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Category:TECHNICAL SPECIFICATIONS & TEST REPORTS
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ML20211B9991999-08-0606 August 1999 Proposed Its,Rev 13 ML20210N0231999-08-0404 August 1999 Rev 12 to 980403 ITS Submittal,Providing Update to Submittal for ITS Sction 3.3,including Changes Associated with NRC Review of Rev 6 to ITS Submittal ML20210J1641999-07-30030 July 1999 Draft Proposed Tech Spec Pages Re Amend to License NPF-43 to Include Provisions for Enabling Oscillation Power Range Monitor (OPRM) Upscale Function in Average Power Range Monitor (APRM) ML20216D6091999-07-26026 July 1999 Rev 11 to ITS Submittal,Dtd 980403,providing Update to ITS Sections 3.5,3.6 & 3.8 ML20209H0331999-07-13013 July 1999 Rev 10 to ITS Submittal,Dtd 980403,providing Update to ITS Submittal for ITS Section 3.4,RCS ML20209D4001999-07-0707 July 1999 Rev 9 to Fermi 2 ITS Submittal Dtd 980403,providing Update for Sections 3.0,4.0 & 5.0 ML20196K1681999-07-0101 July 1999 Rev 8 to ITS Submittal Dtd 980403,providing Update to ITS Submittal for ITS Section 3.7 ML20210A3031999-06-30030 June 1999 Rev 14 to 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[Table view] Category:TEST REPORT
MONTHYEARML20216G5151998-02-28028 February 1998 Non-proprietary Version of NEDC-32788, Safety Review for Enrico Fermi Energy Center Unit 2 Safety/Relief Valve Setpoint Tolerance Relaxation Analyses ML20197J1901993-03-31031 March 1993 Power Uprate Startup Test Rept for Nov 1992-Mar 1993 ML20127P1461993-01-0808 January 1993 Third Refueling Outage Final Rept for Reactor Containment Bldg Integrated Leak Rate Test NRC-90-0022, Final Rept for Reactor Containment Bldg Integrated Leak Rate Test. W/900221 Ltr1990-01-31031 January 1990 Final Rept for Reactor Containment Bldg Integrated Leak Rate Test. W/900221 Ltr NRC-88-0212, Suppl 9 to Interim Startup Test Rept1988-09-10010 September 1988 Suppl 9 to Interim Startup Test Rept ML20151K0271988-07-25025 July 1988 Confirmation Test Rept for IE Bulletin 85-003 NRC-88-0038, Suppl 7 to Interim Startup Test Rept1988-03-10010 March 1988 Suppl 7 to Interim Startup Test Rept ML20147D6841987-12-23023 December 1987 Rev 2 to Chemical & Physical Testing of Fasteners for Fermi 2 ML20147D6741987-12-23023 December 1987 Rev 2 to Chemical & Physical Testing of Fasteners for Fermi 2 ML20147D6661987-12-23023 December 1987 Rev 2 to Chemical & Physical Testing of Fasteners for Fermi 2 ML20147D6981987-12-21021 December 1987 Rev 1 to Chemical & Physical Testing of Fasteners for Fermi 2 NRC-87-0229, Suppl 6 to Fermi 2 Nuclear Power Plant Interim Startup Test Rept1987-12-0707 December 1987 Suppl 6 to Fermi 2 Nuclear Power Plant Interim Startup Test Rept NRC-87-0155, Suppl 5 to Interim Startup Test Rept1987-09-19019 September 1987 Suppl 5 to Interim Startup Test Rept ML20238E9371987-08-31031 August 1987 Rev 0 to Vols 1 & 2 to DET-22-103, Final Test Rept, In-Plant Safety Relief Valve Discharge Test,Enrico Fermi Atomic Plant,Unit 2 ML20235F5761987-08-31031 August 1987 Max Credible Fault Tests CM249-Q2 Carrier Modulator for Fermi 2 Spds. Fault Applied to Output of CM249-Q2 Does Not Cause Degradation of Isolator Input Signal Beyond Acceptable Level ML20237G3621987-08-0606 August 1987 Leakage Reduction Program Summary Rept for Process Sampling Leakage Monitoring Sys (P33-00) ML20237G3821987-08-0606 August 1987 Leakage Reduction Program Summary Rept for RWCU Sys (G33-00) ML20237G3991987-08-0606 August 1987 Leakage Reduction Program Summary Rept for Post-Accident Sampling Sys (P3400) NRC-87-0084, Suppl 4 to Fermi 2 Nuclear Power Plant,Interim Startup Test Rept1987-06-10010 June 1987 Suppl 4 to Fermi 2 Nuclear Power Plant,Interim Startup Test Rept ML20214J3811987-03-12012 March 1987 Leakage Reduction Program Summary Rept for HPCI Sys (E41-00) ML20214J4151987-03-12012 March 1987 Leakage Reduction Program Summary Rept for Standby Gas Filter Sys (T46-00) ML20214J3991987-03-12012 March 1987 Leakage Reduction Program Summary Rept for RCIC Sys (E51-00) ML20204H0071987-03-10010 March 1987 Suppl 3 to Fermi 2 Nuclear Power Plant Interim Startup Test Rept ML20210A7691987-02-0303 February 1987 Leakage Reduction Program Summary Rept for Control Room Drive Sys-(C1100),Fermi Unit 2 ML20211D3601986-10-16016 October 1986 Main Steam Bypass Sys Testing Program Rept ML20197C2531986-10-10010 October 1986 Leakage Reduction Program Summary Rept for RHR Sys - (E1100) ML20199E8631986-06-13013 June 1986 Submits Suppl 1 to 860312 Startup Rept,Per Tech Spec 6.9.1.3.No Test Results Available Due to 851031 Plant Shutdown.Supplemental Rept Will Be Submitted by 860920 ML20203A0281986-03-20020 March 1986 Leakage Reduction Program Summary Rept for Core Spray Sys - (E2100) ML20203A0661986-03-20020 March 1986 Leak Reduction Program Summary Rept for Primary Containment Monitoring Sys - (T50-00) ML20210D9091986-03-18018 March 1986 Rev to Description of Diesel Generator Bearing Reliability Demonstration Test Program ML20140D4161986-03-12012 March 1986 Interim Startup Test Rept ML20215C2601985-07-17017 July 1985 Radiation Measurements - Complete Survey ML20107E1941984-11-30030 November 1984 Reactor Containment Bldg Integrated Leak Rate Test, Preoperational Test Results,Nov 1984 ML20065F9751982-07-0808 July 1982 Inservice Testing Program ML20009B2421981-06-10010 June 1981 Revised Slope Stability Analysis of Shore Barrier,Enrico Fermi Atomic Power Plant,Unit 2,810610. ML20010E6651979-12-13013 December 1979 Test Rept: Cofrentes H22-P017B-H22-P018-H22-P005. ML20010E6641979-12-11011 December 1979 Test Rept: Cofrentes H13-P618. 1998-02-28
[Table view] |
Text
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LEAKAGE REDUCTION PROGRAM
SUMMARY
REPORT FOR RESIDUAL HEAT REMOVAL (RHR) SYSTEM - (E1100)
DETROIT EDISON COMPANY FERMI-2 POWER PLANT REPORT NO.
E1100-86-01 4
1 9
f
~ISI P'fograms M1pervisor Approved By:
/4//e/P(,
Plarit Manager f
8611060018 861103 PDR ADOCK 0500 1
P
..2
LEAKAGE REDUCTIOI9 PROGRAM REPORT FOR RESIDUAL HEAT REMOVAL SYSTEM - (E1100)
INTRODUCTION: Both the Fermi-2 Technical Specifications, paragraph 6.8.4.a.2, and the Fermi-2 FSAR, Section H.III.D.l.1, require that leakage from systems outside primary containment that could or would contain highly radioactive fluids, be reduced and maintained to as-low-as-practical levels.
To demonstrate the leak tight integrity of the Residual Heat Removal System, a system leakage test is conducted once per reactor refueling (approximately once every 18 months).
This report is for the initial leakage test.
REFERENCES:
- 1) Dwg. No. 6M721-5706-1 " Residual Heat Removal (RHR)
Division II - Functional Operating Sketch".
- 2) Dwg. No. 6M721-5712-1 " Fuel Pool Cooling and Cleanup System - Functional Operating Sketch".
- 3) Dwg. No. 6M721-5739-2 " Hydrogen Recombiner System -
Functional Operating Sketch".
- 4) Dwg. No. 6M721-5725 " Post Accident Sampling System -
Functional Operating Sketch".
- 5) Dwg. No. 6M721-5706-2 " Residual Heat Removal (RHR)
Division I - Functional Operating Sketch".
- 6) Procedure No. 43.204.01, " Residual Heat Removal Division I Leakage Monitoring Test" (A copy of this procedure is on file at the plant).
- 7) Procedure No. 43.204.02, " Residual Heat Removal Division II Leakage Monitoring Test" (A copy of this procedure is on file at the plant).
TEST DESCRIPTION: Division I and Division II of the Residual Heat Removal System are lined up and tested in each of the four modes of operations (LPCI testing flow mode, Torus cooling mode, Torus spray mode and Shutdown cooling mode).
During ecch mode of operation an inspection for leakage is performed while the system is at normal operating pressure.
TEST
SUMMARY
a DIVISION - I Total Leakage for this system is within the acceptable limits defined for this system.
Total leakage for this system from all components within the test boundary was:
175 Drops /
Minute Total.
Page 1
LEAKAGE REDUCTION PROGRAM REPORT FOR Residual Heat Removal TEST RESULTS
SUMMARY
- DIVISION II: Ell-F025B Flange gasket was replaced and the leakage stopped. The Total leakage for the system from all components was reduced to 363 drops / min total.
After replacement of the gasket the total leakage for I
this system is within the acceptable limits defined for this I
system.
ACCEPTANCE CRITERIA: The general leakage criteria to be applied during the first fuel cycle as the basis for instituting corrective action in the form of corrective maintenance shall as stated below.
Per the EF-2 FSAR, this leakage criteria will be further evaluated at the end of the first refueling cycle to determine the long range leakage reduction program criteria.
This will allow experience gained during the initial fuel cycle to be factored into the long range criteria.
Residual Heat Removal Division I 350 drops / minute Residual Heat Removal Division II 550 drops / minute l
Page 2
LEAKAGE REDUCTION PROGRAM REPORT FOR 4
RESIDUAL HEAT REMOVAL TEST RESULTS: Residual Heat Removal Division I final leakage results from procedure: 43.204.01.
Procedure 43.204.01 (Completed 08-16-85)
Examination Point /
Location Leakage Detected Description Yes No RHR Pump (s) Suction Piping from Suppression Pool. ISO.
No. M-3154-1.
Ell-F004A EL 542' X
C-15 Ell-F004C EL 542' X
C-13 Ell-F030A EL 544' X
C-15 RHR Pump (s) Suction Piping from RPV. ISO. No. M-3152-1 Ell-F006A EL 544 X
C-17 Ell-F006C EL 544 X
RHR Pump (s) Suction Piping X
ISO. No. M-3154-1 and M-3180-1 RHR Pump (s) Seals, Leak-off)
X and Drains. ISO. No. M-2734-1 RHR Pump (s) Discharge and Min.
Flow Piping. ISO. No. M-3157-1, M-3178-1 and M-3180-1.
Ell-F031A EL 547 X
C-15 Ell-F072C EL 544 X
C-15 RHR Instrument Rack - H21-P018 Ell-N015A EL 570' X
C-13 RHR Hx Inlet Piping. ISO. No.
X M-3158-1.
l Page 3
LEAKAGE REDUCTIOM PROGRAM REPORT FOR Residual Heat Removal (E1100)
Division I Examination Point /
Location Leakage Detected Description Yes No RHR Hx Bypass Piping. ISO. No.
M-3146-1 and M-3158-1.
l Ell-F048A EL 590' X
C-17 RHR Hx Shell Side Integrity:
X Flanges and Drains. ISO. No.
M-4097-1.
RHR Hx Outlet Piping. ISO.
No. M-3146-1 and M-4011-1.
Ell-F003A EL 617' X
C-17 Ell-F084A EL 615' X
C-17 Ell-F085A EL 615' X
C-17 l
l RHR Discharge Piping. ISO.
X No. M-3146-1.
RHR Test / Torus Cooling and Misc. Tie Ins. ISO. No.
M-3160-1, M-3178-1, M-4011-1, M-4059-1 and M-4612-2. RHR Torus Spray Piping. ISO No.
M-3160-1.
Ell-F007A EL 578' X
C-13 Ell-F028A EL 578' X
B-13 LPCI Discharge and Cross-Tie Piping. ISO. No. M-3146-1 Keep Fill Check Valve. ISO.
No. M-4598-1.
Ell-F611A EL 570' X
A-13 LPCI Injection Piping. ISO.
X No. M-2298-1 and M-3146-1.
Drywell Spray Piping ISO. No.
X M-3159-1.
Page 4
LEAKAGE REDUCTION PROGRAM REPORT FOR Residual Heat Removal (E1100)
Division II TEST RESULTS: Residual Heat Removal Division II final leakage results from procedure: 43.204.02.
Procedure 43.204.02 (Completed 08-02-85)
Examination Point /
Location Leakage Detected Description Yes No RHR Pump (s) Suction Piping X
from Suppression Pool.
ISO. No. M-3152-1 RHR Pump (s) Suction Piping from RPV. ISO. No. M-3152-1 and M-3181-1.
Ell-F006B EL 546' X
C-9 Ell-F006D EL 546' X
5 A-ll RHR Pump (s) Suction Piping.
ISO. No. 3153-1 and M-3181-1.
Ell-F071B EL 540' X
C-10 RHR Pump (s) Seals, Leak-off(s)
X and Drains. ISO. No. M-2734-1.
I RHR Pump (s) Discharge and Min.
Flow Piping. ISO. No. M-3177-1, M-3179-1 and M-3181-1.
Ell-F034B EL 545' X
C-ll Ell-F034D EL 545' X
l C-ll Ell-F072D EL 540' X
C-10 RHR Instrument Racks - H21-P021 X
and H21-P548.
RHR Hx Inlet Piping. ISO. No.
X M-3158-1.
Page 5
LERKAGE REDUCTION PROGRAM REPORT FOR Residual Heat Removal (E1100)
Division II Examination Point /
Location Leakage Detected Description Yes No RHR Hx Bypass Piping-ISO. No.
M-3151-1 and M-3158-1.
Ell-F048B EL 606' X
C-9 RHR Hx Shell Side Integrity:
X Flanges and Drains. ISO. No.
M-4097-1.
RHR Hx Outlet Piping. ISO.
No. M-3151-1, M-3184-1 and M-40ll-1.
Ell-F078 EL 585' X
C-10 RHR Hx Discharge and Heat-up /
Flush Piping. ISO. No. M-3151-1, M-3161-1 and M-3166-1.
Ell-F025B EL 576' X
C-10 Ell-F026B EL 575 X
C-9 RHR Test / Torus Cooling and Misc.
Tie-Ins. ISO. No. M-3161-1, M-3179-1, M-4251-1 and M-4611-1.
RHR Torus Spray Piping. ISO. No.
M-3161-1.
Ell-F007B EL 578' X
B-ll Ell-F028B EL 578' X
B-ll LPCI Discharge Piping. ISO. No.
M-3151-1.
Ell-F010 (Div. I)
EL 575' X
B-12 Ell-F611B EL 565' X
B-ll Page 6
LEAKAGE REDUCTION PROGRAM REPORT FOR Residual Heat Removal (E1100)
Division II Examination Point /
Location Leakage Detected Description Yes No LPCI Injection Piping and Fuel X
Pool Tie-Ins. ISO. No. M-2299-1, M-3151-1, M-3668-1 and M-3669-1.
Shutdown Cooling Suction Piping.
ISO. No. M-2299-1 and M-3152-1.
Ell-Flll EL 545' X
B-12 Drywell Spray Piping (Boundary Terminates at Ell-016B) and Keep Fill Check Valves. ISO. No.
M-3035-1 and M-3164-1.
Ell-F204B EL 560' X
C-9 Ell-F205B EL 560' X
C-9 RPV Head Spray Piping. ISO.
X No. M-3035-1 and M-3164-1 l
l Page 7