ML18096A755
| ML18096A755 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 06/03/1992 |
| From: | Stone J Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| TAC-M79960, TAC-M79961, NUDOCS 9206120221 | |
| Download: ML18096A755 (24) | |
Text
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UNITED STATES
_NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 June 3, 1992 Docket Nos. 50-272 and 50-311 LICENSEE:
Public Service Electric and Gas Company FACILIT~: Salem Nuclear Generating Station, Units 1 and 2
SUBJECT:
SUMMARY
OF MEETING WITH PUBLIC SERVICE ELECTRIC AND GAS COMPANY (PSE&G) ON MAY 11, 1992, TO DISCUSS EMERGENCY DIESEL GENERATOR LOADS AND SURVEILLANCE TESTS (TAC NOS. M79960 AND M79961)
On May 11, 1992, PSE&G met with the NRC staff to discuss the emergency diesel generator (EDG) load analysis, surveillance test loading requirements, and EDG acceptance tests in support of an amendment request dated March 6, 1991 (LCR 87-07, Revision 1). The agenda for the meeting was included in the Meeting Notice dated April 27, 1992.
The staff's major concerns were that the latest load study shows the worst case total loading on the 2A EDG to be 2853 kW which is only 7 kW below the 2-hour rating of the EDGs of 2860 kW, and the total load that is automatically connected to the EDG is 2812 kW.
Each item from the agenda is repeated below with a summary of the licensee's response, including agreements and commitments for additional information.
- 1.
Discuss the basis for changing the power factor from 0.5 (1988 load study) to 0.4 (ES-9.002 load study) for motor-operated valves (MOVs).
Load study ES-9.002 noted that Limitorque reported a power factor range of 0.2 to 0.8. Also, there were many small loads that have had their kW requirements revised down without a basis for the revision being clearly stated in load study ES-9.002.
Based on telephone discussions with Limitorque, it was learned that the power factor for the motor operators was 0.8 for starting and 0.2 for running.
During stroking of the valves, 20% of the time the 0.8 number is used and 80%
of the time the 0.2 number is used, producing a weighted average of 0.32.
PSE&G used 0.4 for the power factor in the calculations.
The revised load study (ES-9.002) is a complete reanalysis of the EDG loads and supersedes the previous load study. All loads that are listed in the revised load study have a basis in other technical documents that are available at the site. There was no attempt to reconcile any difference between the previous load study and the revised load study because of the complete revision.
- 2.
Discuss how representative, in terms of population and expected load conditions, the assumption that the 230 volt motors will be loaded on the EDG at an average of 80% of their nameplate rating, given the 10%
sample that was used in load study ES-9.002.
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p PSE&G based the 80% of nameplate rating on a sample of 10 motors out of a total population of 90 motors for both Salem Units.
These 230 volt motors account for approximately 5% of the total load on the EOG.
PSE&G grouped the motors based on their application and determined the actual operating load of each motor in the sample.
A weighted average was then determined.
The weighted average was 83%, and 80% was used in the calculation.
PSE&G agreed to determine the impact on the total load on the EOG if a value of 95% of nameplate rating is used.
- 3.
Discuss the basis or assumption supporting the timing of the following loads in ES-9.002:
- a.
Cabinet space and jacket water heaters,
- b.
Reactor nozzle support fan, and
- c.
Charging pump.
The cabinet space and jacket water heaters are locked out by the safeguards equipment controller (SEC) for 1200 seconds.
At 1200 seconds, the lockout is removed and the equipment can be energized if required.
The reactor nozzle support fan* is automatically sequenced on by the SEC in the case of loss-of-offsite power (LOOP).
The fan is locked out by the SEC for the case of a loss-of-coolant accident (LOCA) with a LOOP.
The centrifugal charging pumps (CCP) are sequenced on by the SEC.
The positive displacement pump (PDP) is not controlled by the SEC.
It is administratively controlled by the emergency operating procedures (EOPs).
Currently, the EOPs take no credit for the PDP.
- 4.
Discuss what analyses or tests were performed to ensure that the EDG load accepting capabilities were not adversely impacted in terms of frequency and voltage regulation requirements as described in Regulatory Guide 1.9, Section C.4, given the revised load value for the service water pump (809 kW now vs 785 kW before).
There was one service water pump out of 12 that had the pump refurbished.
No changes were made to the motor.
The testing done by the vendor following completion of the refurbishment determined that the power requirements had increased from 785 kW to 809 kW and the inertia of the pump had increased by about 5%.
In the load study calculations, this higher value was used for all cases.
No special tests of the refurbished pump, in terms of frequency and voltage regulation requirements, were performed.
However, the initial tests of the EDGs, performed by the EOG vendor, included a step load increase of 1500 kW resistive load (see 5, below).
This load is greater than the load represented by the refurbished service water pump, thus showing the EOG is capable of accepting the load.
The tests that were performed by PSE&G were the normal 18-month surveillance tests. These tests include a load sequencing test where all auto connected loads, including the service water pumps, are sequenced onto the EDG.
Voltage and frequency are recorded before the loads are sequenced on and after all loads have been sequenced onto the bus to assure the technical specifications requirements are met.
In addition, a load rejection test is performed.
The EDG is operated at a load that is at least as great as the service water pump.
The EDG output breaker is then opened.
Voltage and frequency are monitored by the operators.
The technical specification requires voltage and frequency to recover within 4 seconds.
This timing is done by the operators using a stop watch.
PSE&G felt that the small increase in inertia would have a minimum affect on the starting current of the pump.
- 5.
Verify that the performance tests conducted by ALCO (the EDG vendor) adequately demonstrated the KVA rating of the diesel generator.
The staff has noted through electrical distribution system functional*
inspection (EDSFI) activities that ALCO has used, for qualification testing of safety grade diesel generators, resistive loads rather than reactive loads.
In addition, discuss whether those tests which established the diesel generator ratings were conducted under anticipated site conditions (i.e., cold start, step load increases).
For initial testing, ALCO included both reactive and resistive loads.
For reactive loads, 6.5 kva/horsepower with a 0.2 power factor was used.
For load sequence testing, resistive loads were used. A step load change of 1500 kW (resistive load), with the bus initially dead, was also included in the vendor tests to demonstrate the EDG's ability to accept large step increases in load.
During startup testing, a test that sequenced the loads on the EDGs was performed.
The test was done before fuel load with the head off the reactor vessel. This allowed the emergency core cooling system (ECCS) pumps to go to full run out conditions, thus achieving the maximum load represented by these pumps.
However, the containment spray and auxiliary feedwater pumps were on recirculation flow when the test was performed, so the maximum load that could be seen by the EDGs during an actual LOCA was not achieved.
During the performance of this test, the frequency fell below the values given in Regulatory Guide (RG) 1.9, but the frequency recovered within the time period specified in RG 1.9.
PSE&G agreed to provide information to the staff, about the frequency dip that occurred during initial testing. This test was conducted with the EDGs initially at ambient conditions.
- 6.
Identify what loads have been added and/or computational errors made since the initial licensing basis that have contributed to the present load profile which is contrary to the UFSAR statements (Section 8.3.1.5.1) that "... the maximum load to be 2750 kW for a maximum of about 30 minutes duration... The time period below 30 minutes, however, is characterized by a load no greater than 2600 kW".
PSE&G discussed the load increases and decreases that had occurred.
The major load increases were:
the runout condition of the ECCS and auxiliary feedwater pumps, service water pumps, and plant modifications that required connection
-. to the vital buses (i.e., Safety Parameter Display System, radiation monitoring system and security system). Also, the inclusion of MOVs and cable losses added to theincrease.
The major load decreases were the deletion of the PDP and the use of actual load on the inverters.
PSE&G agreed to provide the staff a written summary of the load increases and decreases.
- 7.
Are loads that are sequenced ON at 30 seconds considered auto-connected loads?
What is the auto-connected load total, under worst case design basis conditions?
Loads that are sequenced ON by the SEC are considered auto-connected loads.
For EOG IA and 2A, the time is 30 seconds; and for EDGs I8, 28, IC, and 2C,the time is 26 seconds.
The total maximum auto connected loads occur for all EDGs assuming a LOOP, LOCA and all EDGs operating, and are as follows:
EOG IA - 2772 kW EOG 18 - 2793 k~*J EOG IC - 2642 kW EOG 2A - 28I2 kW EOG 28 - 2716 kW EOG 2C - 265I kW
- 8.
The 50.59 evaluation, denoted IEA-I025, indicates that the current surveillance requirement 4.8.I.I.2.b.5 (Unit I) and 4.8.I.I.2.c.8 (Unit 2) to verify that the loads do not exceed the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> rating (2750 KW)of the EOG should be changed to the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> (2860 kW) rating.
Discuss how the existing surveillance procedure, as currently implemented, meets the 2750 kW limit and how you will assure that future load growth will not exceed the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> limit.
The current surveillance test is done with the ECCS pumps in recirculation.
The loads on the EDGs in this condition are less than the 2750 kW listed in the technical specifications.
PSE&G agreed to review the initial startup test (see 5 above) loading and compare the initial surveillance tests that were done to ensure load growth has not gone beyond the 2-hour rating of the EDGs.
This information will be provided to the staff.
Future load growth is controlled by the Design Change Process at PSE&G.
Any modifications to the plants are required to have a Design Change Package (DCP) developed.
The DCP details the modifications to be made, including any
_changes to the electric power requirements.
If the change represents a substantial increase in the power requirements from the EDGs, an equivalent reduction in power demand is required.
- 9.
The staff has noted via Information Notice 9I-I3 and through EDSFI activities that some licensees have not adequately addressed environmental factors that might impact the actual performance of the EDG.
Discuss what derating factors (i.e., ambient room temperature, combustion air temperature) have been considered concerning operation under accident conditions and when the EOG is tested.
PSE&G has looked at the ambient room temperature conditions for the EDGs and concluded that with the current limits, no derating of the EDGs is required.
The river water temperature has an FSAR limit of 85°F (there are no limits on river water temperature in the technical specifications). With the river water temperature below 85°F, the jacket water temperature and lube oil temperature remain below their alarms of 175°F and 185°F, respectively. It is PSE&G's position that ai long as the jacket water temperature and lube oil temperature remain below their alarm point, the EDG is not degraded.
PSE&G is revising the calculation to increase the river water temperature limit to 90°F.
This calculation will include an evaluation of whether or not the EDGs will be derated if the river water temperature reaches 90°.
PSE&G has agreed to provide the staff with a copy of the evaluation when completed.
- However, this evaluation is not necessary for the completion of the review of the amendment request.
- 10.
On page 5 of the Salem Station 50.59 evaluation, IEA-1025, the worst case one hour.transient is 2824 kW, 2798 kW, and 2673 kW for EDG lA, EDG 18 and EDG lC, respectively.
However, the load study, ES-9.002, shows the worst case value (i.e., highest value in the first hour) to be 2812 kW, 2838 kW, and 2687 kW for EDG lA, EDG 18, and EDG lC, respectively.
Please discuss.
PSE&G stated that the values in the 50.59 evaluation were "working numbers" that were inadvertently left in the safety evaluation and are not correct.
The 50.59 safety evaluation will be revised.
Enclosed is the handout used by PSE&G during the meeting and a list of attendees at the meeting.
IS/
Enclosures:
- 1.
Handout
- 2.
List of Attendees cc w/enclosures:
See next page DISTRIBUTION:
Docket File
- NRC & Local PDRs PDI-2 Reading TMurley/FMiraglia JPartlow SVarga JCalvo CMi ller OFFICE NAME DATE OFFICIAL FILENAME:
MO'Brien(2)
JStone OChopra James C. Stone, Senior Project Manager Project Directorate I-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation RLobel, EDO 17G21 EWenzinger, RGN-I JWhite, RGN-I Jenkins Lazarowitz, RGN-I OGC EJordan, 3701 ACRS 10 PDI-2 PM FROS A I ~/92 I I
1 *
- . PSE&G has looked at the ambient room temperature conditions for the EDGs and concluded that with the current limits, no derating of the EDGs is required.
The river water temperature has an FSAR limit of 85°F (there are no limits on river water temperature in the technical specifications). With the river water temperature below 85°F, the jacket water temperature and lube oil temperature remain below their alarms of I75°F and I85°F, respectively. It is PSE&G's position that as long as the jacket water temperature and lube oil temperature remain below their alarm point, the EOG is not degraded.
PSE&G is revising the calculation to increase the river water temperature.limit to 90°F.
This calculation will include an evaluation of whether or not the EDGs will be derated if the river water temperature reaches 90°.
PSE&G has agreed to provide the staff with a copy of the evaluation when completed.
- However, this evaluation is not necessary for the completion of the review of the amendment request.
IO.
On page 5 of the Salem Station 50.59 evaluation, IEA-I025, the worst case one hour transient is 2824 kW, 2798 kW, and 2673 kW for EOG IA, EOG I8 and EOG IC, respectively.
However, the load study, ES-9.002, shows the worst case value (i.e., highest value in the first hour) to be 28I2 kW, 2838 kW, and 2687 kW for fDG IA, EOG I8, and EOG IC, respectively.
Please discuss.
PSE&G stated that the values in the 50.59 evaluation were "working numbers" that were inadvertently left in the safety evaluation and are not correct.
The 50.59 safety evaluation will be r~vised.
Enclosed is the handout used by PSE&G during the meeting and a list of attendees at the meeting.
Enclosures:
I. Handout
- 2.
List of Attendees cc w/enclosures:
See next page James C. Stone, Senior Project Manager Project Directorate 1-2 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
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DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING NRC/PSE&G WORKING MEETING ROCKVILLE, MD MAY 11, 1992
DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING
SUMMARY
OF ITEMS
- 1. INTRODUCTION
- 2. CALCULATION REVISION HISTORY
- 3. NRC QUESTIONS AND ANl\\YERS
- 4. OPEN DISCUSSION
DIESEL LOAD CALCULATION EVOLUTION CONTRACT AWARDED TO PFEPAAE LOAD STll>Y SAR TABLE DISCREPANCY
& RtNJUT DIESEL LOADIN&
& LOAD CONTROL CIESTIONEO REPORT SCENARIO ISSlED HYPOllESIZED 12/87 12/87 12/88 DEF ISSUED PAA I
SAFETY &
EN6'6 MEMO ISSUED JUSTIFYING LOAD IN&
ACCEPTABILITY I
I OPERABILITY FEVIEW H
H 10/90 f
_j 9/90 SSFI 4/91 ATS ITEMS OPENED 5/91 tECHANICAl EOP REVIEW COMPLETE D/6 LOAD CALCULATION COMPLETE 9/91 12/91 e
DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING QUESTIONS AND ANSWERS 1 WHAT IS THE BASIS FOR MOTOR OPERATED VALVE POWER FACTORS THROUGHOUT THE LOAD STUDY?
1.1 CHANGE FROM.5 TO.4 Pf PER TELECON WITH UMITORQUE 1.2 VALVE STROKE TIMES LESS THAN 30 SECONDS 1.3 VALVES OPERATE AT 100% OF THE RA TWCI 1.4 POWER FACTOR CHANGES INSIGNIFICANT 1.5 OTHER LOADS
3100 3000
~ 2'UJ0
~ 2800
~ 2700
~ 2600 2500 2400 l ()I l f JI J. I.
- I.~ 1 ~1. * ~ J l
UILSLL GLNLHA I 01~ 2A
- CASL H L OCA & LOPA ALL DIESELS OPERATINC 3100 ( ~ HOUR>
*-*e-************-*****---*********----------------********--------------------------------------------------------------------------~------
266 2188 1
q 12""
e 5
v AffEL-n=:J>
l.~E TIME IN f=iRAr/\\£.
tAo\\J'~ @
- 4 3000 7200
<2 HRS>
3600 l220
<l HOUR>
SECONDS VF 50420 2365'.J I
I *
- I I * * * *.
86488 l24 HRS 50400 72000
<14 HRS) <20 HRS>
3100 3000
~ 2900
~ 2800
~ 2700
~ 2600 2500 2400 1
q 0
5 13
-:---i LALL NU. lS-Y.~02-0 f
I DIESEL GENERA TOR 2A - CASE B LOCA & LOPA ALL -DIESELS OPERA TING
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j r,
266 ti I l I
3100 < ~ HOUR) 1200
<2 HOUR>
i 3000 7200 50420 2365~
8648 (2'4 HRS>
1 I
/
-*--v
<2 HRS>
3600 7220 (1 HOUR>
':l04"1'1 1c000 TIME IN SECONDS N\\ov 's. @.
DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING 2 HOW REPRESENTATIVE WAS 230 VOLT MOTOR SAMPLING?
2.1 DISCUSSION 2.2 10% OF APPROXIMATELY 100 MOTORS WERE SAMPLED 2.3 RANGE OF MOTORS IS.05 TO 30 HORSEPOWER 2.4 ROOM COOLING UNITS AND CHILLERS WAS THE LARGEST GROUP REPRESENTING ABOUT 225 HORSEPOWER THESE UNITS AVERAGED LESS THAN 80% USE FACTOR 2.5 MISCELLANEOUS PUMPS WERE THE SECOND LARGEST GROUP REPRESENTING 197 HORSEPOWER AND AVERAGED 81 % USE FACTOR 2.6 VENT FANS WERE THE SMALLEST GROUP REPRESENTING 134 HORSEPOWER WHICH HAD A 99% LOAD FACTOR
- 2. 7 230 VOLT MOTOR LOADS REPRESENT 5% OF EOG CONTINUOUS RATING MOTOR TYPE
- IN
22 225 76%
.308 MISC. PUMPS 2
36 197 81%
.287 VENT FANS 3
32 134 99%
.239 TOTALS 10 90 556 84%
83%
DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING 3 DISCUSS THE BASIS FOR ASSUMPTION SUPPORTING THE TIMING OF THE FOLLOWING LOADS IN ES-9.002 3.1 CABINET SPACE AND JACKET WATER HEATERS 3.2 REACTOR NOZZLE SUPPORT FAN 3.3 CHARGING PUMPS
' I
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DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING 4 HOW WAS THE ACCEPTABILITY OF THE SERVICE WATER PUMP HORSEPOWER CHANGE DOCUMENTED 4.1 DISCUSSION 4.2 NO MOTOR CHANGE OUT WAS PERFORMED 4.3 EVALUATION OF STEADY STATE CONDmONS WAS PERFORMED 4.4 NO SIGNIFICANT CHANGE TO MOTOR STARTING CHARACTERISTIC
DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING 5 DISCUSS HOW THE FACTORY ACCEPTANCE TEST DEMONSTRATED ADEQUACY OF DIESEL GENERA TORS 5.1 FACTORY TESTING INCLUDED BOTH RESISTIVE AND INDUCTIVE TESTING 5.2 STARTUP TESTING FURTHER SUPPORTED ACTUAL LOADS 5.3 ENVIRONMENTAL CONDITIONS
1' DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING 6 DISCUSS LOAD CHANGES UP THROUGH THE PRESENT REVISION OF THE LOAD STUDY
- 6. 1 INCREASES 6.2 DECREASES
alllll. GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTWG 7 DEFINE AUTO CONNECTED LOADS 7.1 SAFEGUARDS EQUIPMENT CONTROLLER SEQUENCED LOADS 7.2 AUTO CONNECTED LOADS ARE CONSIDEMD TO
- THOSE LOADS THAT ARE OPERATING AT THE END OP THE SEQUENCER SEQUENCE
DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING 8 DISCUSS HOW EXISTING SURVEILLANCE PROCEDURE TO VERIFY AUTO-CONNECTED LOADS s 2750 KW IS MET, AND HOW WE WILL ASSURE FUTURE LOAD GROWTH WILL NOT RESULT IN EXCEEDING 2860 KW 8.1 EVERY 18 MONTH DIESEL GENERA TOR MAINTENANCE AND SURVEILLANCE PERFORM ROUTINE MAINTENANCE ON EMERGENCY DIESEL GENERATOR (EOG) ENGINE, GENERATOR, AND AUXILIARY EOG EQUIPMENT 8.2 PERFORM POST MAINTENANCE ENGINE RUN
- 1. MEASURE AND RECORD ENGINE PARAMETERS
- 2. OBSERVE ENGINE, GENERATOR, AND AUXILIARY EQUIPMENT PERFORMANCE
- 3. PERFORM EOG ONE-HOUR SURVEILLANCE OPERABILITY RUN 8.3 PERFORM 24 HOUR EOG ENDURANCE RUN (UNIT 2 ONLY) 1
AND 22 HOURS ATS!!:: 2600 KW (CONTINUOUS RATING) WHILE MAINTAINING STEADY STATE VOLTAGE AND FREQUENCY RANGE
- 2. PERFORM ESF AUTO EOG START VIA SEC WITHIN 5 MINUTES OF STOPPING EOG AND VERIFY EOG OPERA TES FOR ::: 5 MINUTES WHILE MAINTAINING STEADY STATE VOLTAGE AND FREQUENCY RANGE
~*..
DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING 8.4 ESF - MANUAL SAFETY INJECTION TEST 1. MANUALLY INITIATE ACCIDENT PLUS BLACKOUT SIGNAL VERIFY ACTUAL EOG ELECTRICAL LOAD IS ~ 2750 KW
- 2. MANUALLY INITIATE A BLACKOUT SIGNAL VERIFY ACTUAL EOG ELECTRICAL LOAD IS ~ 2750 KW
- 3. PERFORM ACCIDENT TRAIN "A" LOADING TEST
- 4. PERFORM ACCIDENT TRAIN "B" LOADING TEST
. 8.5 PERFORM ~4 HOUR LOAD STUDY RUN (UNIT 1 ONLY)
- 1. SIMILAR TO UNIT 2'S 24 HOUR ENDURANCE RUN 8.6 FUTURE LOAD GROWfH REVIEWED AS PART OF DESIGN CHANGE PACKAGE PROCESS DESIGN CONSIDERATIONS CHECKLIST TECHNICAL STANDARD "ELECTRIC LOAD CONTROL"
I
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DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING 9 DISCUSS WHAT DERATING FACTORS (I.E., AMBIENT ROOM TEMPERATURE, COMBUSTION AIR TEMPERATURE) HAVE BEEN CONSIDERED CONCERNING OPERATION UNDER ACCIDENT CONDITIONS AND WHEN THE EOG IS TESTED 9.1 AMBIENT ROOM TEMPERATURE ONCE THROUGH VENTILATION SYSTEM FOR EACH EOG ROOM ORIGINAL DESIGN: MAINTAIN 110 F BASED ON 95 F INLET AIR REVIEW DURING CBD EFFORT CALCULATED TEMPERATURE AT EXHAUST DUCT INLET = 136 F VOLTAGE REGULATOR/EXCITER PANEL AND GENERATOR LOCATED UPSTREAM OF DIESEL ENGINE ENGINEERING EVALUATION OF EQUIPMENT CRITICAL FOR EOG OPERATION WAS PERFORMED AND DETERMINED ACCEPTABLE 9.2 JACKET WATER AND LUBE OIL COOLING COMBUSTION AIR IS OUTSIDE AMBIENT FROM SEPERA TE DUCT JACKET WATER HEAT EXCHANGER COOLS ENGINE AND TURBOCHARGER 85 F RIVER WATER, 170 F MAX JACKET WATER 90 F RIVER WATER, 174 F 175 F HI TEMP ALARM LUBE OIL 180 F@ 85 F 184 F@90 F 185 F HI TEMP ALARM
DIESEL GENERATOR LOAD ANALYSIS AND ACCEPTANCE TESTING 10 DISCUSS THE NUMERICAL DISCREPANCl~S IN 50.59, 1EA-1025 10.1 "WORKING NUMBERS" ERRANTLY LEFT !N SAFETY EVALUATION
MEETING ATTENDEES DIESEL GENERATOR TESTING AND LOADING, SALEM 1 & 2 NAME James Stone M. Eugene Lazarowitz Louis Miceli Bill McTigue Ronalda V. Jenkins
- 0. P. Chopra Moises L. Burstein M. Mortaarulo T. Haehl e Raymond Brown May 11, 1992 ORGANIZATION NRC/NRR/PDI-2 NRC/RGN-1/DRS EB PSE&G Salem Tech Dept EBASCO/PSE&G Licensing NRC/NRR/SELB NRC/NRR/SELB PSE&G PSE&G PSE&G PSE&G ENCLOSURE 2
4 1,
IP F'.Ji.J\\ *: c. :icrv*i ce Electric & Gas Company 41t cc:
Mark-J. Wetterhah~, Es~uire Winston & Strawn 1400 L Street NW Washington, DC 20005-3502 Richard Fryling, Jr., Esquire Law Department - Tower SE 80 Park Place Newark, NJ 07101 Mr. Calvin A. Vondra General Manager - Salem Operations Salem Generating Station P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. S. LaBruna Vice President - Nuclear Operations Nuclear Department P.O. Box 236 Hancocks Bridge, New Jersey 08038 Mr. Thomas P. Johnson, Senior Resident Inspector Salem Generating Station U.S. Nuclear Regulatory Commission Drawer I Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection CN 415 Trenton, NJ 08625-0415 Maryland People's Counsel American Building, 9th Floor 231 East Baltimore Street Baltimore, Maryland 21202 Mr. J. T. Robb, Director Joint Owners Affairs Philadelphia Electric Company 955 Chesterbrook Blvd., 51A-13 Wayne, PA 19087 Salem Nuclear Generating Station, Units 1 a92 Richard Hartung Electric Service Evaluation Board of Regulatory Commissioners 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Lower Alloways Creek Township c/o Mary 0. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Mr. Frank X. Thomson, Jr., Manager Licensing and Regulation Nuclear Department P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David Wersan Assistant Consumer Advocate Office of Consumer Advocate 1425 Strawberry Square Harrisburg, PA 17120 Mr. J. A. Isabella MGR. - Generation Department Atlantic Electric Company P.O. Box 1500 1199 Black Horse Pike Pleasantville, NJ 08232 Carl D. Schaefer External Operations - Nuclear Delmarva Power & Light Company P.O. Box 231 Wilmington, DE 19899 Public Service Commission of Maryland Engineering Division ATTN:
Chief Engineer 231 E. Baltimore Street Baltimore, MD 21202-3486 Mr. Steven E. Miltenberger Vice President and Chief Nuclear Officer Public Service Electric & Gas Company Post Office Box 236 Hancocks Bridge, New Jersey 08038