ML18086A493

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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)
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Text

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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 MONTH April 1981 ..

DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-NET) (MWE-NET) 1 0 17 0 2 0 18 0 3 0 19 0 4 0 20 . 0 5 0 21 0 0 0 6 22 0 0 7 23 8 0 24 0 9 0 25 0

10. 0 26 0 11 0 27 0 12 0 28 0 13 0 29 267 0 852 14 30
15. 0 31 16 0 Pg. 2 of 13 8.1-7.Rl

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

~: 609-365-7000 X507

l. Unit Nane: Salem lfl Notes:

. 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) : 0-79----
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.ative 719 2,879 33,624

11. Hours In Reporting Period
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):

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

UNIT SllU'ltX)iNS l\ND PrnER RErix:TIONS DOCKET NO. :_5_0_-_2_7_2_ _ _ _ __

REPORr KXmIApril 1981 UNIT'NAME: Salem /fl . I DATE: May 11, 1981 COMPLETED BY:

TELEPHONE:

L.K. Miller 609-365-7000 X507

)

ME:l1DD OF WRATION SHlJlTIOO LICENSE SYSTliM CI:Ml'CMNl' CNJSE Ml> <DRml:TlVE NJ. lll\TE. TYP~ ooms> ~ lXMN EVm1' c:mE4 . CXDES l\CTION 'ID RFJIC'IDR REPORr I PREVml' RmJRREJCE 81-071 3/28/81 F 670.9 A 4 - - - HA TURBIN #13 Low Pressure Turbine Blade Repair 81-073 4/29/81 F 7.9 A .3 - - - CH VALVOP Main Feed Regulator Valve Malfunction Causing LOW~Low Level In #11 Steam f

81-075 4/30/81 F 0.0 A 5 - - - HH FILTER Generator Clean Condensate Pump Suction Strain~ ...

  • I

~

ers Il

.. .1

\

1 2 3 4 5 F: Forced Reason: Mathod: Exhibit G - Instructions Exhibit 1-Saaoo Source

  • SI Scheduled A-Equipient Failure(EKplain) 1-Manual for Preparaticm of Data

&-Maintenance or Test Entry Sheets for Lioensee C-Refueling 2-Manual Scram. Event Report (Int> File D-Regulatory Restriction 3-Automatic Scram. (NURm.0161>

E-Q?erator Training & Lioense Examination 4-Con*tinuation of F-Mninistrative Previous Outage

~ational Error(EKplain)

IHJther (Explain) 5-Load Reduction 9-0ther Page 4 of 13 8-1-7.Rl

MAJOR PLANT MODIFICA'4tiNs REPORT MONTH April 1981 609-365-7000 X507

  • DCR NO. PRINCIPLE SYSTEM SUBJECT 1ED-0102A Steam Generator Drains Recovery of Continuous Blowdown lED-0170 Air Conditioning Replace Control Room Intake Duct lED-0259 Reactor Coolant Addenda to Steam Generator Instruction Manual lED-0299 Emergency Lighting Install Battery Pacs lEC-0403 Circulating Water Install a Strainer at 13B Circulating Water Traveling Screen lEC-07 53 Residual Heat Removal Modification to RHR Sump lEC-0973 Sampling System Revise Sample Lines Thru Contain-ment Wall lEC-0996 Steam Generator Feed- Plug Top Threaded Conax Connection water on No. 13 Steam Generator Feed Nozzle lEC-1091 Electrical Power Remove Resistor Rl8 from all Tranistat Thyristor Firing Circuits 1SC-0080A Demineralized Water Modify Discharge of Mixed Bed Acid Pump lSC-0453 Reactor Coolant Authorize use of Westinghouse Coupling
  • DESIGN CHANGE REQUEST 8-1-7. Rl Page 5 of 13

DOCKETJj.: 50-272

~MAJO~ PLANT MODIFICATIOAt UNIT N  : Salem Ill April* 1981 ~~~~~~~~~~~~

DATE: May 11, 1981 COMPLETED BY: L. K. Miller

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

TELEPHONE: 609-365-7000 X507

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

  • DCR NO. 10CFRSO. 59. SAFETY EVALUATION 1ED-0102A Implementation of this DCR will not affect the safe shutdown of the NSSS equipment or pose a health hazzard to the general public.

lED-0170 This DCR does not involve any unreviewed safety or environmental question.

lED-0259 This changes~neither design nor operating setpoints but rather describes maintenance procedures. There is no unreviewed safety question.

lED-0299 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-0403 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.

lEC-0753 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.

lEC-0973 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.

lEC-0996 This design change does not alter the function of the existing system to operate as intended. -No unreviewed safety question is involved.

lEC-1091 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.

1SC-0080A 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.

lSC-0453 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

SALEM GENERATING STATION SAFETY RELATED EQUIPMENT WORK ORDER LOG UNIT 1 WORK ORDER EXPLANATION OF WORK PERFORMED NUMBER DEPT EQUIPMENT IDENTIFICATION 920980 MD Incore Flux Thimbles Description of Problem - Clean all flux thimbles Corrective Action Taken - Cleaned flux thimbles 928643 MD Valve, 14MS9 Description of Problem - valve leaking steam Corrective Action Taken - Replaced valve I,

939516 MD Valve, 12NT18 Description of Problem - valve leaking corrective Action Taken - Tightened packing 939591 MD Heat Trace Circuit No. 623 Description of Problem - Temperature erratic corrective Action Taken - Replaced insulation 939592 MD Heat Trace Circuit No. 624 Description of Problem - Temperature erratic Corrective Action Taken - Replaced insulation 939629 MD Valve, 11Gl33 Description of Problem - Bonnet leak Corrective Action Taken - Installed new gasket 942234 MD Valve, 1CV68 Description of Problem - Packing leak corrective Action Taken - Repacked 942246 MD Va). ve, 1CV7 O Description of Problem - Packing leak Corrective Action Taken - Repacked 942247 MD Description of Problem - Packing leak Corrective Action Taken - Repacked 942248 Vi'!.lve, 1CV73 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 #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 Corrective Action Taken - Replaced door seals I lo\

f, .. I 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 DEPT EQUIPMENT IDENTIFICATION EXPLANATION OF WORK PERFORMED 945271 MD No. 13 Nozzle Support Fan Description of Problem - Excessive noise in operation Corrective Action Taken - Replaced bearings 945724 MD No. 12 Auxiliary Building Description of Problem - Belts broken Exhaust Fan Corrective Action Taken - Replaced belts 945745 MD Boric Acid Evaporator Heat Description of Problem - Temperature not being maintained Trace Corrective Action Taken - Insulated faulty ~t~rs 1:. **I 945746 MD No. 11 Boric Acid Description of Problem - Temperature not being maintained Concentrates Pump Heat Trace Corrective Action Taken - Insulated faulty lines 945756 MD Auxiliary Feed Pump Room Description of Problem - Leaking Cooler Corrective Action Taken Replaced gasket 945778 MD Valve, 1CV56 Description of Problem Pa.eking leak Corrective Action Taken - Repacked 945792 MD valve, 1R.H33 Description of Problem - Packing leak Corrective Action Taken - Repacked 945874 !1D NO. 15 Service Water Pump Description of Problem - Will not start Corrective Action Taken - Repl.aced faulty relay 945941 MD No. lB Diesel Generator Description of Problem - Failed alarm Cor;rective Action Taken - Replaced blown fuse 0

947757 MD No. ;1.l"* Component cool.;i..ns. Desc:i;iption of Probl.em - Breaker indicates tri pped Pump corrective Action Taken - Repaired faulty switch 947865 Valve, l2,1\F23 Description of Problem Blowing steam Corrective Action Taken Repacked valve Pa,ge 9 of 13

t" WORK ORDER NUMBER DEPT EQUIPMENT IDENTIFICATION EXPLANATION OF WORK PERFORMED 947904 MD Valve Lock Out Switches Description of Problem - Switches not operating Corrective Action Taken - Replaced internal Micro-Switches 947916 MD Valve, lPS28 Description of Problem - Packing leak Corrective Action Taken - Replaced valve 947941 MD Electrical Penetration I-9 Description of Problem - Test valve broken off Corrective Action Taken - Replaced valve I II:

1: . .I 947991 MD No. 13 Steam Generator Feed- Description of Problem - Furmanite connection leaking water Nozzle Corrective Action Taken - Furmanited connection 928320 PD Valves, 11 & 13BF40 Description of Problem - valves will not shut Corrective Action Taken - Changed springs on positioners 928325 PD Valve, 12BF40 Description of Problem - Valve will not shut Corrective Action Taken - Changed spring on positioner 928396 PD Power Range Channel 1N43 Description of Problem - Trip point low Corrective Action Taken - Adjusted bistable trip points 928423 l'P Recorder NR45 Description of Problem - Recorder running slow Corrective Action Taken - Replaced chart drive 934517 PD Radiation Monitor 1R32B Description of Problem - Continuously in alarm Corrective Action Taken - *Repaired shorted connection 1 ,, ~I* , ..

934546 l'P Valve, l2MS10 Description of Problem - ~eaking diaphram Corrective Action Taken - Tightened bo~ts on valve operator 942431 l'D No. l Turntng Gea~ 1\mmeter Description of Problem - Not registering correctly Corrective Action Taken - Replaced meter Page 10 ofl3

WORK ORDER NUMBER DEPT EQUIPMENT IDENTIFICATION EXPLANATION OF WORK PERFORMED 943827 PD Valve, 1CV7 Description of Problem - No open/close indication Corrective Action Taken - Cleaned limit switches 943831 PD No. 12 Auxiliairy Feedwater Description of Problem - Pegged high Pump Meter Corrective Action Taken Replaced amplifier in transmitter 944840 PD control Bank A Description of Problem - Control console indication faulty Corrective Action Taken - Replaced converter board I II I I :. ~ ' I 945061 PD valve, 11MS18 Description of Problem - No open light Corrective Action Taken - Adjusted limit switch i !

945087 PD Radiation Monitor 1R21 Description of Problem - Indicates less than zero Corrective Action Taken - Replaced detector 945126 PD No. 13 Fan Coil Unit Flow Description of Problem - Indicates zero while in service Transmitter Corrective Action Taken - Tightened input resistor connection 945795 PD Valve, l2SW122 Description of Problem - Flow indication is backwards Corrective Action Taken - Blew down transmitter 945906 PD Valve, 11SW305 Description of Problem - Valve won't close Corrective Action Taken - Air supply valve was restroked 947760 PD No. 15 Fan Coil Unit Damper Description of Problem - Air leak Operator Corrective Action Taken - Repaired leak 1 11

~ r..

947790 PD No. 1 Air Particulate Pump Description of Problem - Pump does not developsufficient flow Corrective Action Taken - Replaced pump 947942 PD Valye, 1CV7l Description of Problem Air line leak Corrective Action Taken - Replaced air line Page llof 13

SALEM UNIT fll OPERATING

SUMMARY

~RIL 1981 4/1 thru Outage - Unit in Cold Shutdown due to turbine repairs.

4/23 4/24 1600 Commenced Reactor heatup.

4/26 1300 Reactor critical.

2335 Reactor trip (from 6% RTP) on low steam generator levels.

4/27 Reactor cooldown due to PS 8 valve stem packing., leak.

4/28 Reactor heatup.

1845 Reactor critical.

2355 Turbine on line, increasing power.

4/29 0335 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. .

4/30 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

REFUELING~INFORMATION DOCKET NO.: 50-272 UN IT: Salem #1 DATE: May 11. 1981 COMPLETED BY: L

  • K
  • Miller
  • ' TELEPHONE: 609-365-7000 X507 April 1981
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: September 1996 Page 13 of 13 8-l-7.R4

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