ML20115G737

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Monthly Operating Rept for Mar 1985
ML20115G737
Person / Time
Site: Salem PSEG icon.png
Issue date: 03/31/1985
From: Ronafalvy J, Zupko J
Public Service Enterprise Group
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
NUDOCS 8504220317
Download: ML20115G737 (15)
v • d • e


Text

1 AVERAGE DAILY UNIT POWER LEVEL Docket No. 50-272 Unit Name Salem # 1 Date April 10,1985 Completed by J. P. Ronafalvy Telephone 609-935-6000 Extension 4455 Month March 1985 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET) (MWe ~'IET) 1 1098 17 1115 2 1114 18 1105 3 1104 19 1102 4 1115 20 1102 5 1101 21 1100 6 1099 22 1101 7 976 23 1106 8 1084 24 1105 9 1102 25 1114 10 1102 26 1087 11 1092 27 1107 12 1106 28 1103 13 1103 29 1111 14 1095 30 1077 15 1092 31 1102 16 1111 P. 8,1-7 R1 ,

8504220317 850331

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OPERATING. DATA' REPORT Docket No.50-272 Date April 10, 1985 Telephone 935-6000 Completed by J. P. Ronafalvy Extension 4455 Operating Status

1. Unit Name Salem No. 1 Notes
2. Reporting Period March 1985
3. Licensed Thermal Power (MWt) 3338
4. Nameplate Rating (Gross MWe) 1175
5. Design Electrical Rating (Net MWe) 1090
6. Maximum Dependable Capacity (Gross MWe)1124
7. Maximum Dependable Capacity (Net MWe) 1079
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/It '
10. Reasons for Restrictions, if any N/A This Month Year to Date Cumulative
11. Hours in Reporting Period 744 2160 67969
12. No. of Hrs. Reactor was Critical 744 2142.6 37966.1
13. Reactor Reserve Shutdown Hrs. 0 0 3088.4
14. Hours Generator On-Line 744 2139.7 36298.3
15. Unit Reserve Shutdown Hours 0 0 0
16. Gross Thermal Energy Generated (MWH) 2480827- 7082904 109850901
17. Gross Elec. Energy Generated (MWH) 848600 2425140 36341190
18. Net Elec. Energy Generated (MWH) 816628 2331205 34429187
19. Unit Service Factor 100 5,9 .1 53.4
20. Unit Availability Factor 100 99.1 53.4
21. Unit Capacity Factor (using MDC Net) 101.7 100.0 46.9
22. Unit Capacity Factor (using DER Net) 100.7 99.0 46.5
23. Unit Forced Outage Rate 0 0.9 31.9
24. Shutdowns scheduled over next 6 months (type, date and duration of each)

N/A

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

i N/A

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

1 Forecast Achieved l Initial Criticality 9/30/76 12/11/76 Initial Electricity 11/1/76 12/25/76 i Commercial Operation 12/20/76 6/30/77 8-1-7.R2 Page of I

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UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH March 1985 Unit Name Sulcm No.1 Date April 10,1985-Completed by J.P. Ronafalvy Telephone 609-935-6000 Extension 4455 Method of Duration Shutting License Cause and Corrective Hours Reason Down Event System Component Action to No. Date Type Prevent Recurrence 1 2 Reactor Report Code 4 Code 5 Intercept Valves F A 5 - HB VALVEX Turbine 85-182 3-07 8.5 3 Method 4 Exhibit G S Exhibit 1 1 2 Reason Salem as F: Forced A-Equipment Failure-explain 1-Manual Instructions 2-Manual Scram. for Prepara- Source S: Scheduled B-Maintenance or Test 3-Automatic Scram, tion of Data C-Refueling D-Regulatory Restriction 4-Continuation of Entry Sheets E-Operator Training & Licensing Exam Previous Outage for Licensee -

F-Administrative 5-Load Reduction Event Report G-Operational Error-explain 9-Other (LER) File H-Other-explain (NUREG 0161)

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MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH ' MARCH 1985 UNIT NAME: Salem 1 DATE: April 10, 1985 COMPLETED BY: J. Ronafalvy TELEPHONE: 609/339-4455

  • DCR_NO. PRINCIPLE SYSTEM SUBJECT 1EC-1304 Chemical & Volume Buttwelding of valves (associated with the test, vent and drain connections along the centrifugal and reciprocating charging pump suction and discharge lines and CVC letdown Lines)- to the header making each of them a "one piece connection" 1EC-1588 Cable Trays Retag, repull various cables 1'

throughout the plant to match '

changes made to wiring

, diagrams prior to implementation of the DCR system.

1EC-1676A Reactor Coolant Replace reactor coolant narrow range RTD's with environmentally qualified elements. Also relocate solenoid valves associated with MS7 and MS18 valves. '

! 1EC-1698A Circulating Water- Install a 316 stainless Traveling Screens steel traveling screen in place of 138 screen. Install one set of 316 stainless steel

baskets in 11A traveling screen. Install flexible line

, from inlet screen wash piping to screen wash spray hdeader piping.

! 1EC-1775 Circulating Water Replace the inlet expansion joints of Unit 1 Main Condensers, additionally replace the remaining outlet expansion joints not changed during the main condenser i

retubing in 1980.

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  • DCR NO. PRINCIPLE SYSTEM SUBJECT 1EC-1816 Safeguards Equipment Install new Lambda power Controller R130 supplies and new Potter Brumfield relays in the Unit 1 SEC's.

IEC-1830 Generator Protective Upgrade generator stator Relay ground fault relay protection.

IEX-1836 Reactor Coolant Revise setpoints of #12 RCP locked rotor protection relaying.

1EC-1874A Service Water Revise 8" Service Water emergency supply line to Aux Feedwater from #12 Service Water nuclear header. Revise 4" SW supply line to room and oil coolers from #12 Service Water nuclear header. Line or replace stainless steel service water supply and return piping to #12 CC Hx.

Add break flanges in service water supply and return piping to #12 CC Hx.

1EC-1950 Containment Cooling Machine stator core, rotor Fan Coolers and roll file to remove eccentricity between stator and core and obtain uniform air gap. Also increase air gap from 39 mils to 44 mils.

Drill ports (3/4") which can be plugged, on end bell .4 each on each end.

i 1EC-1988 Steam Generator Change the SGFP No. 11 and Feed Pump and 12 thrust bearing wear alarm Turbine Lube and and trip setpoints from 8 Control Oil and 12 psi to 13 and 17 psi respectively.

1ET-1996 Chilled / Service Test application of Garlock Water " Turbo-Star" cartridge type mechanical seal in chiller

, condenser recirc pumps No. 11, 12, 13.

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  • DCR NO. PRINCIPLE SYSTEM SUBJECT ISC-0605 Service Water Pump Vent the oil level columns Motors (#15) in the bearing oil lubrication system on No. 15 Service Water Pump Motor.

1SC-0892 Containment Personnel Install a mechanical stop Hatch valve at the hatch flowmeter-air supply line.

Separate valve to be installed on El. 100' and El. 130' hatches.

ISC-1306 Security (Barriers) Make additions and modifications.to provide security barriers on three air vents in the 122' El. hallway between the Aux Building and the "A" Building.

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m MAJOR PLANT MODIFICATIONS DOCKET NO.: 50-272 REPORT MONTH MARCH 1985 UNIT NAME: Salem 1 DATE: April 10, 1985 COMPLETED BY: J. Ronafalvv TELEPHONE: 609/339-4455

  • DCR NO. SAFETY EVALUATION 10 CFR 50.59 IEC-1304 This change addresses the intent to increase conservatism and thereby reduce the possibility of a future occurrence of cracks / breaks at the tect, vent, and drain connections.

In addition, the section modulus of the connection will be significantly increased which will improve resistance to heretofore undetected shock load. No unreviewed safety or environmental questions are involved.

1EC-1588 The work to be done with this DCR will not change the actual design of any system nor will it affect any safety related system. No unreviewed safety or environmental questions are involved.

1EC-1676A This change involves a substitution of existing equipment.

The system response time will increase and the over temperature delta T (Table 3.3.2 of the Tech. Specs.) will increase but by an amount less than that allowed in Table 15.1-3 of the FSAR accident analysis. No unreviewed ,

safety or environmental questions are involved.

1EC-1698A This change involves the upgrading of the traveling screen material. This system does not affect the presently performed safety analysis nor does it create any new hazards. No unreviewed safety or environmental questions are involved.

1EC-1775 The work to be done with this DCR will not change the actual design of any system nor will it affect any safety related system. No unreviewed safety or environmental questions are involved.

IEC-1816 This change replaces conponents with components manufactured by a different vendor. All replacement components have been qualified to equal to or greater requirements than the original equipment. This includes seismic qualification to IEEE 344. All failure modes are identified to the originally installed equipment. No unreviewed safety or environmental questions are involved.

  • DCR - Design Change Request

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1EC-1830 This change increases protection of the Main Generator <

stator from ground faults. The change is non-safety related and does not add any generator trips which are not already possible through various electrical faults. No unreviewed safety or environmental questions are involved.

1EX-1836 This change verifies the #12 RCP~ locked motor protection relay set points to determine if the motor is acceptable to remain in service or must be removed for further inspection. No unreviewed safety or environmental questions are involved.

1EC-1874A This change replaces the Service Water unlined stainless steel supply and return piping with polyethylene lined carbon steel. The new piping will prevent the buildup of marine growth on the pipe wall and will prevent pipe corrosion. The new polyethylene piping will stand up to the Service Water conditions. It will not affect the effluent to the river and will prevent the release of Service Water to the atmosphere. Also, the 8" emergency supply to the Auxiliary Feedwater System and the 4" supply to the Room Coolers are being revised to allow the line to be isolated ,thereby eliminating the build-up of marine growth and silt. It will also allow the supply line to the Room Coolers to operate more efficiently. The addition of break flanges will allow for future inspections to verify the integrity of the system. No unreviewed safety or environmental questions are involved.

1EC-1950 These changes result in a uniform air gap in the electrical motor and provides a means to verify the uniformity. These features only add to the reliability and availability of the motor. No unreviewed safety or environmental questions are involved.

l lEC-1988 The intended function of the system remains unaffected.

l The change is in conformance with the manufacturer's recommendation. This is a non-safety related system. No unreviewed safety or environmental questions are involved.

lET-1996 The test applicatins of a " Garlock Turbostar" cartridge type mechanical seal in the Chiller Condenser Recirc.

Pumps do not affect any presently performed safety analysis nor does it create any new hazards. No unreviewed safety or environmental questions are involved.

  • DCR - Design Change Request l

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  • DCR NO. SAFETY EVALUATION 10 CFR 50.59 ISC-0605 The modification of the oil sight gauge vent will improve the accuracy of the oil level indication. No unreviewed safety or environmental questions are involved.

ISC-0892 The controls changes do not affect the operation of installed equipment and will not deduct from the margin of safety of presently installed equipment. This change does not affect the safe shutdown of the plant. No unreviewed safety or environmental questions are involved.

ISC-1306 This change involves the structural work required to restrict unauthorized access through a roof opening by welding bars to the roof opening frame. The work area is the hallway between the Aux. Building and the A Building (122' elevation). This hallway is not in a safety related area of the plant. No unreviewed safety or environmental questions are involved.

  • DCR - Design Change Request O

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PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER. LOG SALEM UNIT 1

%O NO DEPT UNIT EQUIPMENT IDENTIFICATION 8503191008 SMD 1 13 FAN COIL UNIT FAILURE DESCRIPTION: SERVICE WATER LINE BROKEN OFF UPSTREAM OF 13SW243 PLEASE REPAIR CORRECTIVE ACTION: WELDED NIPPLE PERFORMED AN ACCEPTABLE PT & IN SERV ICE LEAK EXAM 8503120950 SMD 1 11BF19 FAILURE DESCRIPTION: REPAIR 11BF19 PACKING LEAK USING FURMANITE PROCESS.

CORRECTIVE ACTION: VALVE FURMANITED .

8503121964 SIC 1 SOLENOID VALVE FAILURE DESCRIPTION: THE INLET VALVE TO THE RIGHT CHAMBER IS BLOWING AIR.

POSSIBLE DIAPHRAGM LEAK. VALVE LOCATED UNDER CHAMBER.

CORRECTIVE ACTION: REPLACED VALVE AND MOISTURE-INDICATOR.

8503070359 SIC 1 AFD MONITOR FAILURE DESCRIPTION: AFD RECORDER IS SPIKING LOW INTO ALARM. I&C DEPT PLEASE REPAIR.

CORRECTIVE ACTION: SWITCH #1 WAS REMOVED CONTACTS CLEANED AND RETURNED TO SERVIC

E. PROCEDURE

1PD-16.1.007 WAS USED TO REMOVE SWITCH FROM SERVICE TO WORK ON IT.

i SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 8503070600 SIC 1 CONTROL FOR 11SW129 FAILURE DESCRIPTION: SOLENOID VALVE IS CONTINUOUSLY VENTING CORRECTIVE ACTION: REBUILD SV-601 WITH ASCO SOLENOID REPAIR KIT.

0099160501 SMD 1 12SW24 12 STRNR. BK/ WASH FAILURE DESCRIPTION: 12SW24 12SWP STRNR. BACKWASH VALVE, HAS BLOWN DIAPHRAGM CORRECTIVE ACTION: FOUND VALVE DIAPHRAGM BLOWN, AND INTERNALS DISTROYED.

REPLACED WITH A NEW COMPLETE VALVE. NEW NUTS AND -

SUTDS. CLEANED AREA.

0099160676

  • SIC 1 VCT FAILURE DESCRIPTION: A SWAGELOCK FITTING ON LEVEL POT BOTTOM BELLOWS IS BLOWING CAUSING A RADIATION PROBLEM. PLEASE REPAIR CORRECTIVE ACTION: REPLACED FITTING SENSING LINE FOR LEVEL BELLOWS ON VCT.

0099160714 SMD 1 #13 CFCU MOTOR COOLER FAILURE DESCRIPTION: SERVICE WATER LEAK IN MOTOR COOLER, PLEASE REPAIR.

CORRECTIVE ACTION: REPLACED MOTOR COOLER 0099160480 SMD 1 16 SW PMP STRNR.

FAILURE DESCRIPTION: 16 SW PMP. STRNR. HAS A PACKING LEAK.

CORRECTIVE ACTION: REPACKED STRAINER

SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099005255 SMD 1 12 BF19 FAILURE DESCRIPTION: PACKING GLAND LEAKING BADLY. PACKING HAS BEEN TIGHTENED AS MUCH AS POSSIBLE WORK ORDER TO COVER TEMP. REPAIRS, FURMANITE CORRECTIVE ACTION: DRILLED TRAPPED AND INSERTED FURMANITE FITTINGS INJECTED FURNMANITE COMPOUND ASSURED VALVE STEM MOVEMENT NEW WO ISSUED FOR PERMANENT REPAIR IS 8502280201 9

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SALEM GENERATING STATION MONTHLY OPERATING

SUMMARY

- UNIT NO. 1 MARCH 1985 SALEM NO. 1 The Unit began the period operating at full power. On 3/07/85 at 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br /> Unit power was reduced to 79% as a result of 12E Intercept valve failing to reopen after completion of a routine turbine valve surveillance test. The valve failed to reopen as a result of a cut seat on the hydraulic dump valve. At 1657 hours0.0192 days <br />0.46 hours <br />0.00274 weeks <br />6.304885e-4 months <br />, with the completion of repairs, the Unit was returned to 100% power where it remained for the rest of the period. On March 31, 1985, No. 1 Unit's consecutive days in operation exceeded its previous record of 88 days.

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.. O REFUELING INFORMATION DOCKET NO.: 50-272 COMPLETED BY:. J. Ronafalvy UNIT NAME: Salem 1 DATE: April 10, 1985 TELEPHONE: 609/935-6000 EXTENSION: 4455 Month March 1985

1. Refueling information has changed from last month:

YES NO X

2. Scheduled date for next refueling: February 22, 1986
3. Scheduled date for restart following refueling: May 4,1986
4. A) Will Technical Specification changes or other license amendments be required?

YES NO NOT DETERMINED TO DATE B) Has the reload fuel design been reviewed by the Station Operating Review Committee?

YES NO X If no, when is it scheduled? January 1986

5. Scheduled date (s) for submitting proposed licensing action:

. January 1986 if required

6. Important licensing considerations associated with refueling:

NONE

7. Number of Fuel Assemblics:

A) Incore 193 B) In Spent Fuel Storage 296

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: September 2001 8-1-7.R4

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Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station April 10, 1985 Director, Office of Inspection and Enforcement U.S. Nuclear Regulatory Commission Washington, DC 20555

Dear Sir:

MONTHLY OPERATING REPORT SALEM NO. 1 DOCKET NO. 50-272 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 March 1985 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 l

  1. ~

J. M. Zupko, Jr.

General Manager - Salem Operations JR:sbh l cc: Dr. Thomas E. Murley i Regional Administrator USNRC Region I 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 of 8-1-7.R4 The Energy People 95 2183 (20M) 1181

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