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Category:License-Operator
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[Table view] Category:Part 55 Examination Related Material
MONTHYEARRS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023 Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations ML23013A1362022-12-0808 December 2022 Post Exam Comments and NRC Resolutions ML23247A0102022-11-0404 November 2022 Miscellaneous Exam Material ML23012A0772022-10-14014 October 2022 Administered Written Examination with Answer Key ML23013A0432022-10-14014 October 2022 Administered Operating Test ML23247A0032022-10-14014 October 2022 Handouts to Applicants ML23247A0082022-09-28028 September 2022 NRC Comments on Draft Licensee-Developed Written Exam ML23247A0072022-09-28028 September 2022 NRC Comments on Draft Licensee-Developed Operating Test ML23247A0092022-09-28028 September 2022 Final QA Related Forms ML23247A0062022-09-21021 September 2022 NRC Comments on Draft Licensee-Developed Operating Test Outlines ML23247A0012022-09-21021 September 2022 Final Written Examination and Operating Test Outlines ML23247A0022022-09-21021 September 2022 Modified Question Source Information ML23233A0472022-07-21021 July 2022 Draft Operating Test ML23247A0052022-07-21021 July 2022 Draft Written Examination ML23247A0042022-05-19019 May 2022 Draft Written Examination and Operating Test Outlines RS-22-045, Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations2022-03-25025 March 2022 Constellation Energy Generation, LLC, Response to NRC Regulatory Issue Summary 2022-01, Preparation and Scheduling of Operator Licensing Examinations ML21012A2692021-01-12012 January 2021 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2021 ML20329A4322020-11-17017 November 2020 Final Qa/Related Forms (Folder 1) ML20322A3502020-09-17017 September 2020 Final Operating Test (Sections a, B, and C) (Folder 3) ML20321A2792020-09-17017 September 2020 Final Written Examination with Answer Key (Form 401-5 Format) (Folder 3) ML20328A2792020-09-17017 September 2020 Handouts to Applicants (Folder 3) ML20329A1412020-09-17017 September 2020 NRC Comments on Draft Licensee-Developed Operating Test (Folder 2) ML20329A1812020-09-17017 September 2020 NRC Comments on Draft Licensee-Developed Operating Test Outlines (Folder 2) ML20328A2912020-09-17017 September 2020 NRC Comments on Draft Licensee-Developed Written Exam (Folder 2) ML20328A1622020-09-17017 September 2020 Final Written Examination and Operating Test Outlines (Folder 3) ML20329A4422020-09-17017 September 2020 Final Qa/Related Form - Form ES-401-6 (Folder 1) ML20329A2002020-08-26026 August 2020 Draft Written Examination and Operating Test Outlines (Folder 2) ML22103A2232020-08-26026 August 2020 Revised Draft Written Examination and Operating Test Outlines (2022 Regional Audit Corrective Action) (Folder 2) ML20329A3542020-07-22022 July 2020 Licensee 75-Day Letter Transmitting the Draft Written Exam and Operating Test Material (Folder 2) ML20329A2232020-07-22022 July 2020 Draft Written Examination (Folder 2) ML20329A2392020-07-22022 July 2020 Draft Operating Test (Section a, Section B, Section C) (Folder 2) ML19352D6572019-12-16016 December 2019 Announcement 0f Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2020 ML19323D1722019-11-18018 November 2019 R. 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Ginna Nuclear Power Plant - Senior Reactor and Reactor Operator Initial License Examinations ML21041A2942019-10-0303 October 2019 Original Questions for Modified Written Exam Questions ML20041E1772019-07-30030 July 2019 Handouts to Applicants (Folder 3) ML20024E6992019-07-23023 July 2019 Draft Written Examination (Folder 2) ML20024E7502019-07-23023 July 2019 NRC Comments on Draft Licensee-Developed Written Exam (Folder 2) ML20024E8202019-07-23023 July 2019 NRC Comments on Draft Licensee-Developed Operating Test (Folder 2) ML20024E2492019-07-23023 July 2019 Draft Operating Test (Section a, Section B, Section C) (Folder 2) RS-19-053, Response to NRC Regulatory Issue Summary 2019-02, Preparation and Scheduling of Operator Licensing Examinations2019-05-16016 May 2019 Response to NRC Regulatory Issue Summary 2019-02, Preparation and Scheduling of Operator Licensing Examinations ML18353A6082018-12-18018 December 2018 Senior Reactor Operator Retake License Examinations ML18344A5852018-12-10010 December 2018 R. E. Ginna - Reactor Operator Retake License Examinations ML19119A1472018-10-30030 October 2018 Final Qa/Related Forms (Folder 1) ML19156A1482018-08-27027 August 2018 Final Qa/Related Form - ES-201-1 (Folder 1) ML18233A5092018-08-21021 August 2018 Operator Licensing Operating Test Approval RS-18-057, Response to NRC Regulatory Issue Summary 2018-02, Preparation and Scheduling of Operator Licensing Examinations2018-04-25025 April 2018 Response to NRC Regulatory Issue Summary 2018-02, Preparation and Scheduling of Operator Licensing Examinations ML18005A4202018-01-0303 January 2018 Announcement of Generic Fundamentals Examination Section of the Written Operator Licensing Examination for 2018 ML17272A3242017-09-28028 September 2017 R. E. Ginna - Senior Reactor and Reactor Operator Initial License Examinations RS-17-070, Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations2017-05-0303 May 2017 Response to NRC Regulatory Issue Summary 2017-03, Preparation and Scheduling of Operator Licensing Examinations ML17114A2862017-04-21021 April 2017 Miscellaneous Exam Material (Folder 1) 2023-06-16
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FIG-1.0 FIGURE MIN SUBCOOLING PAGE Approval Authority: GS-Shift Operations FIGURE MIN SUBCOOLING NOTE:
Subcooling Margin Saturation Temperature From Figure Below[-] Core Exit T/C Indication RCS PRESSURE (PSIG) 00200 1 of 1 2500, _,,r,,--,.-7 --+' -,--
+-i- ~---,-,---;-.-.,....,-,-.,..-;-,--,--,-,-,--.-,-,--,-,.-,-,--,---,-,--,--,-.--,-,--,-,-,--,-,......,.._
2400 --l--,f--+--f-l-+-+-+--+-+-+-+-+-+-i-+---f-!-+-l-1-+-+-+--+-+-+-+-!---'--!--l--!
2300 2200 2100 t+~s!!~~!~~e!~~t!~e!~s!!3sf~s~1a~e1~s!1~~!~~f!~~tilJ=..... ~+-;~~=+~~~~~~~~~~:t1j~
2000 1900 1800 1700 1600 1=1:=l=l=l:=S=:l=l=E~=!:=i~ t=:!=U=!=l:==1=!=!-=~ali+/-lJJ~LLd~::ti:::a~:!:::l+/-.:1 1500 1400 HEBBB§3~t ----.-i 1300 -l=+=!=~+=+=!=~::=:-+__:__~-~__'..._:_____..:!.::j:+.:~:!.:::+=t:=1=+=-!=+::::-=+=J/J',.=/::::;=+=;:::::H~-+-1 1200 +-i,-+-+-t-+-+-+--t--t----t-t--'-i-r--J-'--+--+-r--+-'----:-+-+--l--i--+-+--s-+--+-f--+-l#'---!-+--+-'-+-+-'-""--'-+--,---:L..-{I L
1100..J:=1++=1=+==!=!+:.r-:++=!=t=::l=i-+:!::+.=:=+:+=.!:=P=t=:!::+::::J=+=l==l=q,ff=µ~=-l--l-:l~---=!___!_+-1=--i--q 1000 900 800 ff~~g,~§§E§J~;E:jm~U=D.::a=!~~~l..!:i+/-.:EE:E,fr~E:.::J.d~
700 600 500 400 300 200 10
- f~~~~i~~i~i~~~~~+/-g~~~~~~i~~~~~~:+/-+/-;;~~~~i!i~~;~~~~;~~:;:~d 200 250 300 350 400 450 500 550 600 650 700 CORE EXIT SATURATION TEMPERATURE (°F)
PLANT SHUTDOWN FROM HOT SHUTDOWN TO COLD CONDITIONS 0-2.2 Revision 171 Page 79 of93 iii Q. -
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Page 1 of 1, Full Range RCS Pressure Temperature Cooldown Curve 2500 <T-
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RCS PRESURE
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- N~RMAL 2250 NCREMENTS.so PSIG
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I I 200 300 400 TEMPERATURE (°F) 500 SATURATION CURVE PSIG I I,
TEMPERATURE INCREMENTS 20°F 600 700
DC Sources - MODES 1, 2, 3, and 4 3.8.4 3.8 ELECTRICAL POWER SYSTEMS 3.8.4 DC Sources - MODES 1, 2, 3, and 4 LCO 3.8.4 The Train A and Train B DC electrical power sources shall be OPERABLE.
APPLICABILITY:
MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A.
One DC electrical power A.1 Restore DC electrical power 2 hours source inoperable.
source to OPERABLE status.
OR In accordance with the Risk Informed Completion Time Program B.
Required Action and B.1 Be in MODE 3.
6 hours Associated Completion Time of Condition A not AND met.
B.2 Be in MODE 5.
36 hours C.
Both DC electrical power C.1 Enter LCO 3.0.3.
Immediately sources inoperable.
R.E. Ginna Nuclear Power Plant 3.8.4-1 Amendment 150
I DC Sources - MODES 1, 2, 3, and 4 3.8.4 SURVEILLANCE REQUIREMENTS SR 3.8.4.1 SR3.8.4.2 SR3.8.4.3 SURVEILLANCE Verify battery terminal voltage is 2-: 129 V on float charge.
- NOTE-
- 1.
SR 3.8.4.3 may be performed in lieu of SR 3.8.4.2.
- 2.
This Surveillance shall not be performed in MODE 1, 2, 3, or 4.
Verify battery capacity is adequate to supply, and maintain in OPERABLE status, the required emergency loads for the design duty cycle when subjected to a battery service test.
- NOTE-This Surveillance shall not be performed in MODE 1, 2, 3, or 4.
Verify battery capacity is 2': 80% of the manufacturer's rating when subjected to a performance discharge test or a modified performance discharge test.
R.E. Ginna Nuclear Power Plant 3.8.4-2 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program 12 months when battery shows degradation, or has reached 85% of expected life with capacity < 100% of manufacturer's rating AND 24 months when battery has reached 85% of the expected life with capacity 2': 100% of manufacturer's rating Amendment No.130
3.8 ELECTRICAL POWER SYSTEMS 3.8.6 Battery Cell Parameters Battery Cell Parameters 3.8.6 LCO 3.8.6 Battery cell parameters for Train A and Train B batteries shall be within limits.
APPLICABILITY:
MODES 1, 2, 3, and 4, When associated DC electrical power sources are required to be OPERABLE by LCO 3.8.5, "DC Sources - MODES 5 and 6.
11 ACTIONS
- ----------------------*r---------------------------------
- NOTE-Separate Condition entry is allowed for each battery.
CONDITION REQUIRED ACTION COMPLETION TIME A.
One or more batteries A.1 Declare associated battery Immediately with one or more battery inoperable.
cell parameters not within limits.
SURVEILLANCE REQUIREMENTS SR 3.8.6.1 SR 3.8.6.2 SR3.8.6.3 SR 3.8.6.4 SURVEILLANCE Verify electrolyte level of each connected battery cell is above the top of the plates and not overflowing.
Verify the float voltage of each connected battery cell is> 2.07 V.
Verify specific gravity of the designated pilot cell in each battery is ~ 1.195.
Verify average electrolyte temperature of the designated pilot cell in each battery is ~ 55°F.
R.E. Ginna Nuclear Power Plant 3.8.6-1 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No.122
SR 3.8.6.5 SR3.8.6.6 SURVEILLANCE Verify average electrolyte temperature of every fifth cell of battery is~ 55°F.
Verify specific gravity of each connected battery cell is:
- a.
Not more than 0.020 below average of all connected cells, and
- b.
Average of all connected cells is ~ 1.195.
R.E. Ginna Nuclear Power Plant 3.8.6-2 Battery Cell Parameters 3.8.6 FREQUENCY In accordance with the Surveillance Frequency Control Program In accordance with the Surveillance Frequency Control Program Amendment No. 122}}