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Category:Letter type:LR
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90-Day Report2022-02-10010 February 2022 In-Service Inspection Activities - 90-Day Report LR-N22-0007, Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs2022-01-0505 January 2022 Request for Exemption from Specific Requirements of 10 CFR Part 26, Fitness for Duty Programs LR-N21-0061, Annual Report of Specific Activity Analysis - TS 6.9.1.5c2021-12-0909 December 2021 Annual Report of Specific Activity Analysis - TS 6.9.1.5c LR-N21-0083, Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion2021-11-24024 November 2021 Loss of Coolant Accident Peak Cladding Temperature Margin Tracking - Annual Report 2021 & 30 Day Report for Salem Unit 2 Upflow Conversion LR-N21-0078, Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS2021-11-18018 November 2021 Hope and Creek Generating Station, Supplement to License Amendment Request to Revise Technical Specifications (TS) to Delete Definitions Found in 10 CFR Part 20 and Delete Figures of the Site and Surrounding Areas from TS LR-N21-0066, Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations2021-11-10010 November 2021 Submittal of Relief Request Associated with the Fourth Inservice Inspection (ISI) Interval Limited Examinations 2023-09-08
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PSEG Nuclear LLC P.O. Box 236, Hancocks Bridge, New Jersey 08038-0236 SEP 1 6 2002 o PSEG NuclearLLC LR-N02-03113 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 UPDATE OF EMERGENCY RESPONSE DATA SYSTEM (ERDS)
DATA POINT LIBRARY SALEM GENERATING STATION UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Ladies and Gentlemen:
In accordance with 10CFR50 Appendix E Section VI.3.a, PSEG Nuclear is notifying the NRC of changes to the Salem Units I and 2 ERDS Data Point Libraries (DPLs). The updates to the DPLs consist of changes to the data point identification numbers as a result of recent plant modifications to Safety Parameter Display System (SPDS). The old data point designation is provided in the first column and corresponding new data point designation is provided in the second column.
The following ERDS data points are affected for Salem Unit 1.
Old Data Point Desiqnation New Data Point Designation UlNM0031FA U1 NM0031 FAS UINM0035BB UINM0035BBS U1ASUBCOOLMR UISBCLMRGNA U1XA8496S A9800 U1XA8499S A9803 U1XA8497S A9801 U1XA8498S A9802 UlXA8500S A9804 UlXA8501S A9805 4C2Q'&2 95-2168 REV. 7/99
Document Control Desk 2 SEP 1 6 2002 LR-N02-0313 The following ERDS data points are affected for Salem Unit 2.
Old Data Point Desianation New Data Point Desiqnation U2NMO031 FA U2NMOO31 FAS U2NMOO35BB U2NMOO35BBS U2TC-HOTTE U2TC-HOTTEST U2ASUBCOOLMR U2SBCLMRGNA U2AVG-CNT U2AVG-CNT-T U2XA8496S A9800 U2XA8499S A9803 U2XA8497S A9801 U2XA8498S A9802 U2XA8500S A9804 U2XA8501S A9805 Unit 2 data point U2LT0961S is being revised to correct a typographical error in the description.
In addition to the update to the ERDS data points, an update is being provided for the contact information, selection of data feeder information, and data feeder information previously submitted to the NRC due to the modification of the SPDS system.
If you have any questions concerning this submittal, please contact Brian Thomas at 856-339-2022.
Sincerely, G. Salamon Nuclear Safety and Licensing Manager
Document Control Desk 3 SEP 1 6 2002 LR-N02-0313 C Mr. Hubert J. Miller Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 U. S. Nuclear Regulatory Commission Attn: Mr. R. Fretz, Licensing Project Manager - Salem Mail Stop 08B1 Washington, DC 20555 USNRC Resident Inspector (X24)
Salem Generating Station Mr. K. Tosch, Manager IV Bureau of Nuclear Engineering P.O. Box 415 Trenton, NJ 08625 Mr. David Hake Delaware Emergency Management Agency (DEMA) 165 Brick Store Landing Rd.
Smyrna, DE 19977
Salem Unit 1 ERDS Data Point Updates LR-N02-0313
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Salem Unit 1 & 2 ERDS Contacts, Selection of Data Feeders and Data Feeder Information Updates LR-N02-0313
SALEM UNITS I & 2 I. Contacts NOTE: Please provide name, title, mailing address, and phone number.
A. Survey Coordinator (i.e. contact for later clarification of questionnaire answers):
Jack Southers Senior Engineer PSEG Nuclear MC N25 PO Box 236 Hancock's Bridge, NJ 08038 856-339-5630 B. Computer Hardware Specialist(s):
Jack Southers Senior Engineer PSEG Nuclear MC N25 PO Box 236 Hancock's Bridge, NJ 08038 856-339-5630 C. Systems Software Specialist(s):
Jack Southers Senior Engineer PSEG Nuclear.
MC N25 PO Box 236 Hancock's Bridge, NJ 08038 856-339-5630 D. Application-level Software Specialist(s):
Jack Southers Senior Engineer PSEG Nuclear MC N25 PO Box 236 Hancock's Bridge, NJ 08038 856-339-5630 E. Telephone Systems Specialist(s):
Pat O'Connell Project Manager - Information Technologies PSEG Nuclear MC N41 PO Box 236 Hancock's Bridge, NJ 08038 856-339-1225
SELECTION OF DATA FEEDERS A. How many data feeders are there (six maximum)
The Salem Safety Parameter Display System (SPDS) is the only data feeder.
Currently, the SPDS system feeds a separate ERDS Personal Computer. The new system combines both the SPDS and ERDS functionality in one system.
B. Identify the selected data feeders and provide the following for each:
(1) a short description of data points it will provide and (2) the rationale for selecting it if another system can also provide its categories of data points.
The data feeder will provide all categories of data points previously submitted.
The Salem Safety Parameter Display System (SPDS) is designed for providing information on accordance with NUREG-0737.
C. Which data feeder is the site time determining feeder? This should be the feeder which is providing the majority of the data points.
The Salem Safety Parameter Display System (SPDS) is the site time determining feeder.
DATA FEEDER INFORMATION
- 1. Identification of the Data Feeder
- a. What is the name of local parlance given to this data feeder (e.g.
Emergency Response Information System)? Please give both the acronym and the words forming it.
Safety Parameter Display System SPDS
- b. Is this the site time determining feeder?
Yes.
- c. How often will this feeder transmit an update set to the ERDS (in seconds)
The feeder is configured to transmit at the recommended 15-second frequency per NUREG-1394.
- 2. Hardware/Software Environment
- a. Identify the manufacturer and model number of the data feeder hardware.
The manufacturer of the computer is COMPAQ computer corporation.
The model of the computer is ML370R.
- b. Identify the Operating System The Operating System is Windows 2000, Service Pack 2.
- c. What method of timekeeping is implemented on this feeder system (Daylight Savings Time, Standard, Greenwich)?
Daylight Savings Time is implemented on the feeder system.
- d. In what time zone is this feeder located?
Public Service Electric & Gas Salem Nuclear Generating Station is located in Eastern Standard Time.
- 3. Data Communication Details
- a. Can this data feeder provide asynchronous serial data communication (RS 232C) with full modem control?
Yes.
- b. Will this feeder transmit in ASCII or EBCDIC?
ASCII
- c. Can this feeder transmit at a serial baud rate of 2400 bps? If not, at what baud rate can it transmit?
The feeder can transmit at 2400 baud.
- d. Does the operating system support XON/XOFF flow control?
Yes.
- 1. Are there any problems forseen with the NRC using XON/XOFF to control the transmission of data?
No problems are forseen. The new ERDS transmission will be fully tested per NRC-312.
- e. If it is not feasible to reconfigure a serial port for the ERDS linkup (i.e.,
change the baud rate, parity, etc.), please explain why.
Not applicable. Serial port will be configured per NUREG-1394 guidelines.
- f. Do any ports currently exist for the ERDS linkup?
New system designed for RS-232C communication ports to the NRC.
- 1. If not, is it possible to add additional ports?
Not applicable.
- 2. If yes, will the port be used solely by the ERDS or shared with other non-emergency-time users. Give details.
The serial ports will be dedicated for ERDS use. There will be no sharing of serial ports.
- 4. Data Feeder Physical Environment and Management
- a. Where is the data feeder located in terms of the TSC, EOF, and control room?
The data feeder is located in the back of the TSC. The data feeder is within the TSC envelope.
- b. Is the data feeder protected from loss of supply of electricity?
Yes. The data feeder is protected with a dedicated Uninterruptible Power Supply (UPS).
- c. Is there a human operator for this data feeder?
No. The SPDS system is intended to operate without human intervention.
An ERDS transmission can be initiated at any SPDS terminal.