TMI-15-057, Changes to Emergency Response Data System (ERDS)
| ML15205A011 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 07/22/2015 |
| From: | Haaf T Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| TMI-15-057 EP-AA-123-F-01, Rev. B | |
| Download: ML15205A011 (7) | |
Text
~Exelon Generation, Three Mile Island Unit 1 Route 441 South, P.O. Box 480 Middletown, PA 17057 Telephone 717-948-8000 July 22, 2015 TM 1-15-O57 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555 Three Mile Island Nuclear Station, Unit 1 Renewed Facility Operating License No. DPR-50 NRC Docket No. 50-289
Subject:
Changes to Emergency Response Data System (ERDS)
In accordance with 10 CFR 50 Appendix E, Section VI.3.a, Exelon Generation Company, LLC (Exelon) at the Three Mile Island Nuclear Station, Unit 1 (TMI) is submitting in the attached enclosure, software changes that affect the transmitted data points identified in the Emergency Response Data System (ERDS) Data Point Library to the NRC. The changes were put into effect on June 23, 2015. The attached satisfies the requirement to provide the changes within 30 days after the changes were completed.
There are no regulatory commitments contained in this request.
Should you have any questions concerning this submittal, please contact Steve Cafrelli at (717) 948-2053.
Respectfully, Thomas P. Haaf Site Vice President (Acting), Three Mile Island Unit 1 Exelon Generation Co., LLC Enclosures cc:
USNRC Regional Administrator, Region I USNRC Project Manager, TM I-i USNRC Senior Resident Inspector, TM I-1 A. J. Bomboy - Lead Analyst IT S. M. Cafrelli - Lead Analyst IT M. D. Fitzwater-Senior Regulatory Engineer M. Mcgee Jr. - Project Manager B. C. Shumaker-Site EP Manager A
eJ~i*EP-AA-1 23-F-0l
_______________Revision B
Nuclear Page 1 of 2 ERDS CONFIGURATION FILE CHANGE AUTHORIZATION STATION: Three Mile Island Are other Units Affected:
REASON FOR REQUEST:
Modify EPL File Change Request:
Station and Unit Configuration:
Change Communication Setup:
List previous values(s): Point ID List new value(s): New Point ID PLANT CONDITIONS:
Date ___Time:
Applicable Unit(s):
1_
[-IYes ]x'No Identify: ________________
[*Add r-I Delete [~] Change
[JYes LIINo I*Yes IZINo
)C4032 A0532 Normal: _________Emergency:
INITIATED BY*.
Name: Steven Cafrelli'~itle: Lead Analyst Organization: IT Date: 11/05/2014 AUTHORIZATION/NOTIFICATION:
Approval: []Yes LINo EP Coordinator/Manager, Brad Shumaker/L*f*-,Date:
Print/Sign
-i VERIFICATION:
Changes Completed by:
~'et T
ae H
i-
_ Print/Sign..
Change Verified by: Name:
H.LF,*bJLt
/
t i{Dept:. L' 7" Date:
,,,.)/
Print/Sign (I/-
RESPONSIBLE DEPARTMENT APPROVAL REVIEW:
Approval: ]*Yes LIINo
[_~.ql..(i/
et I T Date: "1 L*
Print/Sign Initiate ATI to track NRC Notification:[*Yes or [-N/A
/117*06'3 -/-*
Date:
7/* 7//5" Changes approved by:
ATI #Date:
- ---'JEP Cordinator/Manager Document Retention SRRS-ID - 5B.1 00
EP-AA-1 23-F-01 Revision B Page 2 of 2 ATI #
Comments:
With installation of new Plant Process Computer in June 2015, point 04032 has been replaced by A0532 providingq the same information as 04032. C4032 is deleted in the new system due to the calculation only multiplyingq the value of A0532 by 1.0. Calculation is no longqer needed.
ExeJ*EP-AA-1 23-F-02
_______________Revision A
Nudear Page 1 of 1 ERDS DATA POINT LIBRARY Addition:
___________Change:
X Deletion: ________
Date:
6/23/2015 Reactor Unit:
TM 1 Data Feeder:
Main SL 1/A Point Identification:
A0532 Plant Spec Point
Description:
Rad Monitor RM-G26 Generic Cond
Description:
Steam Generator A Steam Line Rad Level Analog/Digital:
Analoq En g Units / Status: CPM Eng Units Conversion:
Exponential Conversion Minimum Instrument Range: 10.0 Maximum Instrument Range: 1.0 x 10~6 Zero Point
Reference:
N/A Reference Point Notes N/A Processed Or Sensor:
Sensor Number Of Sensors:
1 How Processed:
N/A Sensor Locations:
On Steam Dump Bypass Line outside Containment Alarm/Trip Set Points:
Hi Alarm at 700.0 CPM: Hi-2 Alarm at 3000.0 CPM Ni Detector Power Supply:
Cut-Off Power Level_________________
Ni Detector Power Supply:
Turn-On Power Level:
Instrument Failure Mode:
Temperature Compensation:_________________
For Dp Transmitters:
Level Reference Leg:
Unique System
Description:
Measures activity in main steam going to the 'A' atmospheric dump relief valve and the 'D'. 'E',
and 'F' turbine bypass steam dump to main condenser. Sensitivity is 1020 CPM/Ci/cc (considered KR-85).
Document Retention SRRS-ID - 5B.1 00
Exek n Nuclear" EP-AA-1 23-F-01 Revision B Page 1 of 2 ERDS CONFIGURATION FILE CHANGE AUTHORIZATION STATION: Three Mile Island Applicable Unit(s):
1 Are other Units Affected:
REASON FOR REQUEST:
IYes r-*INo Identify:
Modify EPL File I*Add
[LJ Delete r* Change Change Request:
Station and Unit Configuration: r'E'Yes Change Communication Setup:[*Yes List previous values(s): Point ID C4033 List new value(s): New Point ID A0533 PLANT CONDITIONS:
rx]No Date
___Time:
Normal: _________Emergency:
INITIATED BY:
/*.
Name: Steven CafrelliTitle: Lead Analyst Organization: IT Date: 11/05/2014 AUTHORIZATION/NOTIFICATION:
Approval: r'x'Yes I-INo EP Coordinator/Manager, Brad Shumaker!
Print/Sign VERIFICATION:
Date:
Changes Completed by: Name: *,**
Oe, Date: L*I ij,,-
__ Print/Sign 6-_'
Change Verified by: Name:
- u,:.,M
/---
Dept:
Date:
- ' J/o /,.
Print/Sign*
RESPONSIBLE DEPARTMENT APPROVAL REVIEW:
Approval: I*Yes I*No Yl~yr,!
- et:IT Date: 7(15)**
Print/Sign Initiate ATI to track NRC Notification:*"es or F-1N/A 137080 i'*--1 Changes approved by:
ATI #
- ordnator/Manager Date: o7///7///5 Date:______*S-Document Retention SRRS-ID - 5B.1 00
E P-AA-1 23-F-O1 Revision B Page 2 of 2 ATI #
Comments:
With installation of new Plant Process Computer in June 2015, point 04033 has been replaced by A0533 providingq the same information as 04033. C4033 is deleted in the new system due to the calculation only multiplyingq the value of A0533 by 1.0. Calculation is no longqer needed.
E~e*
IEP-AA-1 23-F-02
___________Revision A
Nuclear" Page 1 of 1 ERDS DATA POINT LIBRARY Addition:
____________Change:° X
Deletion: ________
Date:
6/23/2015 Reactor Unit:
TM1 Data Feeder:
Main SL 2/B Point Identification:
A0533 Plant Spec Point
Description:
Rad Monitor RM-G27 Generic Cond
Description:
Steam Generator B Steam Line Rad Level Analog/Digital:
Analoq Eng Units / Status: CPM Eng Units Conversion:
Exponential Conversion Minimum Instrument Range: 10.0 Maximum Instrument Range: 1.0 x 106 Zero Point
Reference:
N/A Reference Point Notes N/A Processed Or Sensor:
Sensor Number Of Sensors:
1 How Processed:
N/A Sensor Locations:
On Steam Dump Bypass Line outside Containment Alarm/Trip Set Points:
Hi Alarm at 700.0 CPM; Hi-2 Alarm at 3000.0 CPM Ni Detector Power Supply:
Cut-Off Power Level_________________
Ni Detector Power Supply:
Turn-On Power Level:
Instrument Failure Mode:
Temperature Compensation:
For Dp Transmitters:
Level Reference Leg:
Unique System
Description:
Measures activity in main steam going to the 'B' atmospheric dump relief valve and the 'A', 'B',
and 'C' turbine bypass steam dump to main condenser. Sensitivity is 1056 CPM/Ci/cc (considered KR-85*.
Document Retention SRRS-ID - 5B.100