ML16236A096: Difference between revisions
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{{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear Nine Mile Point Nuclear Station, LLC 4300 Winfield Road Warrenville, IL 60555 | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 26, 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear Nine Mile Point Nuclear Station, LLC 4300 Winfield Road Warrenville, IL 60555 | ||
==SUBJECT:== | ==SUBJECT:== | ||
R. E. GINNA NUCLEAR POWER PLANT -CORRECTION LETTER TO LICENSE AMENDMENT NO. 122 RE: LICENSE AMENDMENT REQUEST TO RELOCATE SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO A LICENSEE CONTROLLED PROGRAM -ADOPTION OF TSTF-425, REVISION 3 (CAC NO. MF6358) | R. E. GINNA NUCLEAR POWER PLANT - CORRECTION LETTER TO LICENSE AMENDMENT NO. 122 RE: LICENSE AMENDMENT REQUEST TO RELOCATE SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO A LICENSEE CONTROLLED PROGRAM - ADOPTION OF TSTF-425, REVISION 3 (CAC NO. MF6358) | ||
==Dear Mr. Hanson:== | ==Dear Mr. Hanson:== | ||
On June 28, 2016 (Agencywide Documents Access and Management System Accession No. ML16125A485), the Nuclear Regulatory Commission (NRC) issued Amendment No. 122 to Renewed Facility Operating License No. DPR-18 for Exelon Generation Company, LLC, the licensee for R.E. Ginna Nuclear Power Plant (Ginna). This amendment revised the technical specifications (TSs) tor Ginna by relocating specific TS surveillance frequencies to a licensee-controlled program with the adoption of Technical Specification Task Force -425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control -Risk Informed Technical Specification Task Force Initiative Sb". Additionally, the change added a new program, the Surveillance Frequency Control Program, to TS Section 5, Administrative Controls. | |||
In reviewing the above information, the NRC staff noted that there was an administrative typographical error on TS page 3.4.(3-2 for Amendment No. 122. In particular, Surveillance Requirement 3.4.6.4 includes a note that states, "Not required to performed until 12 yours after entering MODE 4", but it should state, "Not required to be performed until 12 hours after entering MODE 4". The correction to TS page 3.4.6-2 is provided and should be replaced with the enclosed TS page 3.4.6.2. These administrative typographical errors do not affect the staff's overall conclusions associated with approval of Amendment No. 122. The changes are within the scope of the application as originally noticed in the Federal Registeron October 13, 2015 (80 FR 61482). We regret any inconvenience the error may have caused. | On June 28, 2016 (Agencywide Documents Access and Management System Accession No. ML16125A485), the Nuclear Regulatory Commission (NRC) issued Amendment No. 122 to Renewed Facility Operating License No. DPR-18 for Exelon Generation Company, LLC, the licensee for R.E. Ginna Nuclear Power Plant (Ginna). This amendment revised the technical specifications (TSs) tor Ginna by relocating specific TS surveillance frequencies to a licensee-controlled program with the adoption of Technical Specification Task Force - 425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative Sb". Additionally, the change added a new program, the Surveillance Frequency Control Program, to TS Section 5, Administrative Controls. | ||
B. Hanson If there are any questions regarding this matter, please contact me at 301-415-3629. | In reviewing the above information, the NRC staff noted that there was an administrative typographical error on TS page 3.4.(3-2 for Amendment No. 122. In particular, Surveillance Requirement 3.4.6.4 includes a note that states, "Not required to performed until 12 yours after entering MODE 4", but it should state, "Not required to be performed until 12 hours after entering MODE 4". The correction to TS page 3.4.6-2 is provided and should be replaced with the enclosed TS page 3.4.6.2. | ||
Docket No. 50-244 | These administrative typographical errors do not affect the staff's overall conclusions associated with approval of Amendment No. 122. The changes are within the scope of the application as originally noticed in the Federal Registeron October 13, 2015 (80 FR 61482). We regret any inconvenience the error may have caused. | ||
B. Hanson If there are any questions regarding this matter, please contact me at 301-415-3629. | |||
Diane Render, Project Manager Plant Licensing Branch 1-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244 | |||
==Enclosure:== | ==Enclosure:== | ||
As stated cc w/encl: Distribution via Listserv | As stated cc w/encl: Distribution via Listserv | ||
RCS Loops - MODE 4 3.4.6 CONDITION REQUIRED ACTION COMPLETION TIME B. One RHR loop ------------------ | |||
- NOTE - | |||
inoperable. | |||
Required Action B.1 is not applicable if all RCS and AND RHR loops are inoperable and Condition C is entered. | |||
Two RCS loops -- - - - - - - - - - - - - - - - - | |||
inoperable. | |||
B.1 Be in MODE 5. 24 hours C. All RCS and RHR loops C.1 Suspend operations that Immediately inoperable. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet the No RCS or RHR loop in SDM of LCO 3.1.1. | |||
operation. | |||
AND C.2 Initiate action to restore one Immediately loop to OPERABLE status and operation. | |||
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY In accordance with SR 3.4.6.1 Verify one RHR or RCS loop is in operation. | |||
the Surveillance Frequency Control Program In accordance with SR 3.4.6.2 Verify SG secondary side water level is ~ 16% for the Surveillance each required RCS loop. | |||
Frequency Control Program In accordance with SR 3.4.6.3 Verify correct breaker alignment and indicated power the Surveillance are available to the required pump that is not in Frequency Control operation. | |||
Program In accordance with SR 3.4.6.4 -----------------NOTE------------------ | |||
the Surveillance Not required to be performed until 12 hours after Frequency Control entering MODE 4. Program Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water. | |||
R.E. Ginna Nuclear Power Plant 3.4.6-2 Amendment No. 122 | |||
ML16236A096 OFFICE LPL 1-1/PM LPL 1-1/LA RPB1/BC LPL1-1/PM NAME DRender KGoldstein TTate DRender DATE 08/18/2016 08/23/16 08/25/2016 08/26/2016}} | |||
Latest revision as of 14:51, 30 October 2019
ML16236A096 | |
Person / Time | |
---|---|
Site: | Ginna |
Issue date: | 08/26/2016 |
From: | Render D Plant Licensing Branch 1 |
To: | Bryan Hanson Exelon Nuclear, Nine Mile Point |
Render D, NRR/DORL/LPL1-1, 415-3629 | |
References | |
CAC MF6358 | |
Download: ML16236A096 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 26, 2016 Mr. Bryan C. Hanson President and Chief Nuclear Officer Exelon Nuclear Nine Mile Point Nuclear Station, LLC 4300 Winfield Road Warrenville, IL 60555
SUBJECT:
R. E. GINNA NUCLEAR POWER PLANT - CORRECTION LETTER TO LICENSE AMENDMENT NO. 122 RE: LICENSE AMENDMENT REQUEST TO RELOCATE SPECIFIC SURVEILLANCE FREQUENCY REQUIREMENTS TO A LICENSEE CONTROLLED PROGRAM - ADOPTION OF TSTF-425, REVISION 3 (CAC NO. MF6358)
Dear Mr. Hanson:
On June 28, 2016 (Agencywide Documents Access and Management System Accession No. ML16125A485), the Nuclear Regulatory Commission (NRC) issued Amendment No. 122 to Renewed Facility Operating License No. DPR-18 for Exelon Generation Company, LLC, the licensee for R.E. Ginna Nuclear Power Plant (Ginna). This amendment revised the technical specifications (TSs) tor Ginna by relocating specific TS surveillance frequencies to a licensee-controlled program with the adoption of Technical Specification Task Force - 425, Revision 3, "Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative Sb". Additionally, the change added a new program, the Surveillance Frequency Control Program, to TS Section 5, Administrative Controls.
In reviewing the above information, the NRC staff noted that there was an administrative typographical error on TS page 3.4.(3-2 for Amendment No. 122. In particular, Surveillance Requirement 3.4.6.4 includes a note that states, "Not required to performed until 12 yours after entering MODE 4", but it should state, "Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after entering MODE 4". The correction to TS page 3.4.6-2 is provided and should be replaced with the enclosed TS page 3.4.6.2.
These administrative typographical errors do not affect the staff's overall conclusions associated with approval of Amendment No. 122. The changes are within the scope of the application as originally noticed in the Federal Registeron October 13, 2015 (80 FR 61482). We regret any inconvenience the error may have caused.
B. Hanson If there are any questions regarding this matter, please contact me at 301-415-3629.
Diane Render, Project Manager Plant Licensing Branch 1-1 Division of Operator Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated cc w/encl: Distribution via Listserv
RCS Loops - MODE 4 3.4.6 CONDITION REQUIRED ACTION COMPLETION TIME B. One RHR loop ------------------
- NOTE -
Required Action B.1 is not applicable if all RCS and AND RHR loops are inoperable and Condition C is entered.
Two RCS loops -- - - - - - - - - - - - - - - - -
B.1 Be in MODE 5. 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> C. All RCS and RHR loops C.1 Suspend operations that Immediately inoperable. would cause introduction of coolant into the RCS with OR boron concentration less than required to meet the No RCS or RHR loop in SDM of LCO 3.1.1.
operation.
AND C.2 Initiate action to restore one Immediately loop to OPERABLE status and operation.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY In accordance with SR 3.4.6.1 Verify one RHR or RCS loop is in operation.
the Surveillance Frequency Control Program In accordance with SR 3.4.6.2 Verify SG secondary side water level is ~ 16% for the Surveillance each required RCS loop.
Frequency Control Program In accordance with SR 3.4.6.3 Verify correct breaker alignment and indicated power the Surveillance are available to the required pump that is not in Frequency Control operation.
Program In accordance with SR 3.4.6.4 -----------------NOTE------------------
the Surveillance Not required to be performed until 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> after Frequency Control entering MODE 4. Program Verify required RHR loop locations susceptible to gas accumulation are sufficiently filled with water.
R.E. Ginna Nuclear Power Plant 3.4.6-2 Amendment No. 122
ML16236A096 OFFICE LPL 1-1/PM LPL 1-1/LA RPB1/BC LPL1-1/PM NAME DRender KGoldstein TTate DRender DATE 08/18/2016 08/23/16 08/25/2016 08/26/2016