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=Text=
=Text=
{{#Wiki_filter:UNITED NUCLEAR REGULATORY WASHINGTON, D.C. 20555-0001 January 22, 2010 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247 FORT CALHOUN STATION, UNIT NO.1 -CORRECTION TO AMENDMENT NO. 263 RE: REQUEST TO ADD STEAM GENERATOR BLOWDOWN ISOLATION REQUIREMENTS TO TECHNICAL SPECIFICATIONS (TAC NO. ME0596)  
{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 22, 2010 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247
 
==SUBJECT:==
FORT CALHOUN STATION, UNIT NO.1 - CORRECTION TO AMENDMENT NO. 263 RE: REQUEST TO ADD STEAM GENERATOR BLOWDOWN ISOLATION REQUIREMENTS TO TECHNICAL SPECIFICATIONS (TAC NO. ME0596)


==Dear Mr. Bannister:==
==Dear Mr. Bannister:==


On October 9, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML092540591), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 263 to Renewed Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit NO.1. The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated January 30, 2009, as supplemented by letters dated June 30 and August 28,2009 (ADAMS Accession Nos. ML090340536, ML091830041, and ML092440295, respectively).
On October 9, 2009 (Agencywide Documents Access and Management System (ADAMS)
Amendment No. 263 added steam generator blowdown isolation operability and surveillance requirements to the TSs. These requirements will be needed as a result of a plant modification to add an interlock to automatically isolate steam generator blowdown following a reactor trip. In addition, the amendment modified the remedial actions for channels that currently contain a key-operated bypass switch by deleting the term "key-operated" so that channels with a bypass switch that are not key-operated may be bypassed as well. On June 30, 2008, the NRC staff issued Amendment No. 257 (ADAMS Accession No. ML081790191), which renumbered most of the pages in TS 3.1. Upon implementation of Amendment No. 257, what had been TS 3.1 -Page 13 became TS 3.1 -Page 14. Due to an administrative error, the NRC issued Amendment No. 263 which revised TS 3.1 -Page 14 improperly as TS 3.1 -Page 13 thereby creating two TS pages having the same page number, TS 3.1 -Page 13. This administrative error did not impact Amendment No. 263 for FCS. The error does not change the NRC staff conclusions regarding Amendment No. 263 for FCS. Enclosed are corrected versions of TS 3.1 -Page 13 (Amendment 257) and TS 3.1 -Page 14 (Amendment 263). Please discard the associated pages from the previous amendments and replace them with the enclosed pages.
Accession No. ML092540591), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 263 to Renewed Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit NO.1. The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated January 30, 2009, as supplemented by letters dated June 30 and August 28,2009 (ADAMS Accession Nos. ML090340536, ML091830041, and ML092440295, respectively).
D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov.  
Amendment No. 263 added steam generator blowdown isolation operability and surveillance requirements to the TSs. These requirements will be needed as a result of a plant modification to add an interlock to automatically isolate steam generator blowdown following a reactor trip.
?eI Y ,. tt, /' Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285  
In addition, the amendment modified the remedial actions for channels that currently contain a key-operated bypass switch by deleting the term "key-operated" so that channels with a bypass switch that are not key-operated may be bypassed as well.
On June 30, 2008, the NRC staff issued Amendment No. 257 (ADAMS Accession No.
ML081790191), which renumbered most of the pages in TS 3.1. Upon implementation of Amendment No. 257, what had been TS 3.1 - Page 13 became TS 3.1 - Page 14. Due to an administrative error, the NRC issued Amendment No. 263 which revised TS 3.1 - Page 14 improperly as TS 3.1 - Page 13 thereby creating two TS pages having the same page number, TS 3.1 - Page 13.
This administrative error did not impact Amendment No. 263 for FCS. The error does not change the NRC staff conclusions regarding Amendment No. 263 for FCS. Enclosed are corrected versions of TS 3.1 - Page 13 (Amendment 257) and TS 3.1 - Page 14 (Amendment 263). Please discard the associated pages from the previous amendments and replace them with the enclosed pages.
 
D. Bannister                                 -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov.
                                          ?eI ,. Y          tt,
                                      /'   ~a      Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285


==Enclosures:==
==Enclosures:==


As stated cc w/encl: Distribution via Listserv   
As stated cc w/encl: Distribution via Listserv
 
ENCLOSURES OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 Corrected Technical Specification Page 3.1 - Page 13 (Amendment 257)
AND Corrected Technical Specification Page 3.1 - Page 14 (Amendment 263)
 
TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS
                                            ~              J Channel Description              Surveillance Function        Frequency Surveillance Method 0(6)
: 18. SIRW Tank Temperature        a. Check                            a. Verify that temperature is within limits.
: b. Test                        R    b. Measure temperature of SIRW tank with standard laboratory instruments.
: 19. Manual Recirculation          a. Test                        R    a. CHANNEL FUNCTIONAL TEST Actuation
: 20. Recirculation Actuation      a. Test                        Q    a. CHANNEL FUNCTIONAL TEST Logic R(7)
: b. Test                            b. CHANNEL FUNCTIONAL TEST
*21. 4.16 KV Emergency Bus        a. Check                      S    a. Verify voltage readings are above Low Voltage (Loss of                                                      alarm initiation on degraded voltage Voltage and Degraded                                                      level - supervisory lights "on".
Voltage) Actuation Logic
: b. Test                        Q    b. CHANNEL FUNCTIONAL TEST (Undervoltage relay)
: c. Calibrate                  R    c. CHANNEL CALIBRATION
: 22. Manual Emergency Off-site    a. Test                        R    a. CHANNEL FUNCTIONAL TEST Power Low Trip Actuation 3.1-Page13      Amendment No. 41.153.163.172.182.249,257
 
TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description                        Surveillance Function                          Frequency                    Surveillance Method
: 23. Auxiliary Feedwater                    a.        Check:                                      S                    a.
: 1) Steam Generator                                                        1)  CHANNEL CHECK Water Level Low (Wide Range)
: 2) Steam Generator                                                        2)    CHANNEL CHECK Pressure Low
: b.      Test:                                        QR(7)                b.
: 1) Actuation Logic                                                        1)  CHANNEL FUNCTIONAL TEST
: c.        Calibrate:                                  R                    c.
: 1) Steam Generator                                                        1)  CHANNEL CALIBRATION Water Level Low (Wide Range)
: 2) Steam Generator                                                        2)    CHANNEL CALIBRATION Pressure Low
: 3) Steam Generator                                                        3)    CHANNEL CALIBRATION Differential Pressure High
: 24. Manual Auxiliary Feedwater            a.      Test                                        R                    a.      CHANNEL FUNCTIONAL TEST Actuation
: 25. Manual Steam Generator                a.      Test                                        R                    a.      CHANNEL FUNCTIONAL TEST Blowdown Isolation
: 26. Automatic Steam Generator              a.      Test                                        R                    a.      CHANNEL FUNCTIONAL TEST Blowdown Isolation NOTES: (1) Not required unless pressurizer pressure is above 1700 psia.
(2)  CRHS monitors are the containment atmosphere gaseous radiation monitor and the Auxiliary Building Exhaust Stack gaseous radiation monitor.
(3)  Not required unless steam generator pressure is above 600 psia.
(4)  QP - Quarterly during designated modes and prior to taking the reactor critical if not completed within the previous 92 days (not applicable to a fast trip recovery).
(5)  Not required to be done on a SIT with inoperable level and/or pressure instrumentation.
(6)  Not required when outside ambient air temperature is greater than 50°F and less than 105°F.
(7)  Tests backup channels such as derived circuits and equipment that cannot be tested when the plant is at power.
(8)  SGLS is required for containment spray pump actuation only. SGLS lockout relays are not actuated for this test.
3.1 - Page 14                Amendment No. 41,54,65,122,163,171,172,182,255,257,263


OMAHA PUBLIC POWER FORT CALHOUN STATION, UNIT DOCKET NO. Corrected Technical Specification Page 3.1 -Page 13 (Amendment Corrected Technical Specification Page 3.1 -Page 14 (Amendment TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
D. Bannister                                 -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov.
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES.
Sincerely, IRA!
INSTRUMENTATION AND CONTROLS J Channel Description Surveillance Function Frequency Surveillance Method 18. SIRW Tank Temperature
Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285
: a. Check 0(6) a. Verify that temperature is within limits. b. Test R b. Measure temperature of SIRW tank with standard laboratory instruments.
: 19. Manual Recirculation
: a. Test R a. CHANNEL FUNCTIONAL TEST Actuation
: 20. Recirculation Actuation
: a. Test Q a. CHANNEL FUNCTIONAL TEST Logic b. Test R(7) b. CHANNEL FUNCTIONAL TEST *21. 4.16 KV Emergency Bus a. Check S a. Verify voltage readings are above Low Voltage (Loss of alarm initiation on degraded voltage Voltage and Degraded level -supervisory lights "on". Voltage) Actuation Logic b. Test Q b. CHANNEL FUNCTIONAL TEST (Undervoltage relay) c. Calibrate R c. CHANNEL CALIBRATION
: 22. Manual Emergency Off-site a. Test R a. CHANNEL FUNCTIONAL TEST Power Low Trip Actuation 3.1-Page13 Amendment No. 41.153.163.172.182.249,257 TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)
MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND Channel Description Surveillance Function Frequency Surveillance Method Auxiliary Feedwater
: a. Check: S a. Steam Generator
: 1) CHANNEL CHECK Water Level Low (Wide Range) Steam Generator
: 2) CHANNEL CHECK Pressure Low QR(7)Test: b. 1) Actuation Logic 1) CHANNEL FUNCTIONAL TEST Calibrate:
R c. 1) Steam Generator
: 1) CHANNEL CALIBRATION Water Level Low (Wide Range) 2) Steam Generator
: 2) CHANNEL CALIBRATION Pressure Low Steam Generator
: 3) CHANNEL CALIBRATION Differential Pressure High Manual Auxiliary Feedwater
: a. Test R a. CHANNEL FUNCTIONAL TEST Actuation Manual Steam Generator
: a. Test R a. CHANNEL FUNCTIONAL TEST Blowdown Isolation Automatic Steam Generator
: a. Test R a. CHANNEL FUNCTIONAL TEST Blowdown Isolation NOTES: (1) Not required unless pressurizer pressure is above 1700 psia. (2) CRHS monitors are the containment atmosphere gaseous radiation monitor and the Auxiliary Building Exhaust Stack gaseous radiation monitor. (3) Not required unless steam generator pressure is above 600 psia. (4) QP -Quarterly during designated modes and prior to taking the reactor critical if not completed within the previous 92 days (not applicable to a fast trip recovery).
(5) Not required to be done on a SIT with inoperable level and/or pressure instrumentation.
(6) Not required when outside ambient air temperature is greater than 50°F and less than 105°F. (7) Tests backup channels such as derived circuits and equipment that cannot be tested when the plant is at power. (8) SGLS is required for containment spray pump actuation only. SGLS lockout relays are not actuated for this test. -Page 14 Amendment No. 41,54,65,122,163,171,172,182,255,257,263 D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov.
Sincerely, IRA! Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285  


==Enclosures:==
==Enclosures:==


As stated cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource GHill,OIS RecordsAmend Resource ADAMS Accession No. ML093561119 OFFICE NRR/LPL4/PM NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NRR/LPL4/PM NAME LWilkins AWang JBurkhardt MMarkley LWilkins DATE 1/19/10 1/20/10 1/19/10 1/22/10 1/22/10 OFFICIAL AGENCY}}
As stated cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource GHill,OIS RecordsAmend Resource ADAMS Accession No. ML093561119 OFFICE NRR/LPL4/PM           NRR/LPL4/PM     NRR/LPL4/LA       NRR/LPL4/BC       NRR/LPL4/PM NAME     LWilkins           AWang           JBurkhardt       MMarkley         LWilkins DATE     1/19/10           1/20/10         1/19/10           1/22/10           1/22/10 OFFICIAL AGENCY RECORD}}

Revision as of 23:23, 13 November 2019

Correction to Amendment No. 263 Request to Add Steam Generator Blowdown Isolation Requirements to Technical Specifications
ML093561119
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 01/22/2010
From: Lynnea Wilkins
Plant Licensing Branch IV
To: Bannister D
Omaha Public Power District
Wilkins, L E, NRR/DORL/LPL4, 415-1377
References
TAC ME0596
Download: ML093561119 (6)
v • d • e


Text

UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 January 22, 2010 Mr. David J. Bannister Vice President and CNO Omaha Public Power District Fort Calhoun Station 444 South 16th St. Mall Omaha, NE 68102-2247

SUBJECT:

FORT CALHOUN STATION, UNIT NO.1 - CORRECTION TO AMENDMENT NO. 263 RE: REQUEST TO ADD STEAM GENERATOR BLOWDOWN ISOLATION REQUIREMENTS TO TECHNICAL SPECIFICATIONS (TAC NO. ME0596)

Dear Mr. Bannister:

On October 9, 2009 (Agencywide Documents Access and Management System (ADAMS)

Accession No. ML092540591), the U.S. Nuclear Regulatory Commission (NRC) issued Amendment No. 263 to Renewed Facility Operating License No. DPR-40 for the Fort Calhoun Station, Unit NO.1. The amendment consisted of changes to the Technical Specifications (TSs) in response to your application dated January 30, 2009, as supplemented by letters dated June 30 and August 28,2009 (ADAMS Accession Nos. ML090340536, ML091830041, and ML092440295, respectively).

Amendment No. 263 added steam generator blowdown isolation operability and surveillance requirements to the TSs. These requirements will be needed as a result of a plant modification to add an interlock to automatically isolate steam generator blowdown following a reactor trip.

In addition, the amendment modified the remedial actions for channels that currently contain a key-operated bypass switch by deleting the term "key-operated" so that channels with a bypass switch that are not key-operated may be bypassed as well.

On June 30, 2008, the NRC staff issued Amendment No. 257 (ADAMS Accession No.

ML081790191), which renumbered most of the pages in TS 3.1. Upon implementation of Amendment No. 257, what had been TS 3.1 - Page 13 became TS 3.1 - Page 14. Due to an administrative error, the NRC issued Amendment No. 263 which revised TS 3.1 - Page 14 improperly as TS 3.1 - Page 13 thereby creating two TS pages having the same page number, TS 3.1 - Page 13.

This administrative error did not impact Amendment No. 263 for FCS. The error does not change the NRC staff conclusions regarding Amendment No. 263 for FCS. Enclosed are corrected versions of TS 3.1 - Page 13 (Amendment 257) and TS 3.1 - Page 14 (Amendment 263). Please discard the associated pages from the previous amendments and replace them with the enclosed pages.

D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov.

?eI ,. Y tt,

/' ~a Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosures:

As stated cc w/encl: Distribution via Listserv

ENCLOSURES OMAHA PUBLIC POWER DISTRICT FORT CALHOUN STATION, UNIT 1 DOCKET NO. 50-285 Corrected Technical Specification Page 3.1 - Page 13 (Amendment 257)

AND Corrected Technical Specification Page 3.1 - Page 14 (Amendment 263)

TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES. INSTRUMENTATION AND CONTROLS

~ J Channel Description Surveillance Function Frequency Surveillance Method 0(6)

18. SIRW Tank Temperature a. Check a. Verify that temperature is within limits.
b. Test R b. Measure temperature of SIRW tank with standard laboratory instruments.
19. Manual Recirculation a. Test R a. CHANNEL FUNCTIONAL TEST Actuation
20. Recirculation Actuation a. Test Q a. CHANNEL FUNCTIONAL TEST Logic R(7)
b. Test b. CHANNEL FUNCTIONAL TEST
  • 21. 4.16 KV Emergency Bus a. Check S a. Verify voltage readings are above Low Voltage (Loss of alarm initiation on degraded voltage Voltage and Degraded level - supervisory lights "on".

Voltage) Actuation Logic

b. Test Q b. CHANNEL FUNCTIONAL TEST (Undervoltage relay)
c. Calibrate R c. CHANNEL CALIBRATION
22. Manual Emergency Off-site a. Test R a. CHANNEL FUNCTIONAL TEST Power Low Trip Actuation 3.1-Page13 Amendment No. 41.153.163.172.182.249,257

TECHNICAL SPECIFICATIONS TABLE 3-2 (continued)

MINIMUM FREQUENCIES FOR CHECKS, CALIBRATIONS AND TESTING OF ENGINEERED SAFETY FEATURES, INSTRUMENTATION AND CONTROLS Channel Description Surveillance Function Frequency Surveillance Method

23. Auxiliary Feedwater a. Check: S a.
1) Steam Generator 1) CHANNEL CHECK Water Level Low (Wide Range)
2) Steam Generator 2) CHANNEL CHECK Pressure Low
b. Test: QR(7) b.
1) Actuation Logic 1) CHANNEL FUNCTIONAL TEST
c. Calibrate: R c.
1) Steam Generator 1) CHANNEL CALIBRATION Water Level Low (Wide Range)
2) Steam Generator 2) CHANNEL CALIBRATION Pressure Low
3) Steam Generator 3) CHANNEL CALIBRATION Differential Pressure High
24. Manual Auxiliary Feedwater a. Test R a. CHANNEL FUNCTIONAL TEST Actuation
25. Manual Steam Generator a. Test R a. CHANNEL FUNCTIONAL TEST Blowdown Isolation
26. Automatic Steam Generator a. Test R a. CHANNEL FUNCTIONAL TEST Blowdown Isolation NOTES: (1) Not required unless pressurizer pressure is above 1700 psia.

(2) CRHS monitors are the containment atmosphere gaseous radiation monitor and the Auxiliary Building Exhaust Stack gaseous radiation monitor.

(3) Not required unless steam generator pressure is above 600 psia.

(4) QP - Quarterly during designated modes and prior to taking the reactor critical if not completed within the previous 92 days (not applicable to a fast trip recovery).

(5) Not required to be done on a SIT with inoperable level and/or pressure instrumentation.

(6) Not required when outside ambient air temperature is greater than 50°F and less than 105°F.

(7) Tests backup channels such as derived circuits and equipment that cannot be tested when the plant is at power.

(8) SGLS is required for containment spray pump actuation only. SGLS lockout relays are not actuated for this test.

3.1 - Page 14 Amendment No. 41,54,65,122,163,171,172,182,255,257,263

D. Bannister -2 If you have any questions, please contact me at 301-415-1377 or Iynnea.wilkins@nrc.gov.

Sincerely, IRA!

Lynnea Wilkins, Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-285

Enclosures:

As stated cc w/encl: Distribution via Listserv DISTRIBUTION PUBLIC LPLIV Reading RidsAcrsAcnw_MailCTR Resource RidsNrrDorlLpl4 Resource RidsNrrPMFortCalhoun Resource RidsNrrLAJBurkhardt Resource RidsOgcRp Resource RidsRgn4MailCenter Resource GHill,OIS RecordsAmend Resource ADAMS Accession No. ML093561119 OFFICE NRR/LPL4/PM NRR/LPL4/PM NRR/LPL4/LA NRR/LPL4/BC NRR/LPL4/PM NAME LWilkins AWang JBurkhardt MMarkley LWilkins DATE 1/19/10 1/20/10 1/19/10 1/22/10 1/22/10 OFFICIAL AGENCY RECORD

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