NL-17-0810, Transmittal of Marked-Up and Clean Technical Specifications Pages for Section 5.5.15 for HNP Implementation of TSTF-500, DC Electrical Rewrite

From kanterella
(Redirected from ML17131A043)
Jump to navigation Jump to search

Transmittal of Marked-Up and Clean Technical Specifications Pages for Section 5.5.15 for HNP Implementation of TSTF-500, DC Electrical Rewrite
ML17131A043
Person / Time
Site: Hatch  
Issue date: 05/11/2017
From: Hutto J
Southern Nuclear Operating Co
To:
Document Control Desk, Office of Nuclear Reactor Regulation
References
NL-17-0810
Download: ML17131A043 (34)
v • d • e


Text

J. J. Hutto

~ Southern Nuclear Regulatory Affairs Director 40 lm emess Center Parkway Post Oflice Box 1295 Bim1ingham. AI. 35242 May 11, 2017 Docket Nos.: 50-321 50-366 U.S. Nuclear Regulatory Commission A TIN: Document Control Desk Washington, D. C. 20555-0001 Edwin I. Hatch Nuclear Plant 205 992 5872 tel 205 992 760 I fax jjhutto@southemco.com NL-17-0810 Transmission of Marked-Up and Clean Technical Specifications Pages for Section 5.5.15 for HNP Implementation of TSTF-500, "DC Electrical Rewrite" Ladies and Gentlemen:

By letter dated August 11, 2015, the Southern Nuclear Operating Company (SNC) submitted a license amendment request (LAR) to revise the Technical Specifications (TS) to adopt TSTF-500, "Direct Current (DC) Electrical Re-write", for the Edwin I. Hatch Nuclear Plant Units 1 and 2. Several requests for additional information (RAI) and their subsequent responses have since been docketed between the Nuclear Regulatory Commission (NRC) and SNC.

On April 4, 2017, SNC provided to NRC updated TS pages for TSTF-500, marked-up on the current latest TS pages. The intent was to provide all the marked-up and clean TS pages associated with TSTF-500. However, the pages for Section 5.5.15, the new proposed "Battery Monitoring and Maintenance Program", were inadvertently omitted.

Consequently, this letter provides the marked-up and clean pages for Section 5.5.15.

Additionally, the TS Table of Contents (TOC) for Section 5.5 is also provided, since some of the page numbers changed as a result of the addition of Section 5.5.15. For continuity, TOC pages iii and iv, for Unit 1 and Unit 2 respectively, are also provided. Therefore, the TOG pages included in this letter supersede the TOG pages sent in the April4, 2017, letter.

Because their page numbers changed as a result of the addition of Section 5.5.15, the clean pages making up the remainder of Section 5.5, following Section 5.5.15, are also provided. There were no substantive changes made to these sections; only their page numbers changed.

The marked-up and clean pages for LCO 3.8.4, 3.8.5, and 3.8.6 supplied in the April 4 letter remain valid.

/

U.S. Nuclear Regulatory Commission NL-17-0810 Page 2 This letter contains no new NRC commitments. If you have any questions, please contact Ken McElroy at 205.992.7369.

Mr. J.J. Hutto states he is Regulatory Affairs Director of Southern Nuclear Operating Company, is authorized to execute this oath on behalf of Southern Nuclear Operating Company and, to the best of his knowledge and belief, the facts set forth in this letter are true.

Respectfully submitted,

~' \\;::::>

J. J. Hutto Regulatory Affairs Director JJH/OCV/

efore me this J.L day of 2'V]~

---=-+-------'='-----'----=--R--'-tv-My commission expires: /0

  • S'
  • d. 0 L7

Enclosures:

1. Marked-Up Unit 1 and Unit 2 TS Pages for Section 5.5.15
2. Clean Unit 1 and Unit 2 TS Pages for Section 5.5.15 cc: Regional Administrator, Region II NRR Project Manager-Hatch Senior Resident Inspector-Hatch Director-Environmental Protection Division RType: CHA02.004

. )

, 2017.

I \\

I I

Edwin I. Hatch Nuclear Plant Units 1 and 2 Unit 1 and Unit 2 Marked-Up TS Pages for Section 5.5.15

, Unit 1 Marked-Up TS Pages for Section 5.5.15

TABLE OF CONTENTS (continued) 3.6 3.6.1.6 3.6.1.7 3.6.1.8 3.6.2.1 3.6.2.2 3.6.2.3 3.6.2.4 3.6.2.5 3.6.3.1 3.6.3.2 3.6.4.1 3.6.4.2 3.6.4.3 3.7 3.7.1 3.7.2 3.7.3 3.7.4 3.7.5 3.7.6 3.7.7 3.7.8 3.8 3.8.1 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.8.8 3.9 3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 CONTAINMENT SYSTEMS (continued)

Low-Low Set (LLS) Valves............................................................................ 3.6-16 Reactor Building-to-Suppression Chamber Vacuum Breakers..................... 3.6-18 Suppression Chamber-to-Drywell Vacuum Breakers.................................... 3.6-20 Suppression Pool Average Temperature...................................................... 3.6-22 Suppression Pool Water Level...................................................................... 3.6-25 Residual Heat Removal (RHR) Suppression Pool Cooling........................... 3.6-26 Residual Heat Removal (RHR) Suppression Pool Spray.............................. 3.6-28 Residual heat Removal (RHR) Drywell Spray............................................... 3.6.29 Containment Atmosphere Dilution (CAD) System......................................... 3.6-31 Primary Containment Oxygen Concentration................................................ 3.6-33 Secondary Containment................................................................................ 3.6-34 Secondary Containment Isolation Valves (SCIVs)........................................ 3.6-37 Standby Gas Treatment (SGT) System........................................................ 3.6-40 PLANT SYSTEMS........................................................................................ 3. 7-1 Residual Heat Removal Service Water (RHRSW) System........................... 3.7-1 Plant Service Water (PSW) System and Ultimate Heat Sink (UHS)............. 3.7-3 Diesel Generator (DG) 1B Standby Service Water (SSW) System............... 3.7-6 Main Control Room Environmental Control (MCREC) System..................... 3.7-8 Control Room Air Conditioning (AC) System................................................ 3.7-12 Main Condenser Offgas................................................................................ 3. 7-16 Main Turbine Bypass System........................................................................ 3.7-18 Spent Fuel Storage Pool Water Level........................................................... 3.7-19 ELECTRICAL POWER SYSTEMS............................................................... 3.8-1 AC Sources-Operating................................................................................ 3.8-1 AC Sources - Shutdown................................................................................ 3.8-20 Diesel Fuel Oil and Transfer, Lube Oil, and Starting Air............................... 3.8-23 DC Sources - Operating................................................................................ 3.8-26 DC Sources-Shutdown................................................................................ 3.8-~

31 B~tt~ry <?ell Parameters........ :....................................................................... 3.8 40 D1stnbut1on Systems-Operating................................................................... 3.8 Distribution Systems-Shutdown.................................................................. 3.8~

REFUELING OPERATIONS......................................................................... 3.9-1 43 Refueling Equipment Interlocks..................................................................... 3.9-1 Refuel Position One-Rod-Out Interlock......................................................... 3.9-3 Control Rod Position..................................................................................... 3.9-4 Control Rod Position Indication..................................................................... 3.9-5 Control Rod OPERABILITY-Refueling........................................................ 3.9-7 (continued)

HATCH UNIT 1 iii Amendment No. ~

TABLE OF CONTENTS (continued) 3.9 3.9.6 3.9.7 3.9.8 3.10 3.10.1 3.10.2 3.10.3 3.10.4 3.10.5 3.10.6 3.10.7 3.10.8 4.0 4.1 4.2 4.3 5.0 5.1 5.2 5.3 5.4 5.5 5.6 5.7 REFUELING OPERATIONS (continued)

Reactor Pressure Vessel (RPV) Water Level................................................ 3.9-8 Residual Heat Removal (RHR) - High Water Level....................................... 3.9-9 Residual Heat Removal (RHR)- Low Water Level....................................... 3.9-11 SPECIAL OPERATIONS.............................................................................. 3.10-1 In service Leak and Hydrostatic Testing Operation........................................ 3.10-1 Reactor Mode Switch Interlock Testing......................................................... 3.10-3 Single Control Rod Withdrawal-Hot Shutdown............................................ 3.10-5 Single Control Rod Withdrawal - Cold Shutdown.......................................... 3.10-8 Single Control Rod Drive (CRD) Removal - Refueling.................................. 3.1 0-12 Multiple Control Rod Withdrawal-Refueling................................................. 3.10-14 Control Rod Testing - Operating................................................................... 3.1 0-16 SHUTDOWN MARGIN (SDM) Test-Refueling............................................ 3.10-18 DESIGN FEATURES.................................................................................... 4.0-1 Site................................................................................................................ 4.0-1 Reactor Core................................................................................................. 4.0-1 Fuel Storage.................................................................................................. 4.0-2 ADMINISTRATIVE CONTROLS................................................................... 5.0-1 Responsibility................................................................................................ 5.0-1 Organization.................................................................................................. 5.0-2 Unit Staff Qualifications................................................................................. 5.0-5 ;G Procedures.................................................................................................... 5.0-6 20 Programs and Manuals................................................................................. 5.0-7 Reporting Requirements............................................................................... 5.049 I

High Radiation Area...................................................................................... 5.0~

(continued)

HATCH UNIT 1 iv Amendment No. ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 5.5.15 Control Room Habitability Program (continued)

Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d.

Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the MCREC System, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.

e.

The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.

The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f.

The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

Battery Monitoring and Maintenance Program This Program provides controls for battery restoration and maintenance. The program shall be in accordance with IEEE Standard (STD) 450-2002. "IEEE Recommended Practice for Maintenance. Testing. and Replacement of Vented Lead-Acid Batteries for Stationary Applications." as endorsed by Regulatory Guide 1.129. Revision 2 (RG), with RG exceptions and program provisions as identified below:

a.

The program allows the following RG 1.129, Revision 2 exceptions:

1.

Battery temperature correction may be performed before or after conducting discharge tests.

2.

RG 1.129. Regulatory Position 1. Subsection 2. "References." is not applicable to this program.

3.

In lieu of RG 1.129. Regulatory Position 2. Subsection 5.2, "Inspections," the following shall be used: "Where reference is made to the pilot cell, pilot cell selection shall be based on the lowest voltage cell in the battery."

(continued)

HATCH UNIT 1 5.0-18 Amendment No. ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Battery Monitoring and Maintenance Program (continued)

4.

In Regulatory Guide 1.129. Regulatory Position 3. Subsection 5.4.1.

"State of Charge Indicator." the following statements in paragraph (d) may be omitted: "When it has been recorded that the charging current has stabilized at the charging voltage for three consecutive hourly measurements. the battery is near full charge. These measurements shall be made after the initially high charging current decreases sharply and the battery voltage rises to approach the charger output voltage."

5.

In lieu of RG 1.129. Regulatory Position 7. Subsection 7.6.

"Restoration". the following may be used: "Following the test, record the float voltage of each cell of the string

b.

The program shall include the following provisions:

1.

Actions to restore battery cells with float voltage < 2.13 V;

2.

Actions to determine whether the float voltage of the remaining battery cells is > 2.13 V when the float voltage of a battery cell has been found to be < 2.13 V:

3.

Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;

4.

Limits on average electrolyte temperature, battery connection resistance. and battery terminal voltage; and

5.

A requirement to obtain specific gravity readings of all cells at each discharge test, consistent with manufacturer recommendations.

HATCH UNIT 1 5.0-19 Amendment No. ~

, Unit 2 Marked-Up TS Pages for Section 5.5.15

TABLE OF CONTENTS 3.8 3.8.6 3.8.7 3.8.8 3.9 3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 3.9.6 3.9.7 3.9.8 3.10 3.10.1 3.10.2 3.10.3 3.1 0.4 3.10.5 3.10.6 3.10.7 3.10.8 4.0 4.1 4.2 4.3 ELECTRICAL POWER SYSTEMS (contlnuedl

~

B~tt~ry <?ell Parameters********:*****************************************************

                                    • 3.8-~ ~

D~str~but~on Systems-Operatmg................................................................... 3.8-3+.- IL--J _

D1stnbut1on Systems-Shutdown.................................................................. 3.8-4-Q~

REFUELING OPERATIONS......................................................................... 3.9-1 Refueling Equipment Interlocks..................................................................... 3.9-1 Refuel Position One-Rod-Out Interlock......................................................... 3.9-3 Control Rod Position..................................................................................... 3.9-5 Control Rod Position Indication..................................................................... 3.9-6 Control Rod OPERABILITY-Refueling........................................................ 3.9-8 Reactor Pressure Vessel (RPV) Water Level................................................ 3.9-9 Residual Heat Removal (RHR)- High Water Level....................................... 3.9-10 Residual Heat Removal (RHR)- Low Water Level....................................... 3.9-12 SPECIAL OPERATIONS.............................................................................. 3.1 0-1 lnservice Leak and Hydrostatic Testing Operation........................................ 3.10-1 Reactor Mode Switch Interlock Testing......................................................... 3.10-3 Single Control Rod Withdrawal - Hot Shutdown............................................ 3.10-5 Single Control Rod Withdrawal - Cold Shutdown.......................................... 3.10-8 Single Control Rod Drive (CRD)

Removal - Refueling................................................................................ 3.1 0-12 Multiple Control Rod Withdrawal-Refueling................................................. 3.10-14 Control Rod Testing - Operating................................................................... 3.1 0-16 SHUTDOWN MARGIN (SDM) Test-Refueling............................................ 3.10-18 DESIGN FEATURES.................................................................................... 4.0-1 Site................................................................................................................ 4.0-1 Reactor Core................................................................................................. 4.0-1 Fuel Storage.................................................................................................. 4.0-2 (continued)

HATCH UNIT2 iv Amendment No. ~

TABLE OF CONTENTS (continued) 5.0 5.1 5.2 5.3 5.4 5.5 5.6 5.7 ADMINISTRATIVE CONTROLS................................................................... 5.0-1 Responsibility................................................................................................ 5.0-1 Or~anization ***:******:********************................................................................... 5.0-2 ~

0 Umt Staff Qualifications................................................................................. 5.0-5 Procedures.................................................................................................... 5.0-6 Programs and Manuals................................................................................. 5.0-7 Reporting Requirements............................................................................... 5.0-4-9 I High Radiation Area...................................................................................... 5. 0-~

(continued)

HATCH UNIT 2 v

Amendment No. ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 5.5.15 Control Room Envelope Habitability Program (continued)

Frequencies specified in Sections C.1 and C.2.of Regulatory Guide 1.197, Revision 0.

d.

Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the MCREC System, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.

e.

The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.

The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f.

The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

Battery Monitoring and Maintenance Program This Program provides controls for battery restoration and maintenance. The program shall be in accordance with IEEE Standard (STD) 450-2002. "IEEE Recommended Practice for Maintenance. Testing. and Replacement of Vented Lead-Acid Batteries for Stationary Applications." as endorsed by Regulatory Guide 1.129. Revision 2 (RG), with RG exceptions and program provisions as identified below:

a.

The program allows the following RG 1.129. Revision 2 exceptions:

1.

Battery temperature correction may be performed before or after conducting discharge tests.

2.

RG 1.129. Regulatory Position 1. Subsection 2. "References." is not applicable to this program.

3.

In lieu of RG 1.129. Regulatory Position 2. Subsection 5.2.

"Inspections." the following shall be used: "Where reference is made to the pilot cell. pilot cell selection shall be based on the lowest voltage cell in the battery."

(continued)

HATCH UNIT 2 5.0-18 Amendment No. ~

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Battery Monitoring and Maintenance Program (continued)

4.

In Regulatory Guide 1.129, Regulatory Position 3. Subsection 5.4.1.

"State of Charge Indicator." the following statements in paragraph (d) may be omitted: "When it has been recorded that the charging current has stabilized at the charging voltage for three consecutive hourly measurements. the battery is near full charge. These measurements shall be made after the initially high charging current decreases sharply and the battery voltage rises to approach the charger output voltage."

5.

In lieu of RG 1.129. Regulatory Position 7. Subsection 7.6.

"Restoration". the following may be used: "Following the test. record the float voltage of each cell of the string."

b.

The program shall include the following provisions:

1.

Actions to restore battery cells with float voltage < 2.13 V;

2.

Actions to determine whether the float voltage of the remaining battery cells is ~ 2.13 V when the float voltage of a battery cell has been found to be < 2.13 V:

3.

Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;

4.

Limits on average electrolyte temperature. battery connection resistance. and battery terminal voltage; and

5.

A requirement to obtain specific gravity readings of all cells at each discharge test. consistent with manufacturer recommendations.

HATCH UNIT 2 5.0-19 Amendment No. ~

Edwin I. Hatch Nuclear Plant Units 1 and 2 Unit 1 and Unit 2 Clean TS Pages for Section 5.5.15

, Unit 1 Clean TS Pages for Section 5.5.15

TABLE OF CONTENTS (continued) 3.6 3.6.1.6 3.6.1.7 3.6.1.8 3.6.2.1 3.6.2.2 3.6.2.3 3.6.2.4 3.6.2.5 3.6.3.1 3.6.3.2 3.6.4.1 3.6.4.2 3.6.4.3 3.7 3.7.1 3.7.2 3.7.3 3.7.4 3.7.5 3.7.6 3.7.7 3.7.8 3.8 3.8.1 3.8.2 3.8.3 3.8.4 3.8.5 3.8.6 3.8.7 3.8.8 3.9 3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 CONTAINMENT SYSTEMS (continued)

Low-Low Set (LLS) Valves............................................................................ 3.6-16 Reactor Building-to-Suppression Chamber Vacuum Breakers..................... 3.6-18 Suppression Chamber-to-Drywell Vacuum Breakers.................................... 3.6-20 Suppression Pool Average Temperature...................................................... 3.6-22 Suppression Pool Water Level...................................................................... 3.6-25 Residual Heat Removal (RHR) Suppression Pool Cooling........................... 3.6-26 Residual Heat Removal (RHR) Suppression Pool Spray.............................. 3.6-28 Residual heat Removal (RHR) Drywell Spray............................................... 3.6.29 Containment Atmosphere Dilution (CAD) System......................................... 3.6-31 Primary Containment Oxygen Concentration................................................ 3.6-33 Secondary Containment................................................................................ 3.6-34 Secondary Containment Isolation Valves (SCIVs)........................................ 3.6-37 Standby Gas Treatment (SGT) System........................................................ 3.6-40 PLANT SYSTEMS........................................................................................ 3.7-1 Residual Heat Removal Service Water (RHRSW) System........................... 3.7-1 Plant Service Water (PSW) System and Ultimate Heat Sink (UHS)............. 3.7-3 Diesel Generator (DG) 1 B Standby Service Water (SSW) System............... 3.7-6 Main Control Room Environmental Control (MCREC) System..................... 3.7-8 Control Room Air Conditioning (AC) System................................................ 3.7-12 Main Condenser Offgas................................................................................ 3. 7-16 Main Turbine Bypass System........................................................................ 3.7-18 Spent Fuel Storage Pool Water Level........................................................... 3.7-19 ELECTRICAL POWER SYSTEMS............................................................... 3.8-1 AC Sources-Operating................................................................................ 3.8-1 AC Sources - Shutdown................................................................................ 3.8-20 Diesel Fuel Oil and Transfer, Lube Oil, and Starting Air............................... 3.8-23 DC Sources - Operating................................................................................ 3.8-26 DC Sources-Shutdown................................................................................ 3.8-31 Battery Cell Parameters................................................................................ 3.8-35 Distribution Systems-Operating................................................................... 3.8-40 Distribution Systems-Shutdown.................................................................. 3.8-43 REFUELING OPERATIONS......................................................................... 3.9-1 Refueling Equipment Interlocks..................................................................... 3.9-1 Refuel Position One-Rod-Out Interlock......................................................... 3.9-3 Control Rod Position..................................................................................... 3.9-4 Control Rod Position Indication..................................................................... 3.9-5 Control Rod OPERABILITY-Refueling........................................................ 3.9-7 (continued)

HATCH UNIT 1 iii Amendment No.

TABLE OF CONTENTS (continued) 3.9 3.9.6 3.9.7 3.9.8 3.10 3.10.1 3.10.2 3.10.3 3.10.4 3.10.5 3.10.6 3.10.7 3.10.8 4.0 4.1 4.2 4.3 5.0 5.1 5.2 5.3 5.4 5.5 5.6 5.7 REFUELING OPERATIONS (continued)

Reactor Pressure Vessel (RPV) Water Level................................................ 3.9-8 Residual Heat Removal (RHR) - High Water Level....................................... 3.9-9 Residual Heat Removal (RHR)- Low Water Level....................................... 3.9-11 SPECIAL OPERATIONS.............................................................................. 3.10-1 lnservice Leak and Hydrostatic Testing Operation........................................ 3.10-1 Reactor Mode Switch Interlock Testing......................................................... 3.10-3 Single Control Rod Withdrawal-Hot Shutdown............................................ 3.10-5 Single Control Rod Withdrawal - Cold Shutdown.......................................... 3.1 0-8 Single Control Rod Drive (CRD) Removal - Refueling.................................. 3.1 0-12 Multiple Control Rod Withdrawal-Refueling................................................. 3.10-14 Control Rod Testing - Operating................................................................... 3.1 0-16 SHUTDOWN MARGIN (SDM) Test-Refueling............................................ 3.10-18 DESIGN FEATURES.................................................................................... 4.0-1 Site................................................................................................................ 4.0-1 Reactor Core................................................................................................. 4.0-1 Fuel Storage.................................................................................................. 4.0-2 ADMINISTRATIVE CONTROLS................................................................... 5.0-1 Responsibility................................................................................................ 5.0-1 Organization.................................................................................................. 5.0-2 Unit Staff Qualifications................................................................................. 5.0-5 Procedures.................................................................................................... 5.0-6 Programs and Manuals................................................................................. 5.0-7 Reporting Requirements............................................................................... 5.0-20 High Radiation Area...................................................................................... 5.0-24 (continued)

HATCH UNIT 1 iv Amendment No.

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 5.5.15 Control Room Habitability Program (continued)

Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d.

Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the MCREC System, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.

e.

The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.

The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f.

The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

Battery Monitoring and Maintenance Program This Program provides controls for battery restoration and maintenance. The program shall be in accordance with IEEE Standard (STD) 450-2002, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," as endorsed by Regulatory Guide 1.129, Revision 2 (RG), with RG exceptions and program provisions as identified below:

a.

The program allows the following RG 1.129, Revision 2 exceptions:

1.

Battery temperature correction may be performed before or after conducting discharge tests.

2.

RG 1.129, Regulatory Position 1, Subsection 2, "References," is not applicable to this program.

3.

In lieu of RG 1.129, Regulatory Position 2, Subsection 5.2, "Inspections," the following shall be used: "Where reference is made to the pilot cell, pilot cell selection shall be based on the lowest voltage cell in the battery."

(continued)

HATCH UNIT 1 5.0-18 Amendment No.

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Battery Monitoring and Maintenance Program (continued) 4 In Regulatory Guide 1.129, Regulatory Position 3, Subsection 5.4.1, "State of Charge Indicator," the following statements in paragraph (d) may be omitted: "When it has been recorded that the charging current has stabilized at the charging voltage for three consecutive hourly measurements, the battery is near full charge. These measurements shall be made after the initially high charging current decreases sharply and the battery voltage rises to approach the charger output voltage."

5.

In lieu of RG 1.129, Regulatory Position 7, Subsection 7.6, "Restoration", the following may be used: "Following the test, record the float voltage of each cell of the string."

b.

The program shall include the following provisions:

1.

Actions to restore battery cells with float voltage < 2.13 V;

2.

Actions to determine whether the float voltage of the remaining battery cells is <!: 2.13 V when the float voltage of a battery cell has been found to be < 2.13 V;

3.

Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;

4.

Limits on average electrolyte temperature, battery connection resistance, and battery terminal voltage; and

5.

A requirement to obtain specific gravity readings of all cells at each discharge test, consistent with manufacturer recommendations.

HATCH UNIT 1 5.0-19 Amendment No.

5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements Reporting Requirements 5.6 The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Deleted.

5.6.2 Annual Radiological Environmental Operating Report

N 0 T E -------------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the (continued)

HATCH UNIT 1 5.0-20 Amendment No.

5.6 Reporting Requirements Reporting Requirements 5.6 5.6.2 Annual Radiological Environmental Operating Report (continued) format of the table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report

NOTE------------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50; Appendix I,Section IV.B.1.

5.6.4 Deleted.

5.6.5 CORE OPERATING LIMITS REPORT (COLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

HATCH UNIT 1

1)

The Average Planar Linear Heat Generation Rate for Specification 3.2.1.

2)

The Minimum Critical Power Ratio for Specification 3.2.2.

3)

The Linear Heat Generation Rate for Specification 3.2.3.

(continued) 5.0-21 Amendment No.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel," (applicable amendment specified in the COLR).

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report is required by LCO 3.3.3.1, "Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a.

RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing, as well as heatup and cooldown rates, shall be established and documented in the PTLR for the following:

i.

Limiting Conditions for Operating Section 3.4.9 "RCS Pressure and Temperature (PIT) Limits."

ii.

Surveillance Requirements Section 3.4.9, "RCS Pressure and Temperature (PIT) Limits."

b.

The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

HATCH UNIT 1

i.

BWROG-TP-11-022-A, Revision 1 (SIR-05-044, Revision 1-A),

"Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," dated June 2013.

(continued) 5.0-22 Amendment No.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Reactor Coolant System (RCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR) (continued) ii.

BWROG-TP-11-023-A, Revision 0 (0900876.40 1, Revision 0-A),

"Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations," dated May 2013.

c.

The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

HATCH UNIT 1 5.0-23 Amendment No.

5.0 ADMINISTRATIVE CONTROLS 5.7 High Radiation Area Reporting Requirements 5.7

5. 7.1 Pursuant to 10 CFR 20, paragraph 20.1601, in lieu of the requirements of 10 CFR 20.1601a, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is > 100 mrem/hr but < 1 000 mrem/hr, measured at 30 em from the radiation source or from any surface the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area.

Entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g.,

radiation protection technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates

< 1 000 mrem/hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

c.

An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility radiation protection supervision in the RWP.

5.7.2 In addition to the requirements of Specification 5.7.1, areas with radiation levels

~ 1 000 mrem/hr, measured at 30 em from the radiation source or from any surface the radiation penetrates, but less than 500 Rads in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> measured at 1 meter from the radiation source or from any surface that the radiation penetrates, shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of the Shift Supervision on duty or radiation protection supervision.

HATCH UNIT 1 5.0-24 Amendment No. I

, Unit 2 Clean TS Pages for Section 5.5.15

TABLE OF CONTENTS 3.8 3.8.6 3.8.7 3.8.8 3.9 3.9.1 3.9.2 3.9.3 3.9.4 3.9.5 3.9.6 3.9.7 3.9.8 3.10 3.10.1 3.10.2 3.10.3 3.10.4 3.10.5 3.10.6 3.10.7 3.10.8 4.0 4.1 4.2 4.3 ELECTRICAL POWER SYSTEMS (continued)

Battery Cell Parameters................................................................................ 3.8-35 Distribution Systems-Operating................................................................... 3.8-40 Distribution Systems - Shutdown.................................................................. 3.8-43 REFUELING OPERATIONS......................................................................... 3.9-1 Refueling Equipment Interlocks..................................................................... 3.9-1 Refuel Position One-Rod-Out Interlock......................................................... 3.9-3 Control Rod Position..................................................................................... 3.9-5 Control Rod Position Indication..................................................................... 3.9-6 Control Rod OPERABILITY-Refueling........................................................ 3.9-8 Reactor Pressure Vessel (RPV) Water Level................................................ 3.9-9 Residual Heat Removal (RHR)- High Water Level....................................... 3.9-10 Residual Heat Removal (RHR)- Low Water Level....................................... 3.9-12 SPECIAL OPERATIONS.............................................................................. 3.1 0-1 lnservice Leak and Hydrostatic Testing Operation........................................ 3.10-1 Reactor Mode Switch Interlock Testing......................................................... 3.10-3 Single Control Rod Withdrawal-Hot Shutdown............................................ 3.10-5 Single Control Rod Withdrawal - Cold Shutdown.......................................... 3.1 0-8 Single Control Rod Drive (CRD)

Removal - Refueling................................................................................ 3.1 0-12 Multiple Control Rod Withdrawal-Refueling................................................. 3.10-14 Control Rod Testing-Operating................................................................... 3.10-16 SHUTDOWN MARGIN (SDM) Test-Refueling............................................ 3.10-18 DESIGN FEATURES.................................................................................... 4.0-1 Site................................................................................................................ 4.0-1 Reactor Core................................................................................................. 4.0-1 Fuel Storage.................................................................................................. 4.0-2 (continued)

HATCH UNIT2 iv Amendment No.

TABLE OF CONTENTS (continued) 5.0 ADMINISTRATIVE CONTROLS................................................................... 5.0-1 5.1 Responsibility................................................................................................ 5.0-1 5.2 Organization.................................................................................................. 5.0-2 5.3 Unit Staff Qualifications................................................................................. 5.0-5 5.4 Procedures.................................................................................................... 5.0-6 5.5 Programs and Manuals................................................................................. 5.0-7 5.6 Reporting Requirements............................................................................... 5.0-20 5.7 High Radiation Area...................................................................................... 5.0-24 (continued)

HATCH UNIT 2 v

Amendment No.

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 5.5.15 Control Room Envelope Habitabilitv Program (continued)

Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d.

Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by one subsystem of the MCREC System, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.

e.

The quantitative limits on unfiltered air inleakage into the CRE. These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c.

The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air inleakage limits for hazardous chemicals must ensure that exposure of CRE occupants to these hazards will be within the assumptions in the licensing basis.

f.

The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.

Battery Monitoring and Maintenance Program This Program provides controls for battery restoration and maintenance. The program shall be in accordance with IEEE Standard (STD) 450-2002, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," as endorsed by Regulatory Guide 1.129, Revision 2 (RG), with RG exceptions and program provisions as identified below:

a.

The program allows the following RG 1.129, Revision 2 exceptions:

1.

Battery temperature correction may be performed before or after conducting discharge tests.

2.

RG 1.129, Regulatory Position 1, Subsection 2, "References," is not applicable to this program.

3.

In lieu of RG 1.129, Regulatory Position 2, Subsection 5.2, "Inspections," the following shall be used: "Where reference is made to the pilot cell, pilot cell selection shall be based on the lowest voltage cell in the battery."

(continued)

HATCH UNIT 2 5.0-18 Amendment No.

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.15 Battery Monitoring and Maintenance Program (continued)

4.

In Regulatory Guide 1.129, Regulatory Position 3, Subsection 5.4.1, "State of Charge Indicator," the following statements in paragraph (d) may be omitted: "When it has been recorded that the charging current has stabilized at the charging voltage for three consecutive hourly measurements, the battery is near full charge. These measurements shall be made after the initially high charging current decreases sharply and the battery voltage rises to approach the charger output voltage."

5.

In lieu of RG 1.129, Regulatory Position 7, Subsection 7.6, "Restoration", the following may be used: "Following the test, record the float voltage of each cell of the string."

b.

The program shall include the following provisions:

1.

Actions to restore battery cells with float voltage < 2.13 V;

2.

Actions to determine whether the float voltage of the remaining battery cells is ~ 2.13 V when the float voltage of a battery cell has been found to be< 2.13 V;

3.

Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates;

4.

Limits on average electrolyte temperature, battery connection resistance, and battery terminal voltage; and

5.

A requirement to obtain specific gravity readings of all cells at each discharge test, consistent with manufacturer recommendations.

HATCH UNIT2 5.0-19 Amendment No.

5.0 ADMINISTRATIVE CONTROLS 5.6 Reporting Requirements Reporting Requirements 5.6 The following reports shall be submitted in accordance with 10 CFR 50.4.

5.6.1 Deleted.

5.6.2 Annual Radiological Environmental Operating Report

NOTE-----------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station.

The Annual Radiological Environmental Operating Report covering the operation of the unit during the previous calendar year shall be submitted by May 15 of each year. The report shall include summaries, interpretations, and analyses of trends of the results of the Radiological Environmental Monitoring Program for the reporting period. The material provided shall be consistent with the objectives outlined in the Offsite Dose Calculation Manual (ODCM), and in 10 CFR 50, Appendix I, Sections IV.B.2, IV.B.3, and IV.C.

The Annual Radiological Environmental Operating Report shall include the results of analyses of all radiological environmental samples and of all environmental radiation measurements taken during the period pursuant to the locations specified in the table and figures in the ODCM, as well as summarized and tabulated results of these analyses and measurements in the format of the (continued)

HATCH UNIT2 5.0-20 Amendment No.

5.6 Reporting Requirements Reporting Requirements 5.6 5.6.2 Annual Radiological Environmental Operating Report (continued) table in the Radiological Assessment Branch Technical Position, Revision 1, November 1979. In the event that some individual results are not available for inclusion with the report, the report shall be submitted noting and explaining the reasons for the missing results. The missing data shall be submitted in a supplementary report as soon as possible.

5.6.3 Radioactive Effluent Release Report

NOTE------------------------------------------------------

A single submittal may be made for a multiple unit station. The submittal should combine sections common to all units at the station; however, for units with separate radwaste systems, the submittal shall specify the releases of radioactive material from each unit.

The Radioactive Effluent Release Report covering the operation of the unit shall be submitted in accordance with 10 CFR 50.36a. The report shall include a summary of the quantities of radioactive liquid and gaseous effluents and solid waste released from the unit. The material provided shall be consistent with the objectives outlined in the ODCM and the Process Control Program and in conformance with 10 CFR 50.36a and 10 CFR 50, Appendix I, Section IV.B.1.

5.6.4 Deleted.

5.6.5 CORE OPERATING LIMITS REPORT CCOLR)

a.

Core operating limits shall be established prior to each reload cycle, or prior to any remaining portion of a reload cycle, and shall be documented in the COLR for the following:

HATCH UNIT 2

1)

The Average Planar Linear Heat Generation Rate for Specification 3.2.1.

2)

The Minimum Critical Power Ratio for Specification 3.2.2.

3)

The Linear Heat Generation Rate for Specification 3.2.3.

(continued) 5.0-21 Amendment No.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.5 CORE OPERATING LIMITS REPORT (COLR) (continued)

b.

The analytical methods used to determine the core operating limits shall be those previously reviewed and approved by the NRC, specifically those described in NEDE-24011-P-A, "General Electric Standard Application for Reactor Fuel," (applicable amendment specified in the COLR).

c.

The core operating limits shall be determined such that all applicable limits (e.g., fuel thermal mechanical limits, core thermal hydraulic limits, Emergency Core Cooling Systems (ECCS) limits, nuclear limits such as SDM, transient analysis limits and accident analysis limits) of the safety analysis are met.

d.

The COLR, including any mid-cycle revisions or supplements, shall be provided upon issuance for each reload cycle to the NRC.

5.6.6 Post Accident Monitoring (PAM) Instrumentation Report When a report is required by LCO 3.3.3.1, "Post Accident Monitoring (PAM)

Instrumentation," a report shall be submitted within the following 14 days. The report shall outline the preplanned alternate method of monitoring, the cause of the inoperability, and the plans and schedule for restoring the instrumentation channels of the Function to OPERABLE status.

5.6.7 Reactor Coolant System CRCS) PRESSURE AND TEMPERATURE LIMITS REPORT (PTLR)

a.

RCS pressure and temperature limits for heatup, cooldown, low temperature operation, criticality, and hydrostatic testing, as well as heatup and cooldown rates, shall be established and documented in the PTLR for the following:

i.

Limiting Conditions for Operating Section 3.4.9 "RCS Pressure and Temperature (PT) Limits" ii.

Surveillance Requirements Section 3.4.9, "RCS Pressure and Temperature (PIT) Limits"

b.

The analytical methods used to determine the RCS pressure and temperature limits shall be those previously reviewed and approved by the NRC, specifically those described in the following documents:

HATCH UNIT 2

i.

BWROG-TP-11-022-A, Revision 1 (SIR-05-044, Revision 1-A),

"Pressure-Temperature Limits Report Methodology for Boiling Water Reactors," dated June 2013.

(continued) 5.0-22 Amendment No.

Reporting Requirements 5.6 5.6 Reporting Requirements 5.6.7 Reactor Coolant System (RCSl PRESSURE AND TEMPERATURE LIMITS REPORT CPTLR) (continued) ii.

BWROG-TP-11-023-A, Revision 0 (0900876.401, Revision 0-A),

"Linear Elastic Fracture Mechanics Evaluation of General Electric Boiling Water Reactor Water Level Instrument Nozzles for Pressure-Temperature Curve Evaluations," dated May 2013.

c.

The PTLR shall be provided to the NRC upon issuance for each reactor vessel fluence period and for any revision or supplement thereto.

HATCH UNIT 2 5.0-23 Amendment No.

5.0 ADMINISTRATIVE CONTROLS

5. 7 High Radiation Area Reporting Requirements 5.7
5. 7.1 Pursuant to 1 0 CFR 20, paragraph 20.1601, in lieu of the requirements of 10 CFR 20.1601 a, each high radiation area, as defined in 10 CFR 20, in which the intensity of radiation is > 100 mrem/hr but < 1000 mrem/hr, measured at 30 em from the radiation source or from any surface the radiation penetrates, shall be barricaded and conspicuously posted as a high radiation area.

Entrance thereto shall be controlled by requiring issuance of a Radiation Work Permit (RWP). Individuals qualified in radiation protection procedures (e.g.,

radiation protection technician) or personnel continuously escorted by such individuals may be exempt from the RWP issuance requirement during the performance of their assigned duties in high radiation areas with exposure rates

< 1000 mrem/hr, provided they are otherwise following plant radiation protection procedures for entry into such high radiation areas.

Any individual or group of individuals permitted to enter such areas shall be provided with or accompanied by one or more of the following:

a.

A radiation monitoring device that continuously indicates the radiation dose rate in the area.

b.

A radiation monitoring device that continuously integrates the radiation dose rate in the area and alarms when a preset integrated dose is received. Entry into such areas with this monitoring device may be made after the dose rate levels in the area have been established and personnel are aware of them.

c.

An individual qualified in radiation protection procedures with a radiation dose rate monitoring device, who is responsible for providing positive control over the activities within the area and shall perform periodic radiation surveillance at the frequency specified by the facility radiation protection supervision in the RWP.

5.7.2 In addition to the requirements of Specification 5.7.1, areas with radiation levels

<:: 1 000 mrem/hr, measured at 30 em from the radiation source or from any surface the radiation penetrates, but less than 500 Rads in 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> measured at 1 meter from the radiation source or from any surface that the radiation penetrates, shall be provided with locked or continuously guarded doors to prevent unauthorized entry and the keys shall be maintained under the administrative control of the Shift Supervision on duty or radiation protection supervision.

HATCH UNIT2 5.0-24 Amendment No. I

Retrieved from "https://kanterella.com/w/index.php?title=NL-17-0810,_Transmittal_of_Marked-Up_and_Clean_Technical_Specifications_Pages_for_Section_5.5.15_for_HNP_Implementation_of_TSTF-500,_DC_Electrical_Rewrite&oldid=5140455"