ML20084L975

Monthly Operating Rept for Apr 1984

ML20084L975
Person / Time
Site:	Salem
Issue date:	04/30/1984
From:	Miller L, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8405150148
Download: ML20084L975 (12)

Text

AVERAGE DAILY UNIT POWER LEVEL Docket No.

50-311 Unit Name Salem # 2 Date May 10, 1984 Completed by L. K. Miller Telephone 609-935-6000 Extension 4455 Month April 1984 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 1004 17 0

2 945 18 0

3 917 19 0

4 1024 20 0

5 1032 21 0

6 425 22 0

7 0

23 0

8~

0 24 0

9 0

25 0

10 0

26 0

11 0

27 0

12 0

28 0

13 0-29 0

14 0

30 0

.15 0

31 0

16 0

Pg. 8,1-7 R1 9*

8405150148 840430 PDR.ADOCK 05000311 R

PDR t

\\

P OPERATING DATA REPORT Docket No. 50-311 Date May 10, 1984

[

Telephone 935-6000

}

Completed by L. K. Miller Extension 4455

' Operating Status Salem No. 2 Notes 1.

Unit Name 2.

' Reporting Period May 1984 3.

. Licensed Thermal-Power (MWt) 3411 3

ITTI 4.

Nameplate Rating. (Gross MWe)

Design Electrical Rating (Net MWe)

III3 j

5.

-Maximum Dependable Capacity (Gross MWe)TITF 7.

Maximum Dependable Capacity (Net MWe) II63 6.

8.

If Changes Occur in Capacity Ratings (items 3 through 7) since Last l

Report, Give Reason l

N/A 9.-

Power Level to Which Restricted, if any (Net MWe)

N/A e

10. Reasons for Restrictions, if any N/A l

This Month Year to Date Cumulative l

l

11. Hours in Reporting Period 719 2903 22344

12. No. of Hrs. Reactor was Critical 161.7 902.8 12611.3 i

13. Reactor Reserve Shutdown Hrs.

0 1443 3533.6 i

14. Hours Generator On-Line 129.3 778.3 12195.6 ;

0 0

0 l

15. Unit Reserve Shutdown Hours

16. Gross Thermal' Energy Generated 406510 2470951 35942023

.'(MWH)

17. Gross Elec. Energy Generated 134460 804960 11673250 i

(MWH)

18. Net Elec. Energy Generated (MWH) 117694 737994 11055242 l

18.0 26.8 54.6 L

19. Unit Service Factor 54.6_

18.0 26.8

20. Unit Availability Factor

21. Unit Capacity Factor 14.8 23.0 44.7 !

(using MDC Net) 22.-Unit Capacity Factor 14.7 22.8 44.4 l (using DER Net) 82.0 73.2 35.0 _ l

23. Unit Forced Outage Rate (type, date and duration of each) ;

t

24. Shutdowns scheduled over next 6 months

(

N/A I

25. If shutdown at end of Report Period, Estimated Date of Startup:

5-5-84

26. Units in Test Status (Prior to Commercial Operation) :

Forecast Achieved I

Initial Criticality 6/30/80 8/2/80 Initial Electricity 9/1/80 6/3/81 Commercial Operation 9/24/80 10/13/81 l

0 3

8-1-7.R2 Page 3 of 12 l

UNIT SHUTDOWN AND POWER REDUCTIONS Dockst No. 50-311 REPORT. MONTH April 1984 Unit Name. Salem No.2 Date May 10, 1984-Completed.by L.K.' Miller Telephone-609-935-6000 Extension-4455 Method of Duration Shutting License Cause and Corrective

~

Event System Component.

Action to No.

Date Type Hours Reason Down 1

2 Rea ctor

~ Report Code 4 Code 5 Prevent Recurrence Turbine Trip Devices-i (Including Instru-84-128 04-06 F

414.6 A

3 HC INSTRU ment s) Control Feedwater Regulating Boiler Level. Control i

84-130 04 F 40.0 A

3 HH VALVEX Valve Nuclear Containment I

Cooler / Filter 84-132 04-25 F

59.3 A

4 WG HTEXCH System Feedwater. Regulating Boiler Level Control HH VALVEX Valve I

84-134 04-27 F

75.6 A

3 i

1 2 Reason 3 Method 4 Exhibit G 5 Exhibit 1 F: Forced A-Equipment Failure-explain 1-Manual Instructions Salem as S: Scheduled B-Maintenance or Test 2-Manual Scram.

for Prepara-Source C-Refueling 3-Automatic Scram, tion of Data j-D-Regulatory Restriction 4-Continuation of Entry Sheets l-E-Operator Training & Licensing Exam Previous Outage for Licensee i

F-Administrative 5-Load Reduction Event Report i

G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161) i i

4 Page 4 of 12

.... -.. -. ~ - -

DOCKET NO:

50-311 MAJOR PLANT MODIFICATIONS UNIT NAME:

SALEM 2 REPORT MONTH APRIL 1984 DATE:

MAY 10, 1984 COMPLETED BY:

L.

K. MILLER

^

TELEPHONE:

(609) 339-4455 4

,,_/-

• DCR NO.

PRINCIPLE SYSTEM SUBJECT 2EC-1744 Circulating Water Remove circulating water traveling screen "Not Running Indication Lights" from 2RPS panel.

Remove motion detectors and wiring from TSI panel to circulating water traveling screen motors.

2EC-1777 Circulating Water Upgrade materials of construction to HC-250 (Abex) or equivalent of No. 21 Screen Wash Pump.

2SC-0996 Annunciators Modify Auxiliary Annunciator inputs 013, 138, 531, 553 and 613 to indicate NORMAL (no alarm) when breakers are de-energized.

2SC-1281 Main Generator Stator Change nipple joint configuration Water Cooling on failed tube connections.

(Package 3 only)

' _/

~

/

• DESIGN CHANGE REOUFST 9-1-7.R1 Page 5 of 12

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-311 l

REPORT MONTH APRIL 1984-UNIT NAME:

Salem 2 DATE: -May 10, 1984 COMPLETED BY:

L.K. Miller TELEPHONE:

609/339-4455 DCR NO.

10CFR 50.59 SAFETY EVALUATION 2EC-1744 This modification does not alter the reliability of any safety related systems.

The functions of the circulating water travelling screens are not altered.

No unreviewed safety or environmental questions are involved.

2EC-1777 This material change of Nos. 21 and 22 Screen Wash Pumps does not alter any presently performed safety analysis, nor does it create any new safety hazards.

The basis of the Technical Specifications remains unchanged.

No unreviewed safety or environmental questions are involved.

2SC-0996 All potential. realistic failure modes have been considered but are not applicable.

This modification will not change any plant process or_ discharge.

No unreviewed safety or environmental questions are involved.

[

2SC-1281 The stator water cooling system is non-safety related and i

located in an area with no safety related equipment.

This modification will'not alter any plant process or discharge.

No unreviewed safety or envir'onmental' i

questions are involved.

t t

• Design Change Request l

L r

I i-i-

l' L

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Page 6~of 12 l

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P S.E & C SALEM GENERATING STATION

' SAFETY RELATED WORK ORDER LOG.

SALEM UNIT NO. 2-WO NO.

DEPT UNIT EQUIPMENT IDENTIFICATION

-910278. OPl 2

230V AC POWER SYSTEM' FAILURE DESCRIPTION:

CHANGE CIRCUIT BREAKER FOR POSITIONS 5G5,'.5G6 FROM TECil'8/72,1.5KW,13.6 AMPS '

TO TED 20,12.. AMPS,' 4KW FOR INSTRUMENT PANEL ~ 361-2A and 36I-2B.

.NO. 2 ' SERVICE ;

WATER INTAKE 460V-230V - CONTROL CENTER. (111083) ;

' CORRECTIVE ACTION:

CHANGED BREAKERS.IAW DCP 2SC-0325 (032184) 938768 IC 2

VALVE 2SJ175 FAILURE DESCRIPTION:'

VALVE APPEARS TO BE LEAKING (081183) '

CORRECTIVE ACTION:

' REPLACED'AND TESTED VALVE (010484) 941599 IC 2

CONTAINMENT PRESSURE RECORDER-FAILURE DESCRIPTION:

RECORDER FOUND OUT OF CALIBRATION.(041684)

CORRECTIVE-ACTION:

REPLACED SERVO' ASSEMBLY AND CALIBRATED RECORDER (041584) 941601 IC 2

21BF19 FEED REG. VALVE E/P.

FAILURE DESCRIPTION:

VERIFY CALIBRATION OF THE E/P (041784)

CORRECTIVE ACTION:

INSTALLED AND CALIBRATED NEW TRANSMITTER (041884) 941606 IC 2

ROD POSITION INDICATOR 2SA2 FAILURE DESCRIPTION:

INDICATION.IS GREATER THAN TWELVE STEPS FROM THE REST OF THE BANK (012384).

CORRECTIVE ACTION:

RECALIBRATED INDICATOR (042384)

Page 7 of 12

P S' E &' G. SALEM GENERATING STATION

- SAFETY RELATED ~ WORK ORDER LOG.

941655-IC.

2 NO.'21 DIESEL GENERATOR VENTILATION VALVE 2DGV2 SOLEN 0ID FAILURE DESCRIPTION:'

VALVE IS BLOWING THROUGH-(032984)

CORRECTIVE ACTION:

REPAIRED LEAKING SOLENOID VALVE (040284)

~941681.

IC'

~2-

VALVE 23BF40 FAILURE DESCRIPTION:

VALVE IS BINDING WHEN STROKING OPEN FROM A FULL CLOSED POSITION (042384)

CORRECTIVE ACTION:

INSPECTED VALVE INTERNALS, NO PROBLEMS NOTED. STEM OPERATED SM0(7IHLY BY HAND (042584).

942679' IC 2

NO. 22 STEAM GENERATOR WIDE RANGE LEVEL RECORDER FAILURE DESCRIPTION:

RECORDER DRIVE CORD BROKEN (040284)

CORRECTIVE ACTION:

INSTALLED NEW DRIVE CORD AND PERFORMED CHANNEL CALIBRATION (040384) 942875 OD 2

2R41A FAILURE DESCRIPTION:

21t41A FAILED

- CORRECTIVE ACTION:

OVERHAULED CONTROLLER AND REPLACED DATA BUFFER VERIFIED SETPOINTS (011384) 947057 MD 2

CVCS VITAL HEAT TRACE FAILURE-DESCRIPTION:

CHECK THERM 0 COUPLE AND CONTROLLER FOR OPERATION (012384)

CORRECTIVE ACTION:

REPLACED FAILED THERMOCOUPLE ON CONTROLLER 260A and 260B (041184) 947784 OD 2

23 STEAM GENERATOR LEVEL CONTROL SYS.

TAILURE DESCRIPTION:

23 SG LEVEL DRIFTED FROM 44% TO 40% (032884)

CORRECTIVE ACTION:

PERFORMED CALIBRATION AND VERIFIED PF0PER OPERATION OF LEVEL CONTROLLER (032984).

~

P S E & G ' SALEM GENERATING STATIGE -

I' SAFETY RELATED WORK ORDER IDG-

~

2 947818' l 0D 2

SOLENOID VALVE 2DGV1~

' FAILURE DESCRIPTION:

SOLENOID VALVE IS BLOWING, AIR, HAMPERING DAMPER' OPERATION (032984) l CORRECTIVE ACTION:

REPLACED SOLENOID VALVE (032984) f.

947857 OD 2

NO. 21 PRESSURIZER BACKUP HEATER ELEMENT FAILURE DESCRIPTION:

BREAKER IS TRIPPING OUT PERIODICALLY (010184)

' CORRECTIVE ACTION:

REPLACED WITH SPARE. BREAKER (042184) i 948071 OD 2-FEED REG. VALVE 23BF19-FAILURE DESCRIPTION:

VALVE NOI STROKING FULL OPEN. (042284) t CORRECTIVE' ACTION:

ADJUSTED SUPPLY PRESSURE AND VERIFIED PROPER. STROKING OF THE VALVE (042284) 1.

i 948110

'0D 2

OHA A-47 "B" 28V-CONTROL BUS VOLT LOW i

FAILURE DESCRIPTION

• BATT. BUS INDICATED LESS THAN 26V WITH N0' ALARM' (042584)

CORRECTIVE ACTION:

FIELD-QUESTIONNAIRE 81-47 WRITTEN TO ENG.'TO PROVIDE A BETTER UV. RELAY FOR I

THIS CKT. (042584) 948173 OD 2

CONTAINMENT VENTILATION RESET BEZEL FAILURE DESCRIPTION:

RESET PUSHBUTTON WOULD NOT RESET'ALL CONTAINMENT VENTILATION RESET BEZEL (3)

WHEN NORMAL RESET: BUTTON PUSHED (041284)

CORRECTIVE ACTION:

FOUND AND REPLACED DEFECTIVE CONTAINMENT VENTILATION ISOLATION RESET RELAY.

(041384)'

Page 9 of 12-

y P S 'E & G : SALEM GENERATING STATION SAFETY RELATED WORK: ORDER' LOG

'948214' OD-2

'2B VITAL BUS? INSTRUMENT INVERTER FAILURE DESCRIPTION:

INVERTER WILL NOT'GO,ON REGULAR FEED.(041884).

CORRECTIVE ' ACTION:

THYRISTOR FUSES BLOWN.IN MASTER' INVERTER. REPLACED FUSES AND RETURNED TO SERVICE (041884) 948605 IC-2' 'NO. 25 FEEDWATER HEATERS FAILURE DESCRIPTION:

CALIBRATE LEVELS.ON 25A, B, & C HEATERS (040684)

CORRECTIVE ACTION:

. CALIBRATED HEATERS (041684) 948606 IC 2-FEEDWATER VALVES'21-24BF19'S FAILURE DESCRIPTION:

VERIFY. VALVE OPERATION (040684)

CORRECTIVE ACTION:

CORRECTED AND. VERIFIED PROPER OPERATION.0F THE VALVES (040684) 948758

.OD 2

22 EAST MAIN STEAM. COIL DRAIN TANK VALVE 22RD2 FAILURE DESCRIPTION:

VALVE HAS A BODY TO BONNET LEAK (040384)

CORRECTIVE ACTION:-

REPLACED BONNET,' LAPPED SEAT, REPACKED VALVE (041584) 948896 OD.

2 23 RC FLOW CHANNEL II FAILURE DESCRIPTION:

MID-SCALE OF CHANNEL IS. FAILED (042184)

CORRECTIVE ACTION:

REPLACED AMPLIFIER (042184) 949988 MD 2

2A DIESEL OUTPUT BREAKER FAILURE DESCRIPTION:

REPLACE OVERCURRENT. RELAY ON BREAKER AS PER SORC REQUEST (031784)

CORRECTIVE' ACTION:'

REPLACED THE RELAY.(041284)

c-t e '

I f

OPERATIONS

SUMMARY

REPORT MARCH 1984 l

Unit No. 2 began the month operating at reduced power (78% to 94%) due to problems experienced with No. 23 A&B Circulator Travelling Screens.

_T e travelling. screen problems were corrected and on April 3, a unit h

power. escalation was commenced.

On April 6, Unit No. 2 tripped at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> due to a false low condenser vacuum signal.

The signal was inadvertently initiated by personnel troubleshooting a problem with l

3 the condenser vacuum indication.

Later, at 1633 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.213565e-4 months <br />, during l

performance of-inservice. testing on Feedwater Regulating Valve 23BF19, a water hammer' occurred.

Investigation rev'ealed that Valve 23BF22 (No.;23 Steam Generator Stop Check Valve) failed to close.

SWasequently,.when Valve 23BF19 was opened, a pressure transient occurred in the main and auxiliary feedwater lines.

Unit No. 2 was placed in Cold Shutdown while investigation of the occurrence and assessment of the damage was performed.

The results of the investigation revealed degradation of three hangers, three struts, and two. sets of trunions.

All the damaged items were repaired.

SWasequently, problems were encountered with Valve 2PR6, an isolation i

valve for the Pressurizer Power Operated Relief Valve 2PRI. _The

. isolation valve was returned to operable status following replacement j

of the valve disc.

Unit No. 2 was returned to service on April 23, at i

1554. hours, and-subsequently tripped at 1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br /> due to a Hi-Hi level in ik). 23 Steam Generator.

On April 24, a unit startup was performed and the turbine latched at 0923 hours0.0107 days <br />0.256 hours <br />0.00153 weeks <br />3.512015e-4 months <br />.

At 0927 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.527235e-4 months <br />, the turbine tripped due to a steam flow / feed flow mismatch on No. 21 Steam I

Generator.

Unit No. 2 remained in Mode 4 to facilitate inspections of

'Nos. 24 and 25 Containment Fan Coil Unit motors for possible stator

^

support.bar. weld cracks.-

No weld failures or degradations were found'.

Subsequently, on April 27, Unit No. 2 was synchronized at 1920 hours0.0222 days <br />0.533 hours <br />0.00317 weeks <br />7.3056e-4 months <br />.

At.1923 hours0.0223 days <br />0.534 hours <br />0.00318 weeks <br />7.317015e-4 months <br />, a reactor trip-occurred due to a Hi-Hi level condition in No. 23 Steam Generator.- A unit startup was commenced-on April 28.

As-a result of testing,- it was determined that No. 23 Feeuwater Flow-Nozzle was not functioning properly ~and the unit was shutdown on the

[

29th,-for repairs.

On April 29, radiography of the nozzle confirmed L

that the nozzle had broken loose from its design location, thus

.providing erroneous flow indication.

The nozzle section of the pipe is expected to be replaced with a similar section from No. 13 Steam Generator.

Unit No. 2 is expected to return to service May 5, 1984.

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Page 11 of 12 t

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l F

REFUELING INFORMATION DOCKET NO.:

50-311

- COMPLETED BY:

L.K. Miller UNIT NAME:

Salem 2 i

DATE:

May 10, 1984 TELEPHONE:

609/935-6000 l'

EXTENSION:

4455

-' Month' April 1984

{

l.

Refueling information has changed from last month:

YES NO X

i 2.

Scheduled date for next refueling:

January 5, 1985

)

3.

Scheduled'date for rectart following refueling:

March 17, 1985 4.

A)

Will Technical Specification changes or other license i

amendments be required?

YES NO l

4 NOT DETERMINED TO DATE-5/1/84

- ]B)

Has the reload fuel design been reviewed by the Station f

Operating Review Committee?

j YES NO X

I

- If no, when is it scheduled? November 1984 5.

Scheduled date (s) for-supmitting proposed licensing action:

December 1984 (if required)

I 6.

Important. licensing considerations associated with refueling:

NONE i

r I'

f L

7.

Number of. Fuel Assemblies:

l A)

. Incore 193 l

l~

B)

In-Spent Fuel. Storage 72 L

ia 8.-

Present licensed speut-fuel storage capacity:

1170 Future spent fuel storage capacity:

1170 i

t l

9.

Date of last refueling that can be discharged to spent fuel pool assuming the present i

f licensed capacity:

March 2000 L 1-7.R4-l Page 12 of 12 1.

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. O >SEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station May 10, 1984 Director, Office of Inspection and Enforcement U.S.

Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 2 LOCKET NO. 50-311 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 April 1984 are being sent to you.

Average Daily Unit Power Level Operating Data Report Unit Shutdowns and Power Reductions Major Plant Modification Safety Related Work Orders Operating Summary Refueling Information Sincerely yours, Y

y J.

f.

Z o, Jr.

Gen 6ral Manager - Salem Operstions LKM:sbh cc:

Dr. Thomas E.

Murley Regional Administrator USNRC I

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 l of 12 j[" g '

8-1-7.R4 L

The Energy People OS218') M.8111