ML20101B206
| ML20101B206 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 11/30/1984 |
| From: | Ronafalvy J, Zupko J Public Service Enterprise Group |
| To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE) |
| References | |
| NUDOCS 8412200167 | |
| Download: ML20101B206 (13) | |
Text
E 1
AVERAGE DAILY UNIT POWER LEVEL' Docket No.
50-272 Unit Name Salem # 1
'Date Dec. 10,1984
. Completed by J.
P.
Ronafalvy Telephone 609-935-6000 Extension 4455 Month November 1984 Day Average Daily Power Level Day Average Daily Power Level (MWe-NET)
(MWe-NET) 1 420 17-0 2
785 18 0
3 555 19 0
4 134 20 0
5 817 21 0
6 250 22 86 4
7 0
23 755 8
0 24 935 9
242 25 969 10 876 26 935 11 8
27 806 12 0
28 797 13 0
29 894 14 0
30 894 15 0
31 16 0
l P.
8,1-7 R1 4 -
8412200167 841130" PDR ADOCK 05000272 R
PDR page 1 of 12
\\/
OPERATING DATA 1 REPORT Docket No.50-272-q Date Dec'.
10, 1984-Telephone 935-6000-TCompleted'by.
J.
P.'Ronafalvy
~ Extension 4455
' Operating Status 1.
. Unit Name Salem No.
l'
' Notes 2..
. Reporting ?eriod November 1984 3.
Licensed Thermal Power (MWt) 3338 4.
NameplateJRating (Gross MWe)
- 1135 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. Rat-ings (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 8040 65065
' 12. No. of Hrs. Reactor was Critical 438.3 2044.7 35195.9
- 13. Reactor Reserva Shutdown Mrs.
0 54.5 3088.4-
- 14. Hours Generator On-Line 366.7 1770.1 33548.0
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 903559 5092629 100912000
- 17. Gross Elec. Energy Generated (MWH) 288570 1673990 33289090
- 18. Net Elec. Energy-Generated (MWH) 261671 1529672 31500984
- 19. Unit Service Factor
-50.9 22.0 51.5
- 20. Unit Availability Factor 50.9 22.0 51.5
- 21. Unit Capacity Factor i
(using MDC Net) 33.7 17.6 44.8
- 22. Unit Capacity Factor (using DER Net) 33.3 17.5 44.4
- 23. Unit Forced Outage Rate 49.1 68.9 33.6
- 24. Shutdowns scheduled over next 6 months (type, date and duration ~of each)
N/A s
- 25. If shutdown at end of Report Period, Estimated Date of Startup:
N/A
- 26. Units in Test Status (Prior to Commercial Operation):
Forecast Achieved L
Initial Criticality 9/30/76 12/11/76 Initial. Electricity 11/1/76 12/25/76
[
Commercial Operation 12/20/76 6/30/77 l
8-1-7.R2 l
Page of i
6 page 2 of 12
~
UNIT SHUTDOWN AND POWER REDUCTIONS Docket No.50-272 REPORT MONTH November 1984 Unit Nase Salen No.1 Date
~Dec.
10,198/.
Completed by J.P.
Ronafalvy Telephone 609-935-6000 Extension 4455 Method of Duration Shutting License Cause and Corrective No.
Date Type Hours Reason Down Event System Component Action to 1
2 Rea cto r Report Code 4 Code 5 Prevent Recurrence Loss of Vacuum /High 84-202 10-30 F
14.2 A
5 HA XXXXXX Back Pressure Loss of Vacuum /High 84-204 11-01 F
8.4 A
5 HA XXXXXX Back Pressure Loss of Vacuum /Hign 5
HA XXXXXX Fack Pressure 84-206 11-01 F
3.4 A _
Feedwater Heater 84-210 11-02 F
5.2 A
5 HH PUMPXX Drain Pumps Stator Windings84-212 11-03 F
3.9 A
5 HA INSTRU Terminals Bushings Stator Windings84-214 11-03 F
20.5 A
5 HA INSTRU Terminals Bushings Stator Windings84-216 11-04 F
5.9 A
1 HA INSTRU Terminals Bushings Turbine Governing 84-222 11-06 F
72.8 A
3 HA INSTRU System Control Turbine Governing HA INSTRU System Control 84-228 11-11 F
274.6 A
3 Other Steam 84-234 11-27 F
34.3 A
5 HA INSTRU Turbine Problems 1
2 Reason 3 Method 4 Exhibit G 5 Exhibit i 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 F-Administrative 5-Load Reduction Event Report mj G-Operational Error-explain 9-Other (LER) File t
1 o H-Other-explain (NUREG 0161) w Om 4
.m
_m si
. MAJOR PLANT. MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH November 1984
. UNIT NAME:
Salem 1 DATE:. December 10, 1984 COMPLETED BT:
J.
Ronafalvy TELEPHONE:
609/339-4455
- DC R NO. -
PRINCIPLE SYSTEM
-SUBJECT 1ET-1166 Incore Instrumentation Disconnect the P-250 computer from:the incore flux mapping-system.
Connect to,the flux mapping system a-Hewlett-Packard multiprogrammer will be;
_ mounted in Rack #77.
I 1EC-1488-
' Security Make additions and modifications as required to improve overall efficiency of the existing security system.
I 1EC-1735 Security Install high mast. (100')
i lighting fixtures and upgrade existing yard and perimeter lighting.
1EC-1809 Reactor Coolant-Pump Modify the shaft vibration Monitors monitor. system to eliminate erroneous vibration monitor readings.
Changes include improving design of bracket, j
replacing M90 probes with M93 (M93A) probes, and isolate drivers from ground.
i l
1SC-0051 Storage Facility Install compressed gas storage facility.
1SC-1331 Chilled Water Install an additional suction
[
gauge no greater than 40 psi for 11 and 12 Chilled Water i
Pumps.
Gauges for use during l
4.0.5.P testing of the pumps.
Page 4 of 12
i
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MAJOR PLANT MODIFICATIONS DOCKET NO.:
50-272 REPORT MONTH NOVEMBER 1984 UNIT NAME:
Salem 1 DATE:
December 10, 1984 COMPLETED BY:
J.
Ronafalvy TELEPHONE:
609/339-4455
- DCR NO.
SAFETY EVALUATION 10 CFR 50.59 1ET-1166 This DCR permits a portable computer to obtain data from non-safety grade instrumentation.
No unreviewed safety or environmental questions are involved.
1EC-1488 This DCR provides additional security barriers.
It.will not add any structural item that could inhibit the safe shutdown of the NSSS equipment.
This modification will not alter any plant process or discharge and will not affect the existing environmental impact of the plant.
No unreviewed safety or environmental questions are involved.
1EC-1735 This DCR upgrades the yard security lighting.
No unreviewed safety or environmental questions are involved.
1EC-1809 This DCR modifies the shaft vibration monitor system.
No unreviewed safety or environmental questions are involved.
- DCR - Design Change Request page 5 of 12
- DCR NO.
SAFETY EVALUATION 10 CFR.50.59 ISC-0051 This DCR installs a compressed gas storage facility.
The following precautions have been incorporated:
1.
Only non-combustible materials are permitted to be used; 2.
Adequate separation from other buildings and equipment; 3.
The facility is to be surrounded by a 7' high chain link fence; 4.
Storage stalls are divided by concrete block walls; 5.
A pitched floor is used to prevent accumulation of water; 6.
Single slope roof design is used to prevent the a
accumulation of gas; 7.
Pad eyes and pipe railings are provided for chains to secure the gas bottles in an upright position; and 8.
Storage stalls are well ventilated.
No unreviewed safety or environmental questions are involved.
1SC-1331 All potential, realistic failure modes have been considered and found to be not applicable.
In accordance with ASME Section XI gauges are no more than four (4) times the reference value.
No unreviewed safety or environmental questions are involved.
]
)
- DCR - Design Change Request i
l J
page 6 of 12
PSE&G SALEM GENERATING STATION SAFETY RELATED WORK ORDER LOG SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099124181 1
NO. 15 SERVICE WATER PUMP STRAINER SMD FAILURE DESCRIPTION:
MOTOR IS TRIPPING OUT CONSTANTLY CORRECTIVE ACTION:
REPLACE MOTOR 84-07-02-069-9 SIC 1
1R3 FAILURE DESCRIPTION:
PERIODICAT.LY SPIKES HIGH 4
CORRECTIVE ACTION:
REPLACED DETECTOR: ADJUSTED ZERO 84-07-01-048-1 SIC 1
1R24A SEAL INJ. FILTFR FAILURE DESCRIPTT.ON:
MONITOR IS FAILED HIGH CORRECTIVE ACfION:
REPLACED DETECTOR 0099122561 SIC 1
1R15 FAILURE DESCRIPTION:
DETECTOR IS ALARMING FOR NO REASON CORRECTIVE ACTION:
REPLACED DETECTOR e
t;
SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 84-11-23-065-1 SMD 1
NO. 11 SERVICE WATER PUMP STRAINER FAILURE DESCRIPTION:
BROKEN SHEAR PIN CORRECTIVE ACTION:
REPLACED SHEAR KEY, BARREL SEAL PLATES AND O-RINGS 84-11-26-086-1 SMD 1
VALVE NO. 12SW24 FAILURE DESCRIPTION:
DIAPHRAGM IS LEAKING CORRECTIVE ACTION:
REPLACED DIAPHRAGM 0099124092 SMD 1
AUX. FEED STORAGE TANK RECIRC PUMP FAILURE DESCRIPTION:
PUMP SEIZED CORRECTIVE ACTION:
REPLACED MECHANICAL SEAL 0099125765 1
NO. 11 B. A. TRANSFER PUMP SMD FAILURE DESCRIPTION:
LEAK UNDER PUMP INSULATION CORRECTIVE ACTION:
REPLACED SEAL 84-10-31-002-3 1
NO. 11 WASTE GAS COMPRESSOR SMD FAILURE DESCRIPTION:
DOES NOT START ON SIGNAL FROM 104 PANEL CORRECTIVE ACTION:
REPLACED CONTROL COIL IN BREAKER 9*a m
- O b
SALEM UNIT 1 WO NO DEPT UNIT EQUIPMENT IDENTIFICATION 009901361-4 SIC 1
NO. 11 LOOP HOP LEG RTD - NARROW RANGE (TE411A)
FAILURE DESCRIPTION:
RTD FAILED CORRECTIVE ACTION:
REPLACED RTD 0099128900 1
NO. 11 CHILLED WATER RECIRC. PUMP SMD FAILURE DESCRIPTION:
WATER LEAKING THROUGH PUMP SEALS CORRECTIVE ACTION:
REBUILT PUMP 84-10-30-075-3 1
NO. 13 STEAM GENERATOR FEED FLOW RECORDER SIC FAILURE DESCRIPTICN:
INDICATOR SIGNAL NOT BEING TRACKED PROPERLY CORRECTIVE ACTION:
REPLACED SERVO AMP 0099026741 1
CONTAINMENT APD PUMP SIC FAILURE DESCRIPTION:
SAMPLE PUMP FOR 1RllA, 1R12A AND 1R12D IS SEIZED CORRECTIVE ACTION:
NEW PUMP INSTALLED 84-05-24-125-6 SMD 1
VALVE 14AF126 FAILURE DESCRIPTION:
VALVE BROKEN, WILL NOT CLOSE CORRECTIVE ACTION:
REPLACED VALVE
?>
fi m
Mt G
l.
I
.g SALEM UNIT 1 WO-NO DEPT UNIT EQUIPMENT IDENTIFICATION 0099122251 SIC 1
VALVE 1CV172 FAILURE DESCRIPTION:
VALVE WILL NOT STAY IN AUTO i
CORRECTIVE ACTION:
REPLACED 800 MFD CORP. ON SERVO SET-POINT STATION-84-09-01-012-7 SMD 1
VALVE 11RS30 FAILURE PESCRIPTION:
VALVE LEAKS CORRECTIVE ACTION:
REPLACED VALVE AS PER DCR 1ED-0351 84-09-07-061-8 SIC 1
RNST HI/LO LEVEL FAILURE DESCRIPTION:
OVERHEAD ANNUNICATOR D-35 IS ILLUMINATED WITH LEVEL IN SPEC.
CORRECTIVE ACTION:
RECALIBRATED 0099021323 SMD 1
1A DIESEL EXPANSION TANK LEVEL FAILURE DESCRIPTION:
LEVEL IS STUCK IN THE LOW POSITION CORRECTIVE ACTION:
REPLACED LEVEL DEVICE 84-09-19-019-2 SMD 1
NO. 11SW24 BACKWASH VALVE FAILURE DESCRIPTION:
VALVE NOT STROKING PROPERLY
'c CORRECTIVE ACTION:
REPLACED VALVE BODY AND INSTALLED NEW DIAPHRAGM u
o Om N
t
SALEM GENERATING STATION MONTHLY OPERATING
SUMMARY
- UNIT NO. 1 OCTOBER 1984 The period began with the reactor at -84% power experiencing Condenser vacuum problems.
On 11/01/84, the vacuum leak was discovered and repaired.
At 1323 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.034015e-4 months <br />, on 11/03/84, the Unit began load reduction, from 85% power to 25% power, due to high differential temperature in the stator coils.
Following investigations and test and with Westinghouse concurrence the three thermocouples in question were declared unreliable and would be repaired at the next available opportunity.
At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />, on 11/04/84 a controlled shutdown commenced as a result of periodic low-low flow alarm indications on the Stator Water System.
Investigations revealed the method utilized to periodically purge the Stator Water System, which utilized a pressure gage found to be out of calibration, resulted in cavitation of the Stator Water Pumps.
The gage was replaced and more conservative limits established for the purge operation.
The Unit was re-synchronized at 1925 hours0.0223 days <br />0.535 hours <br />0.00318 weeks <br />7.324625e-4 months <br /> on 11/04/84.
On 11/06/84 at 0645, a Reactor Trip occurred from #13 Steam Generator Low-Low Level.
The trip was due to operation of the Electro-Hydraulic Control (EHC)
System which resulted in a complete load reduction from 86% power.
Extensive investigation including simulated operation of the EHC System could not produce the exact cause of the transient.
Following instrumentation of various signals associated with the EHC System the Unit was returned to service on 11/09/84 at 0732.
On 11/11/84 at 0109, the Unit experienced at trip from 93% reactor power as a result of #13 Steam Generator Low-Low Level.
Conditions surrounding the trip were similar to those experienced on 11/06/84.
The Unit was brought to cold shutdown (Mode 5) to repair non-isolable steam leaks associated with a turbine stop valve, a safety injection check valve and two main steam isolation by-pass valves.
Further extensive research and testing was conducted to determine the initiating problem that resulted in the past two reactor trips from No. 13 Steam Generator Low-Low Level.
Sinulated input signals to the EHC System revealed proper functioning of that system.
No failed components were identified.
Several cards in the EHC System that could have initiated the sequence of events, leading to the two (2) reactor trips, were replaced.
The reactor began heatup 'on 11/17/84 and entered Mode 3 on 11/18/84 at 0421 hours0.00487 days <br />0.117 hours <br />6.960979e-4 weeks <br />1.601905e-4 months <br />.
With the completion of required surveillances, the reactor wcs brought critical on 11/20/84 at 1935 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.362675e-4 months <br /> and synchronized on 11/22/84 at 1148 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.36814e-4 months <br />.
During startup and power operation additional monitoring (to that established previously) of the EHC System to detect any abnormalities was performed.
Thic monitoring is continuing.
As the period ended, the Unit was operating at 85% of rated power to evaluate Generator stator coil differential temperature readings.
.page 11 of 12 l
e e
REFUELING INFORMATION DOCKET NO.:
50-272 COMPLETED BY:
J. Ronafalvy UNIT NAME:
Salem 1 DATE:
December 10, 1984 TELEPHONE:
609/935-6000 EXTENSION:
4455 Month November 1984 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 DETEPMlllED TO DATE 10/1/84 B)
Has the reload fuel design been reviewed by the Station Operating Review Committee?
YES NO X
If no, when is it scheduled?
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 Assemblies:
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 l
l page 12 of 12
f,.
c O PSEG Public Service Electric and Gas Company P.O. Box E Hancocks Bridge, New Jersey 08038 Salem Generating Station December 10, 1984
' 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 November 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 Gunmary Refueling Information Sincerely yours, 4_-!&
J. M.
Zupko, Jr.
General Manager - Salem Operations JR:sbh cc:
Dr. Thomas E. Murley Regional Administrator USNRC 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 Phge of 8-1-7.R4 gG l l Tho Entngy Peeph)
% JIT)(2 TAO 1t81 s