ML18081B024
| ML18081B024 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 02/04/1980 |
| From: | Librizzi F Public Service Enterprise Group |
| To: | Schwencer A Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML18081B025 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-578 NUDOCS 8002080636 | |
| Download: ML18081B024 (8) | |
Text
Public Service Electric and Gas Company 80 Park Place Newark, N.J. 07101 Phone 201 /430-7000 Mr. A. Schwencer, Chief Operating Reactor Branch #1 Division of Operating Reactors U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Gentlemen:
SALEM GENERATING STATION UNIT NO. 1 RESPONSES TO NRC INQUIRIES AT AUXILIARY FEEDWATER SYSTEM MEETING February 4, 1980 Representatives from your staff and PSE&G met in Bethesda on January 3, 1980 to review the Salem response to NUREG 0578, Item 2.l.7a and 2.l.7b on the auxiliary feedwater system.
At this meeting, a number of items were requested to be submitted by PSE&G to assist in your review of Salem.
Attached are the responses to the inquiries.
Two copies of the drawings re-quested are also attached.
PAM:to'g Attachments CENTENNIAL OF LIGHT (d
1879 1979 General Manager -
Electric Production
'8002080 63.~
95-2001 (300M) 1-79
SALEM GENERATING STATION UNIT NO. 1 INFORMATION SUBMITTAL TO RESPOND TO NRC INQUIRIES FROM AUXILIARY FEEDWATER MEETING JANUARY 3, 1980
- 1.
Submit functional drawings showing the isolation devices for protection and control circuits.
RESPONSE
Two copies of the following PSE&G drawings for Salem are attached:
220431-B-9524-3 220433-B-9524-3 220435-B-9524-3 220437-B-9524-3 Functional Diagram -
No. 11 & 21 Steam Generator Control and Protec-tion Levels.
Functional Diagram -
No. 12 and 22 Steam Generator Control and Protec-tion Levels.
Functional Diagram -
No. 13 and 23 Steam Generator Control and Protec-tion Levels.
Functional Diagram -
No. 14 and 24 Steam Generator Control and Protec-tion Levels.
These drawings show the steam generator narrow range level initiating signals circuitry for reactor trip and auxiliary feedwater actuation and their use in feedwater control.
Signal isolators are shown in the circuits for separation between the protection and control portions of the circuits.
- 2.
Provide documentation references describing the initiat-ing circuit isolation devices and fault protection.
RESPONSE
A brief description of protection circuit isolation is provided in the Salem FSAR on Page 7.2-6 and 7.2-16.
The Salem FSAR references two Westinghouse documents for a detailed discussion of isolation cir-cuits.
These two reports are WCAP-7824, "Isolation Test -
Process Instrumentation Isolation Amplifier, Westing-house Computer and Instrumentation Division, Model 131-110" and WCAP-7672, "Solid State Logic Protection System Description".
- 3.
Submit the 125 volt DC control schematics for the motor operated pumps.
RESPONSE
Two copies of the following PSE&G drawings for Salem are attached.:
203312-B-9768-13 203315-B-9769-13 Control Schematic -
No. 11 and 21 Auxiliary Feedwater Pumps Control Schematic -
No. 12 and 22 Auxiliary Feedwater Pumps
- 4.
Provide information on minimum requirements for auxil-iary feedwater system operation as defined in safety analyses.
RESPONSE
The Salem FSAR establishes the safety re-quirements for the auxiliary feedwater system in the "Accident Analysis", Section 14.
In the loss of normal feedwater transient, the safety analysis of the incident was performed assuming only one motor driven auxiliary feedwater pump is operable deliv-ering flow to two steam generators (refer to FSAR Page 14.1-38).
In the feedwater line rupture accident, the safety analysis of the incident was performed assuming auxiliary feedwater initiation with a flow of 426 gpm (refer to FSAR Page 14.3-22).
The results of both analyses demonstrated that the plant is maintained in a safe condition.
As stated at the meeting and presented in the Salem FSAR Section 10.2, the two motor driven pumps are each rated at 440 gpm and the one turbine driven pump is rated at 880 gpm.
The design of the automatic, as well as the manual initia-tion circuits of the auxiliary feedwater system at Salem, is adequate to assure that the minimum require-ments are met.
In addition, the Salem Unit #1 design was reviewed by the NRC staff and found acceptable on the basis of mini-mum requirements and single failure criterion to assure that a minimum auxiliary feedwater flow of 440 gpm is delivered to two steam generators.
The results of that review were documented on Pages 10-5 to 10-7 of the AEC (NRC) Safety Evaluation of the Salem Nuclear Generating Station, Units 1 and 2, dated October 11, 1974.
- 5.
Provide a description of the system level annunciation when portions of the auxiliary feedwater system are out of service.
RESPONSE
Administrative controls are utilized for alerting operators of the inoperability of the auxiliary f eedwater system due to maintenance/testing of equip-ment.
The unavailable equipment log and tagging request procedure assure that the operators are aware of the out-of-service status for the system.
Technical speci-fications have been established which limit the out-of-service time for the system.
In addition, individual alarms are printed out on the Salem auxiliary annunciator system in the Control Room alerting the operator to conditions/potential conditions in which equipment of the auxiliary feedwater system may not operate properly when called upon.
Such alarms would result in investigation or confirmation of the status of the auxiliary feedwater system.
The alarms provided are indicated on Table 1.
The combination of administrative controls and the above noted alarms provide the operator with sufficient infor-mation to determine the operability status of the auxil-iary feedwater system.
- 6.
Provide qualification documentation references for the following specified auxiliary feedwater system equipment:
Transmitter (low level)
Logic Equipment Instrument Racks Actuation Device
RESPONSE
Table 2 lists an example of each item re-quired with data concerning equipment qualification.
Similar information was previously provided in the re-sponse to FSAR questions 7.18 and 7.30.
Only the steam generator narrow range level transmitters have undergone environmental qualification testing.
The remaining items are not located in areas subject to an adverse en-vironment (provided with Class lE ventiliation system) or are not required to operate due to redundant equip-ment in other areas if an adverse environment results because of high energy line breaks.
- 7.
Revise Salem response to NUREG 0578, Item 2.l.7b to in-dicate the use of the wide range steam generator levels as a backup indication for auxiliary feedwater flow.
RESPONSE
The response to Item 2.l.7b will be revised to reflect the operator's use of the following parame-ters for the determination of proper auxiliary feedwater system operation:
auxiliary feedwater flow steam generator narrow range levels steam generator wide range levels auxiliary feedwater valve positions auxiliary feedwater pump discharge pressure auxiliary feedwater pump status JPG:jb HP12 1/4
SALEM GENERATING STATION UNIT NO. 1 RESPONSE TO NRC/AFW MEETING 1/3/80 Table 1 Auxiliary Annunciator Alarms for Auxiliary Feedwater System Alarms due to testing of protection system logic Train A - No. 11 Aux. FW Pump Start Blocked Train A - No. 13 Aux. FW Pump Start Blocked Train B - No. 12 Aux. FW Pump Start Blocked Train B - No. 13 Aux. FW Pump Start Blocked Alarms for pump inoperability No. 11 Aux. FW Pump - Loss of 125V DC No. 11 Aux. FW Pump - Loss of 28V DC No. 12 Aux. FW Pump - Loss of 125V DC No. 12 Aux. FW Pump - Loss of 28V DC No. 13 Aux. FW Pump & Turbine - Loss of 125V DC No. 13 Aux. FW Pump & Turbine - Loss of 28V DC No. 13 Aux. FW Pump Speed Control - Loss of 115V AC Alarms for valve inoperability Aux. FW Valve llAFll - Out of position/Loss of 115V AC Aux. FW Valve 12AF11 - Out of position/Loss of 115V AC Aux. FW Valve 13AF11 - Out of position/Loss of 115V AC Aux. FW Valve 14AF11 - Out of position/Loss of 115V AC Aux. FW Valves 11-14AF11 - Loss of 28V DC Aux. FW Valves 11-12AF21 - Out of position/Loss of 115V AC Aux. FW Valves 11-12AF21 - Loss of 28V DC Aux. nJ Valves 13-14AF21 - Out of position/Loss of 115V AC Aux. FW Valves 13-14AF21 - Loss of 28V DC Alarms for miscellaneous functions Aux. FW Temp & Suction Alarms - Loss of 125V DC Aux. FW Temp & Suction Alarms - Loss of 28V DC
Alarms for miscellaneous functions (Cont 1d)
Aux. FW Tank Level Alarms - Loss of 125V DC Aux. FW Tank Level Alarms - Loss of 28V DC NOTE:
The initiating signals (low steam generator level) are not bypassed during testing but are placed in the tripped mode - refer to Technical Specifications.
A description of the auxiliary annunciator system is presented in the Salem FSAR Response to Question 7.7.
SALEM GENERATING STATION UNIT NO. 1 RESPONSE TO NRC/AFW MEETING 1/3/80 Table 2 Representative Equipment Qualification Documentation for Auxiliary Feedwater System Equipment T:ransmitter (low level input)
Logic Equipment instrument Racks Actuation Device Device Steam Gen.
Narrow Range Level Sol id State Protec-tion System Process Control &
Protection Cabinets Aux. FW Pump Motor Manuf. /Model Barton 764 (Lot 2)
Westinghouse Westinghouse/
Hagan Allis Chalmers 588US-RG-3600RPM 600HP Qualification Document Westinghouse Letter Report NS-TMA-2184 WCAP 7817, Supp. 3 and Westinghouse letter NS-CE-692 WCAP 7817, Supp. 1 and WCAP-8832 Allis Chalmers Rotor Shaft Deflections, Stress Calcu-lations, Seismic Shock 8/7/70 FSAR Ref.
Q7.30, Q7.41 Q7.18, Q7.29 Q7.18, Q7.29 Q7.18, Q7.29 Remarks Enviromlental & Seismic Seismic No environmental required-locata:I in control room area which is provided with redundant Class lE Vent Systems Seismic No environinental required-located in relay room area which is provided with redundant Class lE Vent Systems Seismic No environmental required-.
redundant Aux. FW pump (turbine) located in other area which is not subject to the same postu-1 ated adverse environment.
NOTE:
The seismic documentation packages for the SSPS, reactor protection racks and auxiliary feedwater pump motor were reviewed by the NRC Seismic Qualification Review Team for Salem during the early part of 1979.
The Westinghouse reports are generic to a number of plants and have already been submitted to the NRC Staff.
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