ML12276A236: Difference between revisions
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| issue date = 10/17/2012 | | issue date = 10/17/2012 | ||
| title = Correction Letter for Amendment TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control | | title = Correction Letter for Amendment TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Volume Values to Licensee Control | ||
| author name = Chawla M | | author name = Chawla M | ||
| author affiliation = NRC/NRR/DORL/LPLIII-1 | | author affiliation = NRC/NRR/DORL/LPLIII-1 | ||
| addressee name = Plona J | | addressee name = Plona J | ||
| addressee affiliation = Detroit Edison, Co | | addressee affiliation = Detroit Edison, Co | ||
| docket = 05000341 | | docket = 05000341 | ||
| license number = NPF-043 | | license number = NPF-043 | ||
| contact person = Chawla M | | contact person = Chawla M | ||
| case reference number = TAC ME6861 | | case reference number = TAC ME6861 | ||
| document type = Letter | | document type = Letter | ||
| Line 22: | Line 22: | ||
==Dear Mr. Plona:== | ==Dear Mr. Plona:== | ||
On February 24,2011, the U.S. Nuclear Regulatory Commission (NRC) issued License Amendment No. 188 to Facility Operating License No. NPF-43 for the Fermi 2 facility (Agencywide Documents Access and Management System (ADAMS) Accession No. | On February 24,2011, the U.S. Nuclear Regulatory Commission (NRC) issued License Amendment No. 188 to Facility Operating License No. NPF-43 for the Fermi 2 facility (Agencywide Documents Access and Management System (ADAMS) Accession No. ML113500433). | ||
After issuance of the license amendment, Detroit Edison Company (the licensee) identified an administrative error on page 3.8-4 of the Technical Specifications (TSs). Specifically, the voltage values in Surveillance Requirements (SRs) 3.8.1.7.a and 3.8.1.7.b were incorrectly shown as 3740 instead of 3950. In the licensee's August 12, 2011, application (ADAMS Accession No. | After issuance of the license amendment, Detroit Edison Company (the licensee) identified an administrative error on page 3.8-4 of the Technical Specifications (TSs). Specifically, the voltage values in Surveillance Requirements (SRs) 3.8.1.7.a and 3.8.1.7.b were incorrectly shown as 3740 instead of 3950. In the licensee's August 12, 2011, application (ADAMS Accession No. ML112270114) associated with License Amendment No. 188, the voltage value in SRs 3.8.1.7.a and 3.8.1.7. b was correctly identified as 3950. Prior to issuance of the amendment, the licensee provided a copy of TS page 3.8-4 to the NRC staff for incorporating into the approved license amendment, and this copy contained the erroneous voltage value. License Amendment No. 188 only revised SR 3.8.1.4. Therefore, the voltage values specified in SRs 3.8.1.7.a and 3.8.1.7.b should reflect the last revision of TS page 3.8-4. Page 3.8-4 was last revised during issuance of License Amendment No. 183 (ADAMS Accession No. ML102770382), and indicated a voltage value of 3950 for SR 3.8.1.7.a and SR 3.8.1.7.b. | ||
J. Plona Please replace existing TS page 3.8-4 with the enclosed corrected replacement page. If you have any questions or concerns regarding this matter, please contact me at (301) 415-8371 or Mahesh.chawla@nrc.gov. Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341 | J. Plona Please replace existing TS page 3.8-4 with the enclosed corrected replacement page. If you have any questions or concerns regarding this matter, please contact me at (301) 415-8371 or Mahesh.chawla@nrc.gov. Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341 | ||
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TS Page 3.8-4 cc w/encl: Distribution via ListServ DISTRIBUTION: | TS Page 3.8-4 cc w/encl: Distribution via ListServ DISTRIBUTION: | ||
PUBLIC LPL3-1 R/F RidsAcrsAcnw | PUBLIC LPL3-1 R/F RidsAcrsAcnw | ||
_MaiICTR Resource RJones, Rill RidsNrrDssStsb Resource RidsNrrDorlDpr Resource MMorris, Rill RidsNrrDorlLpl3-1 Resource RidsNrrPMFermi2 Resource GWaig, NRR RidsNrrLABTully Resource RidsNrrDeEptb Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDssSbpb Resource JCameron, Rill MSingletary, NRR RWolfgang, NRR P ac k age A ccession Num b er: | _MaiICTR Resource RJones, Rill RidsNrrDssStsb Resource RidsNrrDorlDpr Resource MMorris, Rill RidsNrrDorlLpl3-1 Resource RidsNrrPMFermi2 Resource GWaig, NRR RidsNrrLABTully Resource RidsNrrDeEptb Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDssSbpb Resource JCameron, Rill MSingletary, NRR RWolfgang, NRR P ac k age A ccession Num b er: ML12276A236 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC(A) | ||
NRR/LPL3-1/PM NAME MChawla BTuily IFrankl MChawla ITBe/tz for DATE 10/16/12 10/16/12 10/17/12 10/17/12 OFFICIAL RECORD}} | NRR/LPL3-1/PM NAME MChawla BTuily IFrankl MChawla ITBe/tz for DATE 10/16/12 10/16/12 10/17/12 10/17/12 OFFICIAL RECORD}} | ||
Revision as of 15:27, 22 June 2019
| ML12276A236 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 10/17/2012 |
| From: | Mahesh Chawla Plant Licensing Branch III |
| To: | Plona J Detroit Edison, Co |
| Chawla M | |
| References | |
| TAC ME6861 | |
| Download: ML12276A236 (4) | |
Text
UNITED NUCLEAR REGULATORY WASHINGTON, D.C.
October 17, 2012 Mr. Joseph H. Plona Senior Vice President and Chief Nuclear Officer Detroit Edison Company Fermi 2 -210 NOC 6400 North Dixie Highway Newport, MI 48166 FERMI 2 -CORRECTION LETTER FOR AMENDMENT RE: TSTF-501, REVISION 1, "RELOCATE STORED FUEL OIL AND LUBE VOLUME VALUES TO LICENSEE CONTROL" (TAC NO. ME6861)
Dear Mr. Plona:
On February 24,2011, the U.S. Nuclear Regulatory Commission (NRC) issued License Amendment No. 188 to Facility Operating License No. NPF-43 for the Fermi 2 facility (Agencywide Documents Access and Management System (ADAMS) Accession No. ML113500433).
After issuance of the license amendment, Detroit Edison Company (the licensee) identified an administrative error on page 3.8-4 of the Technical Specifications (TSs). Specifically, the voltage values in Surveillance Requirements (SRs) 3.8.1.7.a and 3.8.1.7.b were incorrectly shown as 3740 instead of 3950. In the licensee's August 12, 2011, application (ADAMS Accession No. ML112270114) associated with License Amendment No. 188, the voltage value in SRs 3.8.1.7.a and 3.8.1.7. b was correctly identified as 3950. Prior to issuance of the amendment, the licensee provided a copy of TS page 3.8-4 to the NRC staff for incorporating into the approved license amendment, and this copy contained the erroneous voltage value. License Amendment No. 188 only revised SR 3.8.1.4. Therefore, the voltage values specified in SRs 3.8.1.7.a and 3.8.1.7.b should reflect the last revision of TS page 3.8-4. Page 3.8-4 was last revised during issuance of License Amendment No. 183 (ADAMS Accession No. ML102770382), and indicated a voltage value of 3950 for SR 3.8.1.7.a and SR 3.8.1.7.b.
J. Plona Please replace existing TS page 3.8-4 with the enclosed corrected replacement page. If you have any questions or concerns regarding this matter, please contact me at (301) 415-8371 or Mahesh.chawla@nrc.gov. Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341
Enclosure:
TS Page 3.8-4 cc w/encl: Distribution via ListServ 3.8.1 AC Sources-Operating SURVEILLANCE REQUIREMENTS (continued)
SURVEI LLANCE SR 3.8.1.4 Veri fy each day tank contai ns one hour supply of fuel oil. 31 days SR 3.8.1. 5 Check for and remove accumulated water from each day tank. 31 days SR 3.8.1.6 Verify each fuel oil transfer system operates to automatically transfer fuel oil from storage tanks to the day tanks. 31 days SR 3.8.1.7 -. -..... --. --. -... -NOTE -........ -. ------All EDG starts may be preceded by an eng-j ne prelube period and followed by a warmup period prior to loading. Verify each EDG starts from standby condition and achieves:
- a. In S 10 seconds. voltage 3950 V and frequency 58.8 Hz; and b. Steady state voltage 3950 V and s 4580 V and frequency 58.8 Hz and s 61.2 Hz. 184 days SR 3.8.1.8 Verify each EDG rejects a load greater than or equal to its associated single largest post-accident load. and following load rejection.
the frequency is S 66.75 Hz. 18 months (continued)
FERMI . UNIT 2 3.8-4 Amendment No. 134.178.183.188 J. Plona -Please replace existing TS page 3.8-4 with the enclosed corrected replacement page. If you have any questions or concerns regarding this matter, please contact me at (301) 415-8371 or Mahesh.chawla@nrc.gov. Sincerely, IRAJ Terry Beltz for Mahesh L. Chawla, Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-341
Enclosure:
TS Page 3.8-4 cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsAcrsAcnw
_MaiICTR Resource RJones, Rill RidsNrrDssStsb Resource RidsNrrDorlDpr Resource MMorris, Rill RidsNrrDorlLpl3-1 Resource RidsNrrPMFermi2 Resource GWaig, NRR RidsNrrLABTully Resource RidsNrrDeEptb Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDssSbpb Resource JCameron, Rill MSingletary, NRR RWolfgang, NRR P ac k age A ccession Num b er: ML12276A236 OFFICE NRR/LPL3-1/PM NRR/LPL3-1/LA NRR/LPL3-1/BC(A)
NRR/LPL3-1/PM NAME MChawla BTuily IFrankl MChawla ITBe/tz for DATE 10/16/12 10/16/12 10/17/12 10/17/12 OFFICIAL RECORD