ML17069A404

Op Test Retake - Draft - Outlines (Folder 2), (Facility Letter Dtd - 11/22/2016)

ML17069A404
Person / Time
Site:	Calvert Cliffs
Issue date:	11/22/2016
From:	NRC Region 1
To:	Exelon Generation Co
Shared Package
ML16326A203	List: IR 05000317/2017301 ML17034A384 ML17069A403 ML17069A404 ML17069A405 ML17069A406 ML17069A407 ML17072A398 ML17090A364
References
U01967
Download: ML17069A404 (4)

Text

Mark 0. Flaherty Plant Manager

d .

Exelon Generation., Calvert Clifts Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby. MD 20657 410 495 5205 Oft ice 443 534 5475 Mobile www.exeloncorp.cum mark.flaher-ty:cvexelon corn November 22, 2016 U. S. Nuclear Regulatory Commission ATTN: Mr. D. H. Dorman, Regional Administrator Region I 2100 Renaissance Boulevard King of Prussia, PA 19406 Calvert Cliffs Nuclear Power Plant Unit Nos. 1 & 2; Docket Nos. 50-317 & 50-318 Facility Operating License Nos. DPR-53 and DPR-69

Subject:

Submittal of Initial Operator License Examination Outline Enclosed are the examination outlines supporting the initial license exam scheduled for the week of February 9, 2016 at Calvert Cliffs Nuclear Power Plant.

This submittal includes all appropriate examination standard forms and outlines in accordance with NUREG-1021, "Operator Licensing Examination Standards for Power Reactors,

Revision 10.

In accordance with NUREG-1021, Revision 10, Section ES-201, "Initial Operator Licensing Examination Process, please ensure that these materials are withheld from public disclosure until after the examinations are complete.

There are no regulatory commitments contained in this letter.

Should you have questions regarding this matter, please contact Mr. Larry D. Smith at (410) 495-5219. For questions concerning the examination materials, please contact Mr. Al Kelly at (410) 495-2289.

Respectfully,

~{)~

Mark D. Flaherty Plant Manager MDF/PSF/psf

Enclosures:

Examination Security Agreements (Form ES-201-3)

Administrative Topics Outline(s) (Form ES-301-1)

Control Room/In-plant Systems Outline (Form ES-301-2)

Completed Checklists:

Examination Outline Quality Checklist (Form ES-201-2)

Mr. D. H. Dorman November 22, 2016 Page 2 cc: (With Enclosures) (via FedEx)

P. Presby, Examiner, NRC Region I (Without Enclosures)

Chief, NRC Operator Licensing Branch NRC Resident Inspector, Calvert Cliffs

ES-301 Administrative Topics Outline Form ES-301-1 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: February 2017 Exam Level: SRO-I Operating Test No.: 2017 Type Administrative Topic (see Note) Describe activity to be performed Code*

Review and approve a completed Surveillance Test Procedure.

SRO-Adm in- I: Perform the initial review of a completed STP 210.003.

Conduct of Operations N,R 2.1.7 -Ability to evaluate plant performance and make operational judgments based on operating characteristics, reactor behavior, and instrument interpretation. (4.7)

Verify Estimated Critical Position SRO-Admin-2: Review and Approve an Estimated Critical Conduct of Operations M,R Condition using approved plant procedures ..

2. I .25 - Ability to interpret reference materials, such as graphs, curves, tables, etc. (4.2)

Establish Initial Conditions for STP O-SA-1 SRO-Admin-3: Establish initial plant conditions for and approve Equipment Control D,R performance of an STP 210.001 2.2.12 Knowledge of surveillance procedures (4. I)

Review and approve a gaseous waste discharge permit.

SRO-Admin-4: Determine adequacy and quality of waste Radiation Control N,R discharge permit.

2.3.11 Ability to control radiation releases. (4.3)

Determine the appropriate emergency response actions per the ERP IP SRO-Admin-5: Determine appropriate emergency response actions per the ERPIP while maintaining an overview of plant Emergency Procedures I Plan M,R conditions 204.097 2.4.38 Ability to take actions called for in the facility emergency plan, including supporting or acting as emergency coordinator if required. (4.4)

NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (:S 3 for ROs; :S 4 for SROs & RO retakes) 1 actual (N)ew or (M)odified from bank (~ I) 4 actual (P)revious 2 exams (:S I; randomly selected) 0 actual

ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 Facility: Calvert Cliffs Nuclear Power Plant Date of Examination: Feburary 20I 7 Exam Level: SRO-I Operating Test No.: 2017 Control Room Systems@ (7 for SRO-I)

Type Safety System I JPM Title Code* Function

a. Sim-I: Dropped CEA during S/U 00 l .A2.03 Ability to predict impact of malfunction and use procedures to control or mitigate a ANSL I misaligned CEA (3.5, 4.2)

b. Sim-2: Override shut a PORV 002.A2.0l Loss of coolant inventory (4.3, 4.4) ADSL 2

c. Sim-3: Depressurize RCS to fill PZR in EOP-5 NSEN 3 010.A4.0 I Ability to manually operate and/or monitor PZR Spray valves (3 .7, 3 .5)

d. Sim-4: Loss ofSRW pump 076.A4.0J Ability to manually operate and/or monitor in the control room the SRW pumps. (2.9, ANS 4 (Secondary) 2.9)

e. Sim-5: Respond to a Faulted S/G ADS 4 (Primary) 035.A2.0l Faulted or ruptured S/Gs (4.5, 4.6)

f. Sim-6: Shift 13 IRU Power Supply 027 A4.0l Ability to manually operate and/or monitor in the control room the IRU controls. (3.3, NSEN 5 3.3)

g. Sim-7: Energize a 480V Load Center 062.A4.0l Ability to manually operate and/or monitor 480V breakers from the Control Room (3.3, DS 6 3.1)

In-Plant Systems@ 3 for SRO-I

h. Plant-I: Control Steam Flow from ADV's locally 039.A2.04 Ability to predict and use procedures to control or mitigate malfunctioning steam EN 4 (Primary) dump(3.4, 3.7)

i. Plant-2: Locally control AFW flow during EOP-7 E06 EA 1.1 Ability to operate and/or monitor components and functions of control and safety EN 4 (Secondary) systems as they apply to the Loss ofFeedwater (4.0, 3.9)

j. Plant-3: Fill SR W and CC Head Tanks during CR Evacuation 008.A2.02 Ability to predict the impact of low CCW surge tank level and based on those EDR 8 predictions, use procedures to correct, or mitigate the consequences of those malfunctions (3.2,3.5)

All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room.

• Type Codes Criteria for SRO-I Required Actual (A)lternate path 4-6 4 (C)ontrol room - 0 (D)irect from bank :S 8 4 (E)mergency or abnormal in-plant 2: I 3 (EN)gineered safety feature - 2 (L)ow-Power I Shutdown  :::: I 2 (N)ew or (M)odified from bank including I (A)  :::: 2 6 (P)revious 2 exams :S 3 (randomly selected) 0 (R)CA 2: I I (S)imulator - 7