ML20093H831

Monthly Operating Rept for June 1984

ML20093H831
Person / Time
Site:	Salem
Issue date:	06/30/1984
From:	John Miller, Zupko J Public Service Enterprise Group
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8407250310
Download: ML20093H831 (10)

Text

r AVERAGE. DAILY UNIT POWER LEVEL Docket No.

50-311 Unit Name Salem # 2 Date July 10,1984 Completed by L. K. Miller-Telephone 609-935-6000 Extension 4455-

. Month June 1984 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)

(MWe-NET) 1 0

17 1070 2

0 18 1108-3 0

19 1102

-4 0

20 1086 5

0 21 1087 6

0 22 1094 7

0 23 1077 8'

0 1087 9

0 25 1095 10 0

26:

1100 11 0

27 1107 12-0

-28 1045 13 0

29 1103 14 574 30 1100 15 1073 31 16 1097 Pg. 8,1-7 R1

$ hK0 R

Page 2 ofl10

• ~ ~

,a.

OPERATING DATA REPORT Docket No. 50-311

^

Date July 10, 1984 Telephone 935-6000 Completed by L.

K. Miller Extension 4455 Operating Status 1.

Unit Name Salem No. 2 Notes 2.

Reporting Period June 1984 3.

Licensed Thermal Power (MWt) 3411 4.

Nameplate Rating (Gross MWe)

IITY 1162 5.

Design-Electrical Rating (Net MWe) 6.

Maximum Dependable Capacity (Gross MWe)1149 7.

Maximum Dependable Capacity -(Net MWe) ITUT 8.

If Changes Occur in Capacity Ratings (items 3 through 7) since Last Report, Give Reason N/A 9.

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

N/A

10. Reasons for Restrictions, if any N/A This Month Year to Date Cumulative

11. Hours in Reporting Period 720 4367 23808

12. No. of Hrs. Reactor was Critical 421.0 1918.3 13626.9-

13. Reactor Reserve Shutdown Hrs.

0 1442.9 3533.6-

14. Hours Generator On-Line 405.4 1769.6 13186.9

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy: Generated (bORI) 1345678 5743709 39214781

17. Gross Elec. Energy Generated (MWH) 449880 1904810-12773100

18. Net Elec. Energy Generated ' (MWH) 425465 1784158 12101406-

19. Unit Service Factor ~

56.-3 40.5 55.4

20. Unit Availability Factor '

56.3 40.5 55.4

21. Unit Capacity Factor (using MDC Net) 53.4 36.9 46.0

22. Unit Capacity Factor (using DER Net) 53.0 36.6

'45.6

23.. Unit Forced Outage Rate.

43.7 59.5 34.8

24. Shutdowns scheduled over next 6smonths (type,. date and duration of each).

N/A.

25. If shutdown at end of Report 1 Period, Estimated-Date of Startup:

N/A

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

s Forecast Achieved Initial Criticality 6/30/80 8/2/80 Initial Electricityg 9/1/80 6/3/81 Commercial. Operation 9/24/80.

~10/13/81-8-1-7.R2' Page-3fof 10 v.

UNIT SHUTDOWN AND POWER REDUCTIONS Dock 3t No. 50-311 REPORT MONTH June 1984' Unit'Name ' Salem No.2 Date..

' July 10,-1984 Completed by L.K. Miller Telephone. 609-935-6000 Extension 4455 Method of-Duration.

Shutting License Cause and Corrective.

Hours Reason Down Event', System.

Com'ponent Action to-No.

Date Type '

2 Reactor Report-Code 4 Code 5-Prevent Recurrence' 1

High Pressure Safety

. Injection Core:

84-170-05-30 F

314.6 A

1 SF VALVEX

- Injection / Core Spray Speed Control,

~ 84-172 06-14 F

4.7 A

5 HH INSTRU

' Feedwater Pump-Traveling. Screen /

Trash' Rack /

HF FILTER Canal Screen 84-190 06-23 F

.5' B

5 Traveling Screen /

Trash-Rack

'.~

84-192 06-23 F

.2

'E 5-HF FILTER Canal Screen' 1

2 Reason 3 Method 4 Exhibit G S 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 D-Regulatory Restriction

.4-Continuation of Entry Sheets E-Operator Training & Licensing Exam

. Previous' Outage for. Licensee

~

5-Load Reduction-Event Report F-Administrative.

G-Operational. Error-explain.

9-Other

-(LER) File H-Other-explain (NUREG 0161)

+

3 Page 4.of-10 w-k v

T A

DOCKET NO3 gn-111 MAJOR PLANT MODIFICATIONS SA W 2

' REPORT MONTH JUNE 198'4 DATE:

JULY 10, 1984 COMPLETED BY :

L. K. MILLER TELEPHONE:

(609) 339-4455

• DCR NO.

PRINCIPLE SYSTEM SUBJECT 1

2ET-0944 Circulating Water Provide electrical power feed to-vendor supplied heat transfer research unit.

2EC-1008 Main Transformers Replace vacuum switch on COPS tank with new model switch and. arrange-ment.

Also relocate vacuum switch alarm.

Install noise suppression.

2EC-1387 SEC I

2EC-1620A Reactor Coolant System-Replace existing recorders with Wide Range RTD Recordero seismically qualified recorders.

I' Instrument Nos. TA-0014, TA-0016, TA-0036 and TA-0038.

t 2EC-1724 Chemical & Volume Replace the 2CV45 and 2Cv50 valves.

j r

Control i

4 1

J i

1 l

5r i

l

~

i-

• DESIGN CHANGE REQUEST 8-1-7.R1

^

Page 5 of 10 O

j

^ ^ - - - -

_.__,,._,..y'y,

MAJOR PLANT MODIFICATIONS DOCKET NO.:

50-311 REPORT MONTH JUNE 1984 UNIT NAME:

Salem 2 DATE:

July 10, 1984 COMPLETED BY:

L.K. Miller TELEPHONE:

609/339-4455 DCR NO.

10CFR 50.59 SAFETY EVALUATION 2ET-0944 This test requires no change to existing systems, nor does it affect any presently performed safety analysis.

No unreviewed safety or environmental questions are involved.

2EC-1008 This change in the alarms improves plant reliability by decreasing operator response time.

No unreviewed safety or environmental questions are involved.

2EC-1387 Implementation _of this DCR does not involve any unreviewed safety or environmental questions.

2EC-1620A All potential realistic failures have been considered and are not applicable.

No unreviewed safety or environmental questions are involved.

2EC-1724 Addition of the blind flange will eliminate two potential paths of unidentified leakage from the reactor Coolant System.

No unreviewed safety or environmental questions are involved.

• Design Change Request t

Page 6 of 10

(..

PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT NO. 2

- WO NO DEFI UNIT EQUIPMENT IDENTIFICATION 954241 - - 0D 2

'NO. 24 OPAT FAILURE DESCRIPTION:

INDICATOR STUCK IN MID SCALE (050484)

CORRECTIVE ACTION:

REPLACED SEVERAL CAPACITORS AND RECALIBRATED (050484) 954117

.0D

.2 NO. 24 STEAM GENERATOR LEVEL INDICATION FAILURE DESCRIPTION:

CHANNEL III IS READING 3% LOWER THAN THE OTHER CHANNELS (050784)

CORRECTIVE ACTION:

REPAIRED ROOT VALVE PACKING LEAK AND PERFORMED RECALIBRATION (052284) 900108-0-MD 2

VALVE 22WG10 FAILURE DESCRIPTION:

BLOCKAGE..IN SUCTION TO WASTE CAS COMER (062584)

. CORRECTIVE ACTION:

REPLACED DIAPHRAGM (070384)

~9900019-9 MD 2

4KV VITAL BUS FAILURE DESCRIPTION:

REMOVE 83 RELAY FROM 1A 4KV VITAL BUS AND INSTALL ON 2C 4KV VITAL BUS (051584)

. CORRECTIVE ACTION:

REMOVED RELAY FROM 1A AND INSTALLED IN 2C, INSTALLED REBUILT RELAY IN 1A AND TESTED (060784)

Page 7 of 10 L.-

!=

l1 UNIT.2

'99022966.MD

.2 2C SAFEGUARDS EQUIPMENT CONTROL CABINET FAILURE DESCRIPTION:

- SPURIOUS ALARMS (061184)

CORRECTIVE ACTION:'

INCREASED DC VOLTAGE IAW MD84-3215. (061284) 6,L84-05-29-550-0

CD 2'

NO. 21 MOTOR GENERATOR SET FAILURE DESCRIPTION:

HIGH VIBRATION (052948)

~

' CORRECTIVE ACTION:

REPLACED INBOARD AND OUTBOARD. BEARINGS (060584)

V

.s

~ ~. " - ~

i F

r

+ -

Page 8 of 10

+

L,..

SALEM UNIT NO. 2 OPERATIONS

SUMMARY

REPORT JUNE 1984 Unit No. 2 began the month shutdown in order to replace 21SJ16 and 22SJ16 valves.

These valves, which are in the ECCS flow path, were considered inoperable after radiographs indicated the valve plug and stem orientation were not proper.

Inspection of the valves after their removal revealed that the weld that holds the disk nut to the disk was missing.

The Unit remained in Mode 5 until June 5, 1984 when plant heatup commenced.

No load pressure and temperature of 2235 psig and 5471o!F was reached on June 6, 1984.

A plant cooldown to approximately 367*F was reached on June 6, 1984.

A plant cooldown to approximately 367 F was initiated on June 7, 1984 to facilitate changeout of No. 23 CVCU motor.

No. 23 CFCU motor failed to start in slow speed during surveillance testing thereby requiring its repair or replacement.

No. 23 CFCU was subsequently replaced with No. 14 CFCU, however it too failed to start in slow speed.

No. 22 CFCU has been placed in the No. 23 CFCU location.

No. 12 CFCU has been placed in the No. 22 CFCU location.

The apparent cause of the CFCU failures to start in slow speed was misalignmetn of the rotor to stator air gap.

The plant recommenced heatup on June 13, 1984.

Criticality was achieved at 1059 hours0.0123 days <br />0.294 hours <br />0.00175 weeks <br />4.029495e-4 months <br /> on June 13, 1984.

The Unit was synchronized on June 14, 1984 at 0238 hours0.00275 days <br />0.0661 hours <br />3.935185e-4 weeks <br />9.0559e-5 months <br /> and reached full power on June 15, 1984.

The Unit remained at full power until June 23, 1984 when the Unit load was decreased to 64% at 0932 hours0.0108 days <br />0.259 hours <br />0.00154 weeks <br />3.54626e-4 months <br /> due to heavy grass loading on the Circulating Water Traveling Screens.

The Unit returned to full power at 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br /> on June 23, 1984 where it remained for the remainder of the period.

Page 9 of 10

llEE" l

REFUELING INFORMATION DOCKET NO.:

50-311 COMPLETED BY:

L.K. Miller UNIT NAME:

Salem 2 DATE:

July 10, 1984 TELEPHONE:

609/935-6000 EXTENSION:

4455 Month June 1984 1.

Refueling information has changed from last month:

YES NO X

2.

Scheduled date for next refueling:

January 5, 1985 3.

Scheduled date for restart follos ing refueling:

March 17, 1985 4.

A)

Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO DATE 6/1/84 B)

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

YES NO X

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

Scheduled date (s) for submitting proposed licensing action:

December 1984 (if required) 6.

Important licensing considerations associated with refueling:

NONE

• /.

Number of Fuel Assemblies:

A)

Incore 193 B)

In Spent Fuel Storage 72 8.

Present licensed spent fuel storage capacity:

1170 Future spent fuel storage capacity:

1170 9.

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

March 2004 8-1-7.R4 Page 10 of 10

O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station July 10, 1984 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTIILY OPERATING REPORT SALEM NO. 2 DOCKET 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 June 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, J.

Zu o, Jr.

General Manager - Salem Operations LKM:sbh cc:

Dr. Thomas E. Murley Regional Administrator USNRC Region I 631 Park Avenue King of Prussia,.PA 19405 Director, Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Washington, DC 20555 Enclosures Page1 of 10 8-1-7.R4 i

The Energy People I

95 2189 (20M11181

_..