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=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 April 22, 2010 Vice President, Operations Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 WATERFORD STEAM ELECTRIC STATION, UNIT 3 -CORRECTION TO TECHNICAL SPECIFICATION PAGE 3/4 3-10 ISSUED WITH AMENDMENT NO. 225 RE: RELOCATION STEAM GENERATOR HIGH LEVEL TRIP FUNCTION (TAC NO. ME2464)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 22, 2010 Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093
 
==SUBJECT:==
WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CORRECTION TO TECHNICAL SPECIFICATION PAGE 3/4 3-10 ISSUED WITH AMENDMENT NO. 225 RE: RELOCATION STEAM GENERATOR HIGH LEVEL TRIP FUNCTION (TAC NO. ME2464)


==Dear Sir or Madam:==
==Dear Sir or Madam:==
On March 18, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093480507), the U.S. Nuclear Regulatory Commission (NRC) staff issued Amendment No. 225 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3. This amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated October 19, 2009 (ADAMS Accession No. ML092940242).
 
The NRC staff discovered a typographical error on TS page 3/4 3-10 that was introduced when the TS pages were being numbered as Amendment No. 225. The resulting error on TS page 3/43-10 was an incorrect title for TABLE 4.3-1, which should have been "REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS." The title for TABLE 4.3-1 has been corrected and a revised TS page 3/4 3-10 is enclosed.
On March 18, 2010 (Agencywide Documents Access and Management System (ADAMS)
Please remove TS page 3/4 3-10 issued on March 18, 2010, and replace it with the enclosed corrected version. This error did not impact Amendment No. 225 and does not change the NRC staff conclusions regarding Amendment No. 225 for Waterford  
Accession No. ML093480507), the U.S. Nuclear Regulatory Commission (NRC) staff issued Amendment No. 225 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3. This amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated October 19, 2009 (ADAMS Accession No. ML092940242).
: 3. We regret any inconvenience caused by this error. If you have any questions, please contact me at 301-415-1480 or via e-mail at kaly.kalyanam@nrc.gov.
The NRC staff discovered a typographical error on TS page 3/4 3-10 that was introduced when the TS pages were being numbered as Amendment No. 225. The resulting error on TS page 3/43-10 was an incorrect title for TABLE 4.3-1, which should have been "REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS." The title for TABLE 4.3-1 has been corrected and a revised TS page 3/4 3-10 is enclosed. Please remove TS page 3/4 3-10 issued on March 18, 2010, and replace it with the enclosed corrected version.
Sincerely, N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382  
This error did not impact Amendment No. 225 and does not change the NRC staff conclusions regarding Amendment No. 225 for Waterford 3.
We regret any inconvenience caused by this error. If you have any questions, please contact me at 301-415-1480 or via e-mail at kaly.kalyanam@nrc.gov.
Sincerely, N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382


==Enclosure:==
==Enclosure:==


As stated cc w/encl: Distribution via Listserv
As stated cc w/encl: Distribution via Listserv


CORRECTED TECHNICAL SPECIFICATION PAGE 3/4 RE: AMENDMENT NO. 225 ISSUED ON MARCH 18, FOR WATERFORD STEAM ELECTRIC STATION, UNIT DOCKET NO.
ENCLOSURE CORRECTED TECHNICAL SPECIFICATION PAGE 3/4 3-10 RE: AMENDMENT NO. 225 ISSUED ON MARCH 18, 2010 FOR WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382
TABLE REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED 1. Manual Reactor Trip N.A. Rand S/U(1) 1,2,3*,4*,5* Linear Power Level -High S D(2,4),M(3,4), Q 1,2 Q(4) 3. Logarithmic Power Level-High R(4) Q and S/U(1) 2#,3,4,5 4. Pressurizer Pressure -High R Q 1,2 5. Pressurizer Pressure -Low R Q 1,2 6. Containment Pressure -High R Q 1,2 7. Steam Generator Pressure -Low R Q 1,2 8. Steam Generator Level -Low R Q 1,2 9. Local Power Density -High 0(2,4), R(4,5) Q, R(6) 1,2 DNBR -Low S S(7), 0(2,4), Q, R(6) 1,2 M(8), R(4,5) DELETED Reactor Protection System Logic N.A. N.A. Q(11) and S/U(1) 1,2,3*,4*,5*
 
WATERFORD  
TABLE 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL         MODES FOR WHICH CHANNEL     CHANNEL         FUNCTIONAL       SURVEILLANCE FUNCTIONAL UNIT                         CHECK   CALIBRATION         TEST           IS REQUIRED
-UNIT 3/43-10 AMENDMENT NO. 40. 69. 153.
: 1. Manual Reactor Trip                 N.A.        N.A.           Rand S/U(1)       1,2,3*,4*,5*
April 22, 2010 Vice President, Operations Entergy Operations, Inc. Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 WATERFORD STEAM ELECTRIC STATION, UNIT 3 -CORRECTION TO TECHNICAL SPECIFICATION PAGE 3/4 3-10 ISSUED WITH AMENDMENT NO. 225 RE: RELOCATION STEAM GENERATOR HIGH LEVEL TRIP FUNCTION (TAC NO. ME2464)  
: 2. Linear Power Level - High           S           D(2,4),M(3,4), Q                 1,2 Q(4)
: 3. Logarithmic Power Level- High       S          R(4)             Q and S/U(1)       2#,3,4,5
: 4. Pressurizer Pressure - High           S        R               Q                 1,2
: 5. Pressurizer Pressure - Low         S          R               Q                 1,2
: 6. Containment Pressure - High           S        R               Q                 1,2
: 7. Steam Generator Pressure - Low       S          R               Q                 1,2
: 8. Steam Generator Level - Low           S        R               Q                 1,2
: 9. Local Power Density - High           S          0(2,4), R(4,5)   Q, R(6)           1,2
: 10. DNBR - Low                         S         S(7), 0(2,4),   Q, R(6)           1,2 M(8), R(4,5)
: 11. DELETED
: 12. Reactor Protection System Logic                             N.A.     N.A.             Q(11) and S/U(1)   1,2,3*,4*,5*
WATERFORD - UNIT 3                                3/43-10                         AMENDMENT NO. 40. 69. 153. 225
 
April 22, 2010 Vice President, Operations Entergy Operations, Inc.
Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 SUB"IECT:          WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CORRECTION TO TECHNICAL SPECIFICATION PAGE 3/4 3-10 ISSUED WITH AMENDMENT NO. 225 RE: RELOCATION STEAM GENERATOR HIGH LEVEL TRIP FUNCTION (TAC NO. ME2464)


==Dear Sir or Madam:==
==Dear Sir or Madam:==
On March 18, 2010 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML093480507), the U.S. Nuclear Regulatory Commission (NRC) staff issued Amendment No. 225 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3. This amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated October 19, 2009 (ADAMS Accession No. ML092940242).
 
The NRC staff discovered a typographical error on TS page 3/4 3-10 that was introduced when the TS pages were being numbered as Amendment No. 225. The resulting error on TS page 3/43-10 was an incorrect title for TABLE 4.3-1, which should have been "REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS." The title for TABLE 4.3-1 has been corrected and a revised TS page 3/4 3-10 is enclosed.
On March 18, 2010 (Agencywide Documents Access and Management System (ADAMS)
Please remove TS page 3/4 3-10 issued on March 18, 2010, and replace it with the enclosed corrected version. This error did not impact Amendment No. 225 and does not change the NRC staff conclusions regarding Amendment No. 225 for Waterford  
Accession No. ML093480507), the U.S. Nuclear Regulatory Commission (NRC) staff issued Amendment No. 225 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3. This amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated October 19, 2009 (ADAMS Accession No. ML092940242).
: 3. We regret any inconvenience caused by this error. If you have any questions, please contact me at 301-415-1480 orvia e-mail at kaly.kalyanam@nrc.gov.
The NRC staff discovered a typographical error on TS page 3/4 3-10 that was introduced when the TS pages were being numbered as Amendment No. 225. The resulting error on TS page 3/43-10 was an incorrect title for TABLE 4.3-1, which should have been "REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS." The title for TABLE 4.3-1 has been corrected and a revised TS page 3/4 3-10 is enclosed. Please remove TS page 3/4 3-10 issued on March 18, 2010, and replace it with the enclosed corrected version.
Sincerely, IRA! N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382  
This error did not impact Amendment No. 225 and does not change the NRC staff conclusions regarding Amendment No. 225 for Waterford 3.
We regret any inconvenience caused by this error. If you have any questions, please contact me at 301-415-1480 orvia e-mail at kaly.kalyanam@nrc.gov.
Sincerely, IRA!
N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382


==Enclosure:==
==Enclosure:==


As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
As stated cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDorlLpl4 Resource KBucholtz, NRRlDIRS/ITSB LPLIV r/f RidsNrrDorlDpr Resource PChung, NRRIDElEICB RidsAcrsAcnw_MailCTR Resource RidsNrrPMWaterford Resource KDesai, NRRlDSS/SRXB RidsNrrDeEicb Resource RidsNrrLAJBurkhardt Resource GHill,OIS RidsNrrDssSrxb Resource RidsOgcRp Resource RecordsAmend Resource RidsNrrDirsltsb Resource RidsRgn4MailCenter Resource ADAMS Accession No ML 101110035 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NRR/LPL4/PM NAME NKalyanam JBurkhardt MMarkley NKalyanam DATE 4/21/10 4/21/10 4/22/10 4/22/10 OFFICIAL RECORD COpy}}
PUBLIC                             RidsNrrDorlLpl4 Resource             KBucholtz, NRRlDIRS/ITSB LPLIV r/f                           RidsNrrDorlDpr Resource               PChung, NRRIDElEICB RidsAcrsAcnw_MailCTR Resource       RidsNrrPMWaterford Resource           KDesai, NRRlDSS/SRXB RidsNrrDeEicb Resource             RidsNrrLAJBurkhardt Resource         GHill,OIS RidsNrrDssSrxb Resource             RidsOgcRp Resource                   RecordsAmend Resource RidsNrrDirsltsb Resource           RidsRgn4MailCenter Resource ADAMS Accession No ML101110035 OFFICE       NRR/LPL4/PM         NRR/LPL4/LA                 NRR/LPL4/BC             NRR/LPL4/PM NAME         NKalyanam           JBurkhardt                 MMarkley               NKalyanam DATE         4/21/10             4/21/10                   4/22/10                 4/22/10 OFFICIAL RECORD COpy}}

Latest revision as of 20:41, 13 November 2019

Correction to Technical Specification Page 3/4 3-10 Issued with Amendment No. 225 Technical Specification Change to Relocate Steam Generator Level - High Trip Function
ML101110035
Person / Time
Site: Waterford Entergy icon.png
Issue date: 04/22/2010
From: Kalyanam K
Plant Licensing Branch IV
To:
Entergy Operations
Kalyanam N, NRR/DORL/LPL4, 415-1480
References
TAC ME2464
Download: ML101110035 (4)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 April 22, 2010 Vice President, Operations Entergy Operations, Inc.

Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093

SUBJECT:

WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CORRECTION TO TECHNICAL SPECIFICATION PAGE 3/4 3-10 ISSUED WITH AMENDMENT NO. 225 RE: RELOCATION STEAM GENERATOR HIGH LEVEL TRIP FUNCTION (TAC NO. ME2464)

Dear Sir or Madam:

On March 18, 2010 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML093480507), the U.S. Nuclear Regulatory Commission (NRC) staff issued Amendment No. 225 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3. This amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated October 19, 2009 (ADAMS Accession No. ML092940242).

The NRC staff discovered a typographical error on TS page 3/4 3-10 that was introduced when the TS pages were being numbered as Amendment No. 225. The resulting error on TS page 3/43-10 was an incorrect title for TABLE 4.3-1, which should have been "REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS." The title for TABLE 4.3-1 has been corrected and a revised TS page 3/4 3-10 is enclosed. Please remove TS page 3/4 3-10 issued on March 18, 2010, and replace it with the enclosed corrected version.

This error did not impact Amendment No. 225 and does not change the NRC staff conclusions regarding Amendment No. 225 for Waterford 3.

We regret any inconvenience caused by this error. If you have any questions, please contact me at 301-415-1480 or via e-mail at kaly.kalyanam@nrc.gov.

Sincerely, N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382

Enclosure:

As stated cc w/encl: Distribution via Listserv

ENCLOSURE CORRECTED TECHNICAL SPECIFICATION PAGE 3/4 3-10 RE: AMENDMENT NO. 225 ISSUED ON MARCH 18, 2010 FOR WATERFORD STEAM ELECTRIC STATION, UNIT 3 DOCKET NO. 50-382

TABLE 4.3-1 REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS CHANNEL MODES FOR WHICH CHANNEL CHANNEL FUNCTIONAL SURVEILLANCE FUNCTIONAL UNIT CHECK CALIBRATION TEST IS REQUIRED

1. Manual Reactor Trip N.A. N.A. Rand S/U(1) 1,2,3*,4*,5*
2. Linear Power Level - High S D(2,4),M(3,4), Q 1,2 Q(4)
3. Logarithmic Power Level- High S R(4) Q and S/U(1) 2#,3,4,5
4. Pressurizer Pressure - High S R Q 1,2
5. Pressurizer Pressure - Low S R Q 1,2
6. Containment Pressure - High S R Q 1,2
7. Steam Generator Pressure - Low S R Q 1,2
8. Steam Generator Level - Low S R Q 1,2
9. Local Power Density - High S 0(2,4), R(4,5) Q, R(6) 1,2
10. DNBR - Low S S(7), 0(2,4), Q, R(6) 1,2 M(8), R(4,5)
11. DELETED
12. Reactor Protection System Logic N.A. N.A. Q(11) and S/U(1) 1,2,3*,4*,5*

WATERFORD - UNIT 3 3/43-10 AMENDMENT NO. 40. 69. 153. 225

April 22, 2010 Vice President, Operations Entergy Operations, Inc.

Waterford Steam Electric Station, Unit 3 17265 River Road Killona, LA 70057-3093 SUB"IECT: WATERFORD STEAM ELECTRIC STATION, UNIT 3 - CORRECTION TO TECHNICAL SPECIFICATION PAGE 3/4 3-10 ISSUED WITH AMENDMENT NO. 225 RE: RELOCATION STEAM GENERATOR HIGH LEVEL TRIP FUNCTION (TAC NO. ME2464)

Dear Sir or Madam:

On March 18, 2010 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML093480507), the U.S. Nuclear Regulatory Commission (NRC) staff issued Amendment No. 225 to Facility Operating License No. NPF-38 for the Waterford Steam Electric Station, Unit 3. This amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated October 19, 2009 (ADAMS Accession No. ML092940242).

The NRC staff discovered a typographical error on TS page 3/4 3-10 that was introduced when the TS pages were being numbered as Amendment No. 225. The resulting error on TS page 3/43-10 was an incorrect title for TABLE 4.3-1, which should have been "REACTOR PROTECTIVE INSTRUMENTATION SURVEILLANCE REQUIREMENTS." The title for TABLE 4.3-1 has been corrected and a revised TS page 3/4 3-10 is enclosed. Please remove TS page 3/4 3-10 issued on March 18, 2010, and replace it with the enclosed corrected version.

This error did not impact Amendment No. 225 and does not change the NRC staff conclusions regarding Amendment No. 225 for Waterford 3.

We regret any inconvenience caused by this error. If you have any questions, please contact me at 301-415-1480 orvia e-mail at kaly.kalyanam@nrc.gov.

Sincerely, IRA!

N. Kalyanam, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-382

Enclosure:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION:

PUBLIC RidsNrrDorlLpl4 Resource KBucholtz, NRRlDIRS/ITSB LPLIV r/f RidsNrrDorlDpr Resource PChung, NRRIDElEICB RidsAcrsAcnw_MailCTR Resource RidsNrrPMWaterford Resource KDesai, NRRlDSS/SRXB RidsNrrDeEicb Resource RidsNrrLAJBurkhardt Resource GHill,OIS RidsNrrDssSrxb Resource RidsOgcRp Resource RecordsAmend Resource RidsNrrDirsltsb Resource RidsRgn4MailCenter Resource ADAMS Accession No ML101110035 OFFICE NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NRR/LPL4/PM NAME NKalyanam JBurkhardt MMarkley NKalyanam DATE 4/21/10 4/21/10 4/22/10 4/22/10 OFFICIAL RECORD COpy

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