ML18302A116
| ML18302A116 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/12/2018 |
| From: | DTE Electric Company, Detroit Edison |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML18302A116 (11) | |
Text
DETROIT EDISON - FERMI 2 AUTOMATED RECORD MANAGEMENT DISTRIBUTION CONTROL LIST 10/12/18 To: 00935
- US NRC PAGE 1 DOCUMENT CNTRL DESK WASHINGTON, DC 20555 Media: 8 1/2 X 11 Number Cnt Issue DTC Doc. Serial Number Page Rev Copies Lvl Date Sec Status TMTRM TRM VOL I 116 1 IR 10/12/18 AFC Please destroy or mark all revised, superseded, or cancelled documents as such. CONTROLLED stamps must be voided by lining through and initialing.
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Detroit Edison EF2, C/0 Info Mgmt 140 NOC, 6400 North Dixie Highway, Newport MI 48166. (734) 586-4338 OR (734) 586-4061 for questions or concerns.
Ref: u33920
LICENSING DOCUMENT TRANSMITTAL FERMl2TECHNICALREQUIREMENTSMANUAL-VOLI
.. -**-- Revision 116 dated 10/12/2018 Immediately, upon receipt of the item(s) below, please insert and/or remove the pages indicated.
Destroy the removed pages. Be sure that Revision 115 has been inserted prior to inserting these pages.
SECTION REMOVE and DESTROY INSERT In Front of TRM Manual Title Page Rev 115 10/11/2018 Title Page Rev 116 10/12/2018 Immediately following List of Effective Pages List of Effective Pages Title Page LEP-1 through LEP-4 Rev 115 LEP-1 through LEP-4 Rev 116 10/12/2018 10/11/2018 3.3 Instrumentation TRM 3.3-2 Rev 106 03/14 TRM 3.3-2 Rev 116 10/18
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TRM 3 .3-21 Rev 59 11/02 TRM 3.3-21 Rev 116 10/18 3.6 Containment Systems TRM 3.6-22 Rev 31 10/99 TRM3.6-22Rev 116 10/18 B3.3 Instrumentation WM B3.3.6-1 Rev 31 10/99 TRMB3.3.6-1 Rev 116 10/18
- END
Fermi 2 Technical Requirements
, Manual Volume I DTE Electric
- DTC: TMTRM Date 10/12/2018 I File: 1754 ARMS -INFORMATION DSN: TRM VOL I Recipient Cf~S I Rev: 116
FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOL I
-'<*.**::*.* LIST OF EFFECTIVE PAGES Page TRM i TRM ii Revision Revision Revision 106 107 Page TRM TRM 3.3-31 3.3-32 Revision Revision Revision 31 3i TRM iii Revision 105 TRM 3.3-33 Revision 31 TRM iv Revision 106 TRM 3.3-34 Revision 31 TRM V Revision 107 TRM 3.3-34a Revision 106 TRM vi Revision 31 TRM 3.3-35 Revision 60 TRM 1.0-a Revision 31 TRM 3.3-36 Revision 104 TRM 1.0-1 , Revision 31 TRM 3.3-37 Revision 72 TRM 2.0-1 Revision 31 TRM 3.3-38 Revision 31 TRM 3.0-a Revision 31 TRM 3.3-39 Revision 31 TRM 3.0-1 Revision 63 TRM 3.3-40 Revision 56 TRM 3.0-2 Revision 72 TRM 3.3-41 Revision 56 TRM 3.0-3 Revision 54 TRM 3.3-42 Revision 45 TRM 3.0-4 Rev*ision 72 TRM 3.3-43 Revision 62 TRM 3.1-a Revision 31 TRM 3.3-44 Revision 72 TRM 3.1-i Revision 31 TRM 3.3-45 Revision 31 TRM 3.2-1 Revision 31 TRM 3.3-46 Revision 31 TRM 3.3-a Revision 31 TRM 3.3-47 Revision 31 TRM 3.3-b Revision 31 TRM 3.3-48 Revision 31 TRM 3.3-c Revision 106 TRM 3.3-49 Revision 31 TRM 3.3-d Revision 31 TRM 3.4-a Revision 31
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FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOL I
- *~-*- - LIST OF E;FFECTIVE PAGES
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'TRM 3.6-18 Revision 31 TRM 3.8-12 Revision 31 TRM 3.6-19 Revision 31 TRM 3.8-13 Revision 61 TRM 3.6-20 Revision 31 TRM 3.8-14 Revision 46 TRM 3.6-21 Revision 31 TRM 3.8-15 Revision 31 TRM 3.6-22 Revision 116 TRM 3.8-16 Revision 31 TRM 3.6-23 Revision 31 TRM 3.8-17 Revision 43 TRM 3.6-24 Revision 115 TRM 3.8-18 Revision 33 TRM 3.6-25 Revision 31 TRM 3.9-a Revision 31 TRM 3.6-26 Revision 31 TRM 3.9-1 Revision 31 TRM 3.6-27 Revision 31 TRM 3.9-2 Revision 65 TRM 3.6-28 Revision 31 TRM 3.9-3 Revision 80 TRM 3.6-29 Revision 31 TRM 3.9-4 Revision 88 TRM 3.6-30 Revision 31 TRM 3.9-5 Revision 31 TRM 3.6-31 Revision 31 TRM 3.10-1 Revision 31 TRM 3.6-32 Revision 70 TRM 3.11-a Revision 31 TRM 3.6-33 Revision 31 TRM 3.11-1 Revision 31 TRM 3.6-34 Revision 31 TRM 3.12-a Revision 31 TRM 3.6-35 Revision 31 TRM 3.12-1 Revision 75 TRM 3.7-a Revision 107 TRM 3.12-2 Revision 31 TRM 3.7-1 Revision 60 TRM 3.12-3 Revision 31 TRM 3.7-2 *Revision 107 TRM 3.12-4 Revision 102 TRM 3.7-3 Revision 70 TRM 3.12-5 Revision 108 TRM 3.7-4 Revision 73 TRM 3.12-6 Revision 53 TRM 3.7-5 Revision 31 TRM 3.12-7 Revision 31 TRM 3.7-6 Revision 31 TRM 3.12-8 Revision 112 TRM 3.7-7 Revision 31 TRM 3.12-9 Revision 40 TRM 3.7-8 Revision 31 TRM 3.12-10 Revision 31 TRM 3.7-9 Revision 31 TRM 3.12-11 Revision 49 TRM 3.7-10 Revision 44 TRM 3.12-12 Revision 31 TRM 3.7-11 Revision 31 TRM 3.12-13 Revision 75 TRM 3.7-12 Revision 72 TRM 3.12-14 Revision 31 TRM 3.7-13 Revision 31 TRM 3.12-15 Revision 31 TRM 3.7-14 Revision 31 TRM 3.12-16 , Revision 75 TRM 3.7-15 Revision 115 TRM 3.12-17 Revision 31 TRM 3.7-16 Revision 115 TRM 3.12.,.18. Revision 75 TRM 3.7-17 Revision 115 TRM 3.12-19 Revision 31 TRM 3.7-18 Revision 115 TRM 3.12-20 Revision 75 TRM 3.7-19 Revision 31 TRM 3.12-21 Revision 31 TRM 3.7-20 Revision 79 TRM 3.12-22 Revision 31 TRM 3.8-a Revision 31 TRM 3.12-23 Revision 31 TRM 3.8-1 Revision 31 TRM 3.12-24 Revision 31 TRM 3.8-2 Revision 31 TRM 3.12-25 Revision 31 TRM 3.8-3 Revision 96 TRM 3.12-26 Revision 75 TRM 3.8-4 Revision 113 TRM 3.12-27 Revision 31 TRM 3.8-5 Revision 31 TRM 3.12-28 Revision 31 TRM 3.8-6 Revision 50 TRM 3.12-29 Revision 78 TRM 3.8-7 Revision 114 TRM 3.12-30 Revision 31 TRM 3.8~8 Revision 50 TRM 4.0-1 Revision 31 TRM 3.8-9 Revision 50 TRM 5.0-a Revision 105 TRM 3.8-10 Revision 50 TRM 5.0-1 Revision 105 TRM 3.8-11 Revision 50 TRM 5.0-2 Revision 105 TRM Vol. I LEP-2 REV 116 10/12/2018
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- TRM Bl.0-1 TRM B2.0-1 TRM B3.0-1 TRM B3.0-2 Revision Revision 31 Revision 31 Revision 63 Revision 63 TRM B3.6.2-1 TRM B3. 6. 3-1 /
TRM B3. 6. 4-1 TRM B3.6.5-l Revision Revision Revision Revision Revision 67 87 31 31 TRM B3.0-2a Revision 72 TRM B3.6.6-1 Revision 70 TRM B3.0-2b Revision*72 TRM B3.6.7-1 Revision 31 TRM B3.0-2c Revision 72 TRM B3.6.8-l Revision 31 TRM B3.0-3 Revision 31 TRM B3.7.l-1 Revision 31 TRM B3.0-4 Revision 31 TRM B3.7.2-1 Revision 107 TRMB3.0-5 Revision 54 TRM B3.7.3-l Revision 73 TRM B3.0-6 Revision 72 TRM B3.7.4-1 Revision 31 TRM B3.0-7 Revision 72 TRM B3.7.4-2 Revision 31 TRM B3.1-l Revision 31 TRM B3.7.5-1 Revision 31 TRM B3.2-1 Revision 31 TRM B3.7.6-l Revision 31 TRM B3.3.1-l Revision 31 TRM B3.7.7-1 Revision 99 TRM B3'.3.l-2 Revision 31 TRM B3.7.8-1 Revision 31 TRM B3.3.2-l Revision 31 TRM B3.7.9-l Revision 79 TRM B3.3.2-2 Revision 31 TRM B3.8.1-1 Revision 31 TRM B3.3.3-1 Revision 67 TRM B3.8.2-l Revision 31 TRM B3.3.4-l Revision 31 TRM B3.8.3-1 Revision 96 TRM B3.3.4-2 Revision 84 TRM B3.8.4-l Revision 31 TRM B3.3.5-1 Revision 31 TRM B3.8.5-l Revision 31 TRM B3.3.5-2 Revision 31 TRM B3.8.6-l Revision 43 TRM B3.3.6-l Revision 116 TRM.B3.9.l-l Revision 31 TRM B3.3.6-2 Revision 31 TRM B3.9.2-1 Revision 65 TRM B3.3.6-3 Revision 31 TRM B3.9.3-l Revision 31 TRM B3.3.6-4 Revision 31 TRM B3.9.4-l Revision 31 TRM B3.3.6-5 Revision 76 TRM B3.10-1 Revision 31 TRM B3.3.6-6 Revision 76 TRM B3.ll.1-1 Revision 31 TRM B3.3.7-1 Revision 31 TRM B3.12.1-1 Revision 31 TRM B3.3.7-2 Revision 31 TRM B3.12.2-1 Revision 112 TRM B3.3.7-3 Revision 106 TRM B3 .12. 3-1 Revision 31 TRM B3.3.8-1 Revision 31 TRM B3.12.4-1 Revision 31 TRM B3.3.9-l Revision 31 TRM B3.12.5-1 Revision 31 TRM B3.3.10-l Revision 56 TRM B3.12.6-l Revision 31 TRM B3.3.ll-1 Revision 45 TRM B3.12.7-1 Revision 31 TRM B3.3.12-l Revision 62 TRM B3.12.8-1 Revision 31 TRM B3.3.13-l Revision 31 TRM B3.3.14-1 Revision 31 TRM B3.4.1-1 Revision 31 TRM B3.4.l-2 Revision 71 TRM B3.4.1-3 Revision 71 TRM B3.4.l-4 Revision 71 TRM B3.4.l-5 Revision 71 TRM B3.4.2-1 Revision 31 TRM B3.4.3-l Revision 31 TRM B3.4.4-l Revision 31 TRM B3.4.5-1 Revision 31 TRM B3.4.6-l Revision 31 TRM B3.4.7-1 Revision 31 TRM B3.5-l Revision 31 TRM B3.6.l-l Revision 31 TRM Vol. I LEP-3 REV 116 10/12/2018
FERMI 2 - TECHNICAL REQUIREMENTS MANUAL VOL I LIST OF EFFECTIVE PAGES
- CORE OPERATING LIMITS REPORT COLR 19, Revision 0 Page Revision Notation Page 1 0 2 0 3 0 4 0 5 0 6 0 7 O' 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 17 0
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RPS Instrumentation TR 3. 3 .1.1
- FUNCTION TABLE TR3.3.1.1-1 (Page 2 of 2)
Reactor Protection System Instrumentation TRIP SETPOINT RESPONSE TIME (seconds)
- 3. Reactor Vessel Steam Dome Pressure - High s 1093 psig < 0. 55 (c)
- 4. Reactor Vessel Water Level - Low, Level 3 > 173.4 inchesCdl < 1. 05 (c)
- 5. Main Steam Isolation Valve - Closure < 8% closed < 0.06
- 6. Deleted
- 7. Drywell Pressure - High < 1.68 1 psig NA
- 8. Scram Discharge Volume Water Level - High
- a. Level Transmitter < 592 ft. 6 inches NA
- b. Float Switch < 594 ft. 8 inches NA
- 9. Turbine Stop Valve-Closure \ < 5% closed < 0.06
- 10. Turbine Control Valve Fast Closure Initiation of fast closure < 0. 08 (el (c) The sensor and relays/logic response time need not be measured and may be assumed to *be the design response time. Prior to return to service of a new transmitter/relay or following refurbishment of a transmitter (e.g., sensor cell or variable damper components/relay), a response time test will be performed to determine an initial sensor/relay specific response time value.
(d) As referenced to instrument zero Top of Active Fuel (TAF). 1 (e) Measured* from de-energization of K37 relay, which .inputs the turbine control valve closure signal, to the RPS.
(f) Deleted (g). The method for determining the Nominal Trip Setpoints, as-found tolerances and as-left tolerances for this function are contained in,fermi 2 setpoint calculations. Setpoint calculations for this function are in accordance with the methods described in GEH Licensing Topical Reports NEDC-31336P-A, "General Electric Instrument Setpoint Methodology," September 1996 and NEDE-33633P-A, "GEH Methodology for Implementing TSTF-493 Revision 4," January 2014 .
Primary Containment Isolation Instrumentation TR 3.3.6.1 TR 3.3 TR 3.3.6.1 INSTRUMENTATION Primary Containment Isolation Instrumentation The primary containment isolation instrumentation trip setpoints are listed in Table TR3.3.6.l-l.
TABLE TR3.3.6.1-1 (Page 1 of 3)
Primary Containment Isolation Instrumentation RESPONSE TIME FUNCTION TRIP SETPOINT (seconds)
- 1. Main Steam Line Isolation
- a. Reactor Vessel Water Level - Low Low Low, ~ 31. 8 inches(fl < 1. O{bl (c)
Level 1
- b. Main Steam Line Pressure - Low > 756 psig NA
- c. Main Steam Line Flow - High s 115. 4 psid < 0 '5 (b)(c)
- d. Condenser Pressure - High s 6.85 psia NA
- e. Main Steam Tunnel Temperature - High s 200°F NA
- f. Deleted
- 2.
g.
h.
Turbine Building Area.Temperature - High Manual Initiation Primary Containment Isolation
- a. Reactor Vessel Water Level - Low, Level 3
< 200°F NA
~ 173.4 inches(fl NA NA NA
- b. Reactor Vessel Water Level - Low Low, Level 2 ~ 110.8 incheslfl NA
- c. Drywell Pressure - High s 1.68 psig NA
- d. Main Steam Line Radiation - High < 3.0 X full power NA background(eJ
- e. Manual Initiation NA NA (continued)
(b} Isolation system instrumentation response time for MSIVs Only. No diesel generator delays assumed for MSIVs.
(c} Except for Function 1 Main Steam Line Isolation Instrumentation DC Output Relays, the sensor and relays/logic response time need not be measured and may be assumed to be the design sensor response time. Prior to return to service of a new transmitter/relay or following refurbishment of a transmitter (e.g., sensor cell or variable damper components/relay), a response time test will be performed to determine an initial sensor/relay-specific response time value.
(e} A new "full power background" level is established for hydrogen water chemistry based on 100%
power operation with the established hydrogen injection rate. Actual background radiation levels may be less depending on actual power level or hydrogen injection rate.
Setpoint adjustment is not necessary for variations in power or hydrogen injection rate, including interruptions in hydrogen flow .
The*setpoint associated with this function also trips and isolates the mechanical vacuum pumps (MVPs) and trips the gland seal exhausters (GSEs).
(f) As referenced to instrument zero Top of Active Fuel (TAF).
TRM Vol. I TRM 3.3-21 REV 116 10/18
PCIVs TR 3.6.3 TABLE TR3.6.3-1 (Page 20 of 22)
- Primary Containment Isolation Valves FUNCTION MAXIMUM ISOLATION TIME (seconds)
- 4. Other Isolation Valves (continued)
- s. EECW Supply to Drywell Equipment Check Valves Division I: P4400-F282A NA Division II: P4400-F282B NA
- t. Control Rod Drive System Insert and Withdrawal Lines
The following valve identifiers are common to all HCUs and sub-components under each HCU PIS number. HCU PIS numbers are Cll03-D001 through Cll03-D185.
Cll-Fl15 NA Cll-F138 NA
- u. Control Rod Drive Scram Discharge Volume
'* Cl100-F010 NA CllOO-FOll NA Cl100-Fl80 NA Cl100-F181 NA (a) The following is a summary of the parameters which will automatically actuate the Primary Containment Isolation Valve Groups. The instrumentation associated with these parameters is de~cribed in Technical Specification LCO 3.3.6.1.
- 1. Group 1 ~ Main Steam System Reactor Vessel Low Water Level - Level 1 Main Steam Line Flow - High Main Steam Line Tunnel Temperature - High Main Steam Line Pressure - Low Condenser Pressure - High Turbine Building Area Temperature - High
- 2. Group 2 - Reactor Water Sample System Reactor Vessel Low Water Level - Level 2 Drywell Pressure - High Main Steam Line Radiation - High
- 3. Group 3 - Residual Heat Removal (RHR) System Reactor Vessel Low Water Level - Level 1 Drywell Pressure - High
- 4. Group 4 - Residual Heat Removal Shutdown Cooling and Head Spray Reactor Vessel Low Water Level - Level 3 Reactor Vessel Pressure - High, Shutdown Cooling Interlock
Primary Containment Isolation Instrumentation TR B3.3.6.l TR B3.3 INSTRUMENTATION TR B3.3.6.1 Primary Containment Isolation Instrumentation BASES This specification ensures the effectiveness of the instrumentation used to mitigate the consequences of accidents by prescribing the OPERABILITY trip setpoints and respons'e times associated with the Technical Specifications instrumentation for isolation _of the reactor systems.
Except for the MSIVs, the safety analysis does not address individual sensor response times or the response time of the logic systems to which the sensors are connected. For D.C. operated valves, a 3 second delay is assUT(led before the valve starts to move. For A.C. operated valves, it is assumed that the A.C.
power supply is lost and is restored by startup of the emergency diesel generators. In this event, a time of 13 seconds is assumed before the valve starts to move. In addition to the pipe break, the failure of the D.C. operated valve is assumed; thus the signal delay (sensor response) is concurrent with the 10 second diesel startup. The safety analysis considers an allowable inventory loss in each case which in turn determines the valve speed in conjunction with the 10 second delay. It follows that checking the valve speeds and the 10 second time for emergency power establishment will establish the response time for the isolation functions. However, to enhance overall system retiability and to monitor instrument chan*nel response time trends, the isolation actuation instrumentation response time shall be measured.and recorded as a part of the ISOLATION SYSTEM RESPONSE TIME .
Operation with a trip set less conservative than its Trip Setpoint but within its specified Allowable Value is acceptable on the basis that the difference between each Trip Setpoint and the Allowable Value is equal to or less than the drift allowance assumed for each trip in the safety analyses.
For Table TR3.3.6.l-1 Function 2.d, a new "full power background" level is established for hydrogen water chemistry based upon 100% power operation with the established hydrogen injection rate. Actual background radiation levels may be less depending on actual power or hydrogen injection rate. Setpoint adjustment is not necessary for variations in power or hydrogen injection rate, including interruptions in hydrogen flow .