View source for NRC-99-0055, Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval

{{Adams
| number = ML20211B956
| issue date = 08/19/1999
| title = Forwards Rev 5 to Inservice Testing Program for Pumps & Valves for Fermi 2 Second 10-Year Interval, Per Provisions of 10CFR50.55a(f)(5)(iv).Rev Includes Four Pump Relief Requests & Ten Valve Relief Requests Requiring NRC Approval
| author name = Fessler P
| author affiliation = DETROIT EDISON CO.
| addressee name = 
| addressee affiliation = NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
| docket = 05000341
| license number = 
| contact person = 
| case reference number = CON-NRC-99-0055
| document report number = NUDOCS 9908250134
| package number = ML20211B965
| document type = CORRESPONDENCE-LETTERS, INCOMING CORRESPONDENCE
| page count = 12
| project = 
| stage = Request
}}

=Text=
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          .N Paul l'ewler I'lant Manager fermi 2 6400 North Dixie llwy, Newport, MI 48106 Tel: 731.686M26
* l                                                                     Detroit Edison l
l l           August 19,1999 l           NRC-99-0055 l
l l           U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington D C 20555-0001 l
l           

==References:==
: 1) Fermi 2 1
NRC Docket No. 50-341 NRC License No. NPF-43 i                        2) Detroit Edison's Letter to the NRC,
                             " Extension of the Fermi 2's First Ten-year Inservice Inspection Interval",
NRC-98-0082, dated April 3,1998 L                        3) NUREG-1482," Guidelines for Inservice Testing i
at Nuclear Power Plants", dated April 1995 l

==Subject:==
Submittal of the Inservice Testing Program for Pumps and Valves - Second Ten-year Interval Pursuant to 10CFR50.55a(f)(5)(iv), Detroit Edison hereby submits the revised Inservice Testing (IST) program for pumps and valves (Enclosure 3) for the second ten-year interval of the Fermi 2 plant operation. Per Reference 2. the second ten-year IST interval will stan on February 17,2000.                                              If,
                                                                                                     /'
The enclosed revision of the IST program is based on the 1989 Edition of Section XI          j of the American Society of Mechanical Engineers (ASME) Boiler and Pressure             .O Vessel Code. The 1989 Edition of the ASME Code is the latest edition currently incorporated by reference in 10CFR50.55a(b).
Detroit Edison performed a full review of the IST Program and revised it to comply with the ASME Code 1989 Edition. This revision includes four Pump Relief 9908250134 990819 PDR  ADOCK 05000341 P                    PDR A DTE Energy Company L.

USNRC NRC-99-0055 Page 2 Requests and ten Valve Relief Requests requiring NRC approval. All Relief Requests are a result of" impractical'' requirements with the exception of Pump Relief Request PRR-004; and Valve Relief Requests VRR-001, VRR-003, VRR-008, and VRR-010. Therefore, except for PRR-004, VRR-001, VRR-003, VRR-008, and VRR-010, the proposed Relief Requests will be implemented at the start of the second ten-year interval as discussed in Section 3.3.3 of Reference 3. PRR-004, VRR-001, VRR-003, VRR-008, and VRR-010 will not be implemented until approval is granted by the NRC. In order to plan for the upcoming seventh Refueling Outage (RFO7) scheduled to start on April 7,2000, NRC approval of the IST Relief Requests is requested by March 7,2000.
Enclosure I contains a list and a brief description of all IST Relief Requests. provides a listing of the Relief Requests utilized during the first ten-year interval and their disposition for the second ten-year interval. The material in  is provided for information and to aid in the review of the Relief Requests required for the second ten-year interval. Enclosure 3 is a copy of the revised IST program including the Relief Requests.
Should you have any questions or require additional information, please contact Mr. Norman K. Peterson of my staff at (734) 586-4258.
Sincerely.            -
                                                           \
jGn                     C, i
Enclosures cc:   A. J. Kugler                                                                         j A. Vegel NRC Resident Office Regional Administrator, Region III l
                                                                                           }

r-ENCLOSURE 1 TO NRC-99-0055 FERMI 2 DOCKET NO. 50-341 NRC LICENSE NO. NPF-43   1 LIST OFIST RELIEF REQUESTS 1
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1 Enclosure 1 NRC-99-0055 Page1of2 1.0      Pump Relief Requests Listing l
Relief Request        Subject                              Component Affected             )
Number PRR-001               Inlet Pressure Measurement for RIIR  RliRSW Pumps Complex Service Water Pumps          (El151C001 A El151C001B,       {
(Vertical Line Shaft Pumps)          El151C001C, El151C001D)         j DGSW (R3001C005, f
R3001C006, R3001C007,           l R3001C008)
EESW (P4500C002A, P4500C002B)
PRR-002               Core Spray Pump Testing - Pumps      Division 1 Pumps Tested in Paral;el Using Pump Curves (E2101C001 A and                l E2101C001C) Tested in Parallel, Pump Cun'e Developed Based on Both Pumps Operating Division 2 Pumps                !
(E2101C001B and                 l E2101C001D) Tested in Parallel Pump Curve Developed Based on Both Pumps Operating PRR-003               Emergency Equipment Cooling Water    P4400C001 A and (EECW) Pumps Tested Using Pump       P4400C001B Cun'es                                                               l PRR-004               RIIR Pumps Upper Motor Thrust        RIiR Pumps Upper Motor Bearing Vibration Limits             Thrust Bearing Vibration, Set Alert Level Above Code Alert l                                                             Level l
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Enclosure 1 NRC-99-0055 Page 2 of 2 2.0     Valve Relief Requests Listing
. Valve Relief Request System (s) -                        Components Number VRR-001                Systems Penetrating Both Primary   Containment Isolation Valves, Containment and Secondary          B21,E41,E51,G11,P34,P44, Containment (Containment Isolation and P50 Valves) and Secondary Containment (Bypass Leakage Valves)
VRR-002                Emergency Diesel Generator         Air Start Solenoid Valves, R30
_ VRR-003               Emergency Equipment Cooling Water  Back Flow Check Valves Disassembly / Inspection, P44 VRR-004                General Relief                     Incorporate Grouping of Check Valves for Disassembly / Inspection Based on NUREG-1482 VRR-005                Core Spray                         Keep Fill Check Valves, E21 VRR-006                Residual Heat Removal              Keep Fill Check Valves, El1 VRR-007                Systems Penetrating Primary        PC Isolation Valves, LLRT Containment                        Option B; B21, B31, Cl 1, C41,C51,El1,E21,E41,E51, G11, G33, G51, P11, P34, P44, P50,T23,T46,T48,T49,and T50 VRR-008                Nuclear Boiler                     SRV Testing Sequence, B21 VRR-009                Control Rod Drive                  SCRAM Valves, Cl1 VRR-010                Torus to Drywell Vacuum Breakers   OM-1 Testing Requirements, T23 l
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I' ENCLOSURE 2TO NRC-99-0055 FERMI 2 DOCKET NO. 50-341 NRC LICENSE NO. NPF-43 DISPOSITION OFIST FIRST INTERVAL RELIEF REQUESTS

Enclosure 2 NRC-99-0055 Page 1 of 5 i
Disposition of Relief Requests from ist 10 Year Interval to 2nd 10 Year Intenral PUMPS 1" 10 Year         2"d 10 Year            Subject Inten al Relief    Inten'al Relief Request No.        Request No.
PR-1                                      Generic Vibration Limits: Not Reg'd, vibration meets OM-6 PR-2                                     Not Reg'd, brg temp not in OM PR-3               PRR-001                RIIR Complex Suction Lift PR-6               PRR-002               CS Pump Parallel Testing and Ref Curve                     I i
PR-8                                      RIIR A/B/D Vibration, Not Reg'd, OM-6 Modified per       I PRR-004 for All RHR Pumps PR-10                                    Not Reg'd, vibration meets OM-6 PR-11              PRR-003                EECW Reference curve PR-12              PRR-004               RHR Pumps Upper Brg Vibration (Alert Level) l l
E            .      .      . . . . .

i Enclosure 2 NRC 99-0055 Page 2 of 5 VALVES 1" 10 Year         2"' 10 Year Interval          Subject Inten'ai Relief Request No. ROJ#       CSJ #     VRR#
VR-1                          CSJ-001            3'd MSIVs VR-2               ROJ-001    CSJ-002            FW Checks VR-4                          CSJ-003            EECW Valve Stroke Times (Isolate  }
CRD Pumps)
VR-5               ROJ-002    CSJ-015            EECW Containment Isol. Valves VR-6                                             Rapid Acting Valves Not Reg'd, OM-10,4.2.1.8(e)
VR-7                          CSJ-004            PlVs
  - VR             ROJ-004    CSJ-005   VRR-004 RHR/CS Inbd Checks VR-9               ROJ-005                       Excess Flow Checks i
VR-10              ROJ-006                       IIPCI Torus Suction Check Valve   i l
VR-16              ROJ-003                       PC Instrument N2 i
VR-12                                   VRR-009 CRD Scram Valves (C1103-F114,      l F126, F127) i VR-14              ROJ-007                       ADS Valves VR-15                         CSJ-006            MSIVs                             l VR-17              ROJ-019                       SRV Down comer Vacuum Brkrs VR-18                         CSJ-007            RR Pump Seal Water PC isol.
VR-20              ROJ-008                       SLC Injection PC Checks i

Enclosure 2 NRC-99-0055 Page 3 of 5 1" 10 Year         2"d to Year Interval           Subject Inten al l
Relief Request No. ROJ#       CSJ #     VRR#
VR-21                         CSJ-008             RR Pump Discharge Valves VR-23                                             Fail Safe Testing                    l Not Reg'd VR-32              ROJ-009                        EECW DW Class D Isolation Checks VR-35                         CSJ-009             PC RPS Atmos. Valves VR-36                         CSJ-010,            inbd Containment Iso. Valves CSJ-011 VR-43              ROJ-010                        CRD Charging Water Check (Cl103F115)
VR-44                                             CRD Cooling Water Check l
(Cl102F138)
Not Req'd VR-45              ROJ-011              VR.R-004 CS Min Flow Checks l
VR-46                                             Group testing PC Isol Valves Not Reg'd, OM-10,4.2.2 VR-49                                            Group testing PC Isol Valves Not Reg'd, OM-10,4.2.2 VR-48/VR-62                             VRR-003 EECW Backflow Checks (4)
VR-66                        CSJ-011              RWCU PC isol Valves,( Also from VR-36, G33-F001)
VR-51                                   VRR-002 EDG Air Start Solenoids VR-40                                   VRR-005 CS Keep Fill Checks

I Enclosure 2 NRC-99-0033 Page 4 of 5 1" 10 Year         2"d 10 Year Interval          Subject Interval Relief Request No. ROJ#      CSJ #      VRR#                  >
VR-41                                   VRR-006 RHR Keep Fill Checks VR-52                        CSJ-012             MSIVLCS PC Isol Valves VR-55              ROJ-012                       SD Cooling Inbd Thermal Relief Checks VR-57                        CSJ-013             Torus /DW Vacuum Breakers Stroke Exercising VR-58              ROJ-013                       RPV Level Backfill Checks VR-60              ROJ-14               VRR-004 CS Pump Dis Checks VR-53                                            Torus /DW Vacuum Breakers Not Reg'd VR-61                                   VRR-007 Option B VR-63              ROJ-015                       RHR Complex Min Flow Valves VR-65                        CSJ-014             EECW Div 1 Check Valve,6 in.
VR-67              ROJ-016              VRR-004 LPCI Pump Min Flow Checks (nen)              ROJ-017                       E41F035 (new)              ROJ-018                       C4100F033A/B CT-C Test (nen)                                   VRR-001 Containment Iso Valves which are Bypass Valves (neu) .                                 VRR-004 General for Position 2 (new)                                   VRR-008 SRV Testing Sequence l
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Enclosure 2  '
NRC-99-0035 Page 5 of 5 i-  1" 10 Year        2dto Year Interval          Subject i  laterval Relief Request No. ROJ#      CSJ #    VRR#
(new)              ROJ-020                     HPCI Steam Throttle, E4100F068 l
   </new)                       CSJ-016           EECW Inbd PC Isolation Checks (new                                  VRR-010 OM-1, Torus - Drywell Vacuum Breaker Testing Requirements l
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l ENCLOSURE 3 TO NRC-99-0055 FERMI 2 DOCKET NO. 50-341 NRC LICENSE NO. NPF-43 I
IST PROGRAM         ;
1
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