-0453 April* 1981

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

DATE:

May 11, 1981 COMPLETED BY:

L. K. Miller

~--------=--=:;--~~~~

TELEPHONE:

609-365-7000 X507

~~~--....... -.....:...:;~_..:.;=..:;:......~

10CFRSO. 59.

SAFETY EVALUATION Implementation of this DCR will not affect the safe shutdown of the NSSS equipment or pose a health hazzard to the general public.

This DCR does not involve any unreviewed safety or environmental question.

This changes~neither design nor operating setpoints but rather describes maintenance procedures.

There is no unreviewed safety question.

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.

The installation of a strainer at the 13B traveling water screen does not create any safety hazzard no*r alter the basic function of the system.

This DCR covers changes and additions to the anti-vortex baffles and trash screens in the containment sump previously done under DCR lED-0699.

These changes improve the functioning and reliability of the RHR system and do not alter the structural integrity of the containment.

No.unreviewed safety question is introduced.

This design change removes the 3/8 tube from the sampling'penetration and replaces it with existing 3/4" or l" sch. 80 pipe.

This change does not affect the sampling capabilities no:r does it affect any safety related functions or create any new safety hazzards.

This design change does not alter the function of the existing system to operate as intended. -No unreviewed safety question is involved.

An unreviewed safety question is not involved for two reasons.

First, the resistor in the design change request is being exchanged with one of the same nominal value, except for its heat dissipation characteristics.

Therefore, the circuit will perform as before~

Second, the voltage reg-ulator circuit is not in, nor interacts with, any safety related systems.

This change involves the replacement of the. demineralized water plant-acid piping (mixed bed and cation) with teflon lined, epoxy coated carbon steel piping, valves, fittings, etc..This change does not involve an unreviewed safety question, alter the technical specifications or degrade in any manner, the S~lem Demin. Water Plant.

The new coupling (6119D31 Group 1) meets or exceeds the requirements of the existing Marmon clamp device.

This change does not involve an unreviewed safety or environmental question.

Page 6 of 13

WORK ORDER NUMBER 920980 928643 939516 939591 939592 939629 942234 942246 942247 942248 DEPT MD MD MD MD MD MD MD MD MD SALEM GENERATING STATION SAFETY RELATED EQUIPMENT WORK ORDER LOG UNIT 1 EQUIPMENT IDENTIFICATION EXPLANATION OF WORK PERFORMED Incore Flux Thimbles Valve, 14MS9 I,

Valve, 12NT18 Heat Trace Circuit No. 623 Heat Trace Circuit No. 624 Valve, 11Gl33 Valve, 1CV68 Va). ve, 1CV7 O Vi'!.lve, 1CV73 Description of Problem Clean all flux thimbles Corrective Action Taken -

Cleaned flux thimbles Description of Problem

- valve leaking steam Corrective Action Taken -

Replaced valve Description of Problem

- valve leaking corrective Action Taken - Tightened packing Description of Problem

- Temperature erratic corrective Action Taken -

Replaced insulation Description of Problem

- Temperature erratic Corrective Action Taken -

Replaced insulation Description of Problem

- Bonnet leak Corrective Action Taken - Installed new gasket Description of Problem

- Packing leak corrective Action Taken -

Repacked Description of Problem

- Packing leak Corrective Action Taken -

Repacked Description of Problem

- Packing leak Corrective Action Taken -

Repacked Description of Problem

- Packing leak Corrective Action Taken -

Repacked I

Paqe 7 of 13

WORK ORDER NUMBER DEPT EQUIPMENT IDENTIFICATION EXPLANATION OF WORK PERFORMED 942260 MD

  1. 12 Residual Heat Removal Description of Problem

- Suction flange leak Pump Corrective Action Taken -

Replaced gasket 942332 MD Valve, lPRl Description of Problem Leaks thru Corrective Action Taken -

Replaced internals 943741 MD Containment Air Lock Description of Problem

- Excessive leakage f,.. I Corrective Action Taken -

Replaced door seals I lo\\

943762 MD Valve, 11MS178 Description of Problem Leaking steam Corrective Action Taken -

Furrnanited valve 943770 MD Valve, 1CV256 Description of Problem

- 0utlet line leaks Corrective Action Taken Welded line 943824 MD Valve, 1CV54 Description of Problem

- Packing leak Corrective Action Taken -

Repacked valve 943825 MD Valve, 1CV56 Description 0f Problem

- Packing leak Corrective,Action Taken -

Repacked valve 944836 MD Valve, 1CV68 Description 0f Problem No close light Corrective,Action Taken Reworked valve internals 945050 MD Heat Trace Circuit No. 602 Description of Problem

- Heat trace tape faulty Corrective Action Taken -

Replaced heat trace tape 945069 MD No. ':{a D;tesel Generator Description of Problem

- Diesel won't trip Corrective Action Taken -

Replaced faulty relay 945169 MD 11 pervice Water Strainer Description 0f Problem Drain line plugged C0rrective Action Taken -

Cleared line

WORK ORDER NUMBER 945271 945724 945745 945746 945756 945778 945792 945874 945941 947757 947865 DEPT MD MD MD MD MD MD MD

!1D MD MD EQUIPMENT IDENTIFICATION No. 13 Nozzle Support Fan No. 12 Auxiliary Building Exhaust Fan Boric Acid Evaporator Heat Trace 1:. **I No. 11 Boric Acid Concentrates Pump Heat Trace Auxiliary Feed Pump Room Cooler Valve, 1CV56 valve, 1R.H33 NO. 15 Service Water Pump No. lB Diesel Generator No. ;1.l"* Component cool.;i..ns.

Pump Valve, l2,1\\F23 EXPLANATION OF WORK PERFORMED Description of Problem

- Excessive noise in operation Corrective Action Taken - Replaced bearings Description of Problem

- Belts broken Corrective Action Taken -

Replaced belts Description of Problem

- Temperature not being maintained Corrective Action Taken - Insulated faulty ~t~rs Description of Problem

- Temperature not being maintained Corrective Action Taken - Insulated faulty lines Description of Problem

- Leaking Corrective Action Taken Replaced gasket Description of Problem Pa.eking leak Corrective Action Taken - Repacked Description of Problem

- Packing leak Corrective Action Taken - Repacked Description of Problem

- Will not start Corrective Action Taken -

Repl.aced faulty relay Description of Problem

- Failed alarm Cor;rective Action Taken - Replaced blown fuse Desc:i;iption of Probl.em

- Breaker indicates tri 0pped corrective Action Taken - Repaired faulty switch Description of Problem Corrective Action Taken Blowing steam Repacked valve Pa,ge 9 of 13

WORK ORDER NUMBER 947904 947916 947941 947991 928320 928325 928396 928423 934517 934546 942431 DEPT MD MD MD MD PD PD PD l'P PD l'P l'D EQUIPMENT IDENTIFICATION Valve Lock Out Switches Valve, lPS28 Electrical Penetration I-9 1:..I No. 13 Steam Generator Feed-water Nozzle Valves, 11 & 13BF40 Valve, 12BF40 Power Range Channel 1N43 Recorder NR45 Radiation Monitor 1R32B 1,,

~I*

Valve, l2MS10 No. l Turntng Gea~ 1\\mmeter t"

EXPLANATION OF WORK PERFORMED Description of Problem Switches not operating Corrective Action Taken -

Replaced internal Micro-Switches Description of Problem

- Packing leak Corrective Action Taken -

Replaced valve Description of Problem

- Test valve broken off Corrective Action Taken -

Replaced valve I II:

Description of Problem

- Furmanite connection leaking Corrective Action Taken - Furmanited connection Description of Problem

- valves will not shut Corrective Action Taken -

Changed springs on positioners Description of Problem

- Valve will not shut Corrective Action Taken -

Changed spring on positioner Description of Problem

- Trip point low Corrective Action Taken - Adjusted bistable trip points Description of Problem Recorder running slow Corrective Action Taken -

Replaced chart drive Description of Problem Continuously in alarm Corrective Action Taken - *Repaired shorted connection Description of Problem

~eaking diaphram Corrective Action Taken - Tightened bo~ts on valve operator Description of Problem Not registering correctly Corrective Action Taken -

Replaced meter Page 10 ofl3

i WORK ORDER NUMBER 943827 943831 944840 945061 945087 945126 945795 945906 947760 947790 947942 DEPT PD PD PD PD PD PD PD PD PD PD PD EQUIPMENT IDENTIFICATION Valve, 1CV7 No. 12 Auxiliairy Feedwater Pump Meter control Bank A I :.

~ ' I valve, 11MS18 Radiation Monitor 1R21 No. 13 Fan Coil Unit Flow Transmitter Valve, l2SW122 Valve, 11SW305 No. 15 Fan Coil Unit Damper Operator 1 1 1

~ r..

No. 1 Air Particulate Pump Valye, 1CV7l EXPLANATION OF WORK PERFORMED Description of Problem No open/close indication Corrective Action Taken -

Cleaned limit switches Description of Problem

- Pegged high Corrective Action Taken Replaced amplifier in transmitter Description of Problem

- Control console indication faulty Corrective Action Taken -

Replaced converter board I II I Description of Problem No open light Corrective Action Taken - Adjusted limit switch Description of Problem

- Indicates less than zero Corrective Action Taken -

Replaced detector Description of Problem

- Indicates zero while in service Corrective Action Taken - Tightened input resistor connection Description of Problem Flow indication is backwards Corrective Action Taken -

Blew down transmitter Description of Problem

- Valve won't close Corrective Action Taken - Air supply valve was restroked Description of Problem

- Air leak Corrective Action Taken - Repaired leak Description of Problem Pump does not developsufficient flow Corrective Action Taken -

Replaced pump Description of Problem Air line leak Corrective Action Taken -

Replaced air line Page llof 13

4/1 SALEM UNIT fll OPERATING

SUMMARY

~RIL 1981 thru Outage - Unit in Cold Shutdown due to turbine repairs.

4/23 4/24 4/26 4/27 4/28 4/29 4/30 1600 1300 2335 1845 2355 0335 Commenced Reactor heatup.

Reactor critical.

Reactor trip (from 6% RTP) on low steam generator levels.

Reactor cooldown due to PS 8 valve stem packing., leak.

Reactor heatup.

Reactor critical.

Turbine on line, increasing power.

Reactor trip (From 27% RTP) on steam generator low-low levels following main feed regulator valve problems.

0645 Reactor critical.

1130 Turbine., on line, increasing power to 100% RTP..

0550 Reactor at steady state, -100% RTP.

1120 Decrease power to 70% RTF to clean condensate pump strainers.

1400 Steady state, 70% RTP; 1700 Increase power to 100% RTF.

2140 Steady state, -100% RTP.

Page 12 of 13

l._

REFUELING~INFORMATION April 1981 DOCKET NO.:

50-272 UN IT:

Salem #1 DATE:

May 11. 1981 COMPLETED BY: L

  • K
  • Miller TELEPHONE: 609-365-7000 X507
l.

Refueling information has changed from last month:

YES X

NO

2.

Scheduled date of next refueling:

Oct. 30, 1981

3.

Scheduled date for restart following refueling:

Jan. 10, 1982

4.

A.

Will Technical Specification changes or other license amendments be required?

YES NO ---

NOT DETERMINED TO-DATE April 1981 B.

Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO x

If no, when is it scheduled?

September 1981

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

5.

Scheduled date(s) for submitting proposed licensing action:

September 1981 (If Required)

6.

Important licensing considerations associated with refueling:

NONE 7.-

Number of Fuel Assemblies:

A.

In-Core 193 B.

In Spent Fuel Storage

  • 104
8.

Present licensed spent fuel storage capacity:

1170

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

Future spent fuel storage capacity:

_____ 1_1_1 __

0 ______________ _

9.

Date of last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity:

Page 13 of 13 8-l-7.R4 September 1996

Retrieved from "https://kanterella.com/w/index.php?title=ML18086A493&oldid=5011057"