Text

Enclosures to Letter Regarding Validation of Proposed Revision to Operator Initial Licensing Examination Process
	ML19178A400
Person / Time
Issue date:	07/25/2019
From:	Chris Miller; Division of Inspection and Regional Support
To:	;
	Buchanan T, NRR/DIRS, 301-415-2789
Shared Package
ML19177A244	List: ML19177A248; ML19177A340; ML19177A341; ML19178A126; ML19178A400;
References
	Download: ML19178A400 (31)
	v • d • e

ES-401 U PREPARING INITIAL SITE-SPECIFIC WRITTEN EXAMINATIONS A. Purpose This standard specifies the requirements, procedures, and guidelines for preparing site-specific written examinations for the initial licensing of reactor operator (RO) and senior reactor operator (SRO) applicants at power reactor facilities licensed under Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Domestic Licensing of Production and Utilization Facilities.

B. Background The content of the written licensing examinations for ROs and SROs is dictated by 10 CFR 55.41, Written Examination: Operators, and 10 CFR 55.43, Written Examination:

Senior Operators, respectively. Each examination shall contain a representative selection of questions concerning the knowledge and abilities (K/As) and skills needed to perform duties at the desired license level. Both the RO and SRO examinations will sample the 14 items specified in 10 CFR 55.41(b), and the SRO examination will also sample the 7 additional items specified in 10 CFR 55.43(b). Given that senior reactor operator-upgrade (SRO-U) applicants previously passed an RO licensing examination covering the topics specified in 10 CFR 55.41(b), they may apply for a waiver of the RO portion of the SRO written examination pursuant to 10 CFR 55.47, Waiver of Examination and Test Requirements.

(Refer to ES-204, Processing Excusals and Waivers Requested by Reactor Operator and Senior Reactor Operator Applicants.)

Except as noted in Section D.1.b of this examination standard, NUREG-1122, Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Pressurized Water Reactors, and NUREG-1123, Knowledge and Abilities Catalog for Nuclear Power Plant Operators: Boiling Water Reactors, available in the Agencywide Documents Access and Management System (ADAMS), provide the basis for developing content-valid operator licensing examinations.

Each K/A stem statement has been linked to an applicable item number in 10 CFR 55.41 and/or 10 CFR 55.43. Preparing the license examination using the appropriate K/A catalog, in conjunction with the instructions in this NUREG-series report, will ensure that the examination includes a representative sample of the items specified in the regulations.

C. Responsibilities

1. Facility Licensee The facility licensee will perform the following activities, as applicable, depending on the examination arrangements confirmed with the U.S. Nuclear Regulatory Commissions ES-401, Page 1 of 52 Enclosure 1

2. NRC Regional Office The NRCs regional office will perform the following activities:

a. Ensure that the outline and examinations are prepared in accordance with Section D.

b. Ensure that the examinations are reviewed for quality as described in Section E.

c. Meet with the facility licensee, when and as appropriate, to pre-review the examination(s) in accordance with ES-201.

D. Examination Preparation

1. Develop the Outline Develop the written examination outline in accordance with the following general instructions:

a. Select the appropriate examination outline model for the licensing examination being developed, as follows:

For RO applicants, use only the left side of Form ES-401-1, BWR Examination Outline, or Form ES-401-2, PWR Examination Outline, depending on the facility design.

For SRO-instant (SRO-I) applicants, use both the RO and SRO portions of Form ES-401-1 (BWR) or Form ES-401-2 (PWR), depending on the facility design.

For SRO-U applicants, use both sides of Form ES-401-1 (BWR) or Form ES-401-2 (PWR) unless the RO portion is waived in accordance with ES-204.

b. Systematically and randomly select specific K/A statements (e.g., K1.03 or A2.11) from NUREG-1122 (for PWRs) or NUREG-1123 (for BWRs) to complete each of the four tiers (i.e., Tier 1, Emergency and Abnormal Plant Evolutions; Tier 2, Plant Systems; Tier 3, Generic Knowledge and Abilities; and Tier 4, Theory") of the applicable examination outline. Use the latest revision of the K/A catalog (NUREG-1122 or NUREG-1123) available at the time the facility licensee requests the written examination outline. To maintain examination consistency, the facility licensees site-specific K/A list shall not be used in place of the NRCs K/A catalog. If the latest revision of the K/A catalogs includes emergency and/or abnormal plant evolutions or plant systems that are not represented on Form ES-401-1 (BWR) or Form ES-401-2 (PWR), contact the program office to determine to which tier and group the topics in questions should be added before sampling. Attachment 1 provides an example of an acceptable methodology for randomly selecting K/As within the defined structure of the examination outline to achieve as broad a sample as possible. Other methodologies may be used provided that they meet the following criteria:

ES-401, Page 3 of 52

Are reproducible and comprehensible and yield an examination outline that is free of bias.

Adhere to the applicable examination model.

Minimize the number of K/As related to any particular system or evolution (i.e., every system or evolution in the group should be sampled once before selecting a second K/A for any system or evolution).

Sample at the specific K/A statement level.

Because the NRCs K/A catalogs are based on generic job and task analyses and not all facilities are the same, inapplicable or inappropriate K/A statements can be eliminated by (1) discarding randomly selected K/As during the outline development process or (2) prescreening the entire K/A catalog to eliminate inappropriate K/As before beginning the random selection process. Licensees that prescreen K/As shall provide the NRC regional office with a list of K/As that should be eliminated, along with a basis for eliminating each K/A, before the NRC develops the written examination outline. Refer to the remainder of this section for specific requirements and guidance on K/A elimination.

The topics for the generic K/A category in Tier 1 (i.e., Column G on Forms ES-401-1 and ES-401-2) shall be selected from Section 2, Generic Knowledge and Abilities, of the applicable K/A catalog. The topics for the generic K/A category in Tier 2 (i.e., Column G on Forms ES-401-1 and ES-401-2) shall be selected from Section 2, Generic Knowledge and Abilities, or Section 5, Components, of the applicable K/A catalog. However, only those topics that are relevant to the selected evolution or system shall be included; therefore, generic K/As for Tiers 1 and 2 for both RO and SRO examinations should be randomly selected from the following set:

2.1.7, 2.1.19, 2.1.20, 2.1.23, 2.1.25, 2.1.27, 2.1.28, 2.1.30, 2.1.31, 2.1.32, 2.2.3, 2.2.4, 2.2.12, 2.2.22, 2.2.25, 2.2.36, 2.2.37, 2.2.38, 2.2.39, 2.2.40, 2.2.42, 2.2.44, 2.4.1, 2.4.2, 2.4.3, 2.4.4, 2.4.6, 2.4.8, 2.4.9, 2.4.18, 2.4.20, 2.4.21, 2.4.30, 2.4.31, 2.4.34, 2.4.35, 2.4.41, 2.4.45, 2.4.46, 2.4.47, 2.4.49, and 2.4.50, for Section 2 K/As

All K/As with an importance rating of 2.5 or above, for Section 5 K/As (Tier 2 only)

All other generic K/As for Tiers 1 and 2 may be eliminated before or after the random selection process, and examinations for single-unit licenses may also eliminate K/As 2.2.3 and 2.2.4.

Examination authors and reviewers should ask themselves the following questions to help determine whether a K/A statement is appropriate for testing:

Is the subject K/A relevant (i.e., is the system, component, process, procedure, or event installed, in use, or possible) at the subject facility?

Is the importance rating of the K/A equal to, or greater than, 2.5 for the license level of the proposed examination, or is there a site-specific priority that justifies keeping the K/A if its importance rating is below 2.5?

ES-401, Page 4 of 52

Is it possible to prepare a psychometrically sound question related to the subject K/A?

ES-401, Page 4 of 52

A number of the generic K/As in Section 2 of the catalogs are specifically linked to one or more topics specified in 10 CFR 55.43(b), and all of the Category A2, AA2, and EA2 K/A statements are (or, in the case of NUREG-1123, should be) similarly linked. Consequently, the K/As for the SRO examination will be drawn from those K/A categories (denoted by Columns A2 and G in the SRO-only section of the applicable examination outline) and from all K/A categories related to the fuel-handling facilities, which are specifically identified for sampling in 10 CFR 55.43(b)(7). The fact that a K/A is linked to both 10 CFR 55.41 and 10 CFR 55.43 does not mean that the K/A cannot be used to develop an SRO-only question, nor does it exclude the K/A from sampling on the RO examination. However, to be used on the SRO-only section of an examination, a question developed from a K/A linked to both 10 CFR 55.41 and 10 CFR 55.43 should test at the level of the 10 CFR 55.43(b) item number(s) that the K/A is linked to, or it should test at a level that is unique to the SRO job position as determined from the facilitys learning objectives. K/A topics linked to 10 CFR 55.41(b) might also be appropriate for developing SRO-level questions if the questions developed evaluate K/As at a 10 CFR 55.43(b) level or at a level that is unique to the SRO job position as determined from the facilitys learning objectives.

Attachment 2 provides additional guidance that may be used when developing SRO-only questions. Use of this guidance is not a requirement.

c. After completing the outline, check the selected K/As for balance of coverage within and across the four tiers. Ensure that every applicable K/A category is sampled at least twice within each of the four tiers so that a valid sample will likely be maintained in the event that some questions are deleted as a result of post-examination comments (except as allowed by Note 1 on Forms ES-401-1 and ES-401-2).

Similarly, ensure that no emergency/abnormal plant evolution, system, or K/A category is oversampled (i.e., avoid selecting more than two K/A topics from a given system unless they relate to plant-specific priorities). Make any adjustments that might be necessary by systematically and randomly selecting replacement K/A statements. When performing these checks, the SRO exam, which consists of 75 RO questions and 25 SRO-only questions, is considered as a 100-question test overall and adjustments will be made to ensure balance of coverage and appropriate sampling. Also check the overall balance of the entire licensing examination, including the walkthrough and the dynamic simulator test, and make any necessary adjustments. Document and justify all changes on Form ES-401-4 and submit the documentation with the completed/revised outline.

d. The NRC-developed outline will be sent to the facility for review in accordance with ES-201. A facility supervisor or manager shall independently review facility revisions to the previously approved outlines before the outlines are submitted to the NRCs regional office for approval in accordance with ES-201.

e. The NRC chief examiner will ensure that any revision to the outline is independently reviewed and provide comments and recommended changes, as appropriate. The NRC chief examiner shall review all K/A rejections and changes to ensure that they are unbiased. The chief examiner shall also review and approve the site-specific item or topic substitutions. Refer to Section C.3 of ES-201 for additional guidance on outline reviews.

ES-401, Page 6 of 52

2. Facility Peer Review As a final check of the examinations technical accuracy, facility management should consider administering the examination (under security agreements) to one or more licensed personnel who were previously uninvolved in developing the examination. In light of examination security concerns, the NRC discourages the use of certain individuals (e.g., the applicants supervisors or coworkers) to validate the examination. Any comments made and problems identified during the trial administration shall be discussed with the NRC chief examiner and resolved before the examination is administered to the license applicants. The intent of the review is to identify and correct deficiencies that may affect the validity of the examination.

E. Attachments/Forms Example Systematic Sampling Methodology Clarification Guidance for SRO-Only Questions Form ES-401-1 BWR Examination Outline Form ES-401-2 PWR Examination Outline Form ES-401-3 Common Examination Outline Form ES-401-4 Record of Rejected K/As Form ES-401-5 Sample Written Examination Question Worksheet Form ES-401-6 Written Examination Quality Checklist Form ES-401-7 Site-Specific RO Written Examination Cover Sheet Form ES-401-8 Site-Specific SRO Written Examination Cover Sheet Form ES-401-9 Written Examination Review Worksheet ES-401, Page 14 of 52

The following process, which uses Form ES-401-1, BWR Examination Outline, for illustration, may be used for each group in Tiers 1 and 2 of the reactor operator (RO) examination outline.

1. Review each group and delete those items (emergency/abnormal plant evolutions (E/APEs) for Tier 1 and systems for Tier 2) that clearly do not apply to the facility for which the examination is being written; be prepared to explain the basis for the deletions to the U.S. Nuclear Regulatory Commission (NRC) chief examiner. Add any operationally important systems or E/APEs that pertain to the facility but are not included in the generic lists on Form ES-401-1.

2. Sequentially number the remaining items in the group and sequentially annotate the same number of tokens. Assuming that 1 of the 21 E/APEs in Tier 1, Group 1, was deleted in Step 1, there should be 20 tokens, numbered from 1 to 20, remaining.

a. Because the number of items remaining in the group (in this case 20) is the same as the required number of points for the group specified in the right-hand column of the examination outline, each item in the group would be sampled one time.

b. If the number of items remaining in the group is smaller than the required number of points for the group (e.g., Tier 2, Group 1, has 23 items but requires 26 points),

sample each item once and determine the rest of the sample by randomly selecting and removing tokens (in this case 3 of 23) until the required total number of points (26) is reached. Update Form ES-401-1 to note the selected items.

c. If the number of items remaining in the group is larger than the required number of points for the group (e.g., Tier 1, Group 2, has 20 items but only requires 7 points), randomly select and remove the required number of tokens (7) and note them on Form ES-401-1.

3. After selecting the topics to be sampled in each group as described in Step 2, count the number of knowledge and ability (K/A) categories in the group (e.g., six for each group in Tier 1 (i.e., K1, K2, K3, A1, A2, and G)) and sequentially annotate the same number of tokens (in this case six). For each E/APE (and system) selected in Step 2, randomly select and remove a token and note the K/A category on Form ES-401-1. If the E/APE (or system) was sampled more than once in accordance with Step 2.a, randomly select a second K/A category. If the selected K/A category contains no K/A statements that have an importance rating above 2.5, systematically select another K/A category, unless the lower importance is justified based on plant-specific priorities. Then replace all tokens in the container and repeat the process for every selected item in each group.

4. Use a similar method to randomly select from among the K/A statements under each selected K/A category. Describe each K/A topic in the space provided on Form ES-401-1 and enter the importance rating. K/As that have importance ratings of less than 2.5 can be used if they are justified based on plant priorities; the facility contact should be prepared to explain the basis to the NRC chief examiner.

For Tier 3 (plantwide generics) of the examination outline, randomly select K/As from Section 2 of the NRCs K/A catalog so that each of the four K/A categories (i.e., Conduct of Operations, Equipment Control, Radiation Control, and Emergency Procedures/Plan) has at least two items (one radiation control K/A is allowed if it is replaced by another Tier 3 category K/A).

For Tier 4 (Theory) of the examination outline, randomly select K/As from Section 6 of the NRCs K/A catalog so that both K/A categories, Reactor Theory and Thermodynamics, has three items each.

ES-401, Page 14 of 52

ES-401 BWR Examination Outline Form ES-401-1 Facility: Date of Exam:

Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 20 7 Emergency and N/A N/A 2 6 3 Abnormal Plant Evolutions Tier Totals 26 10 1 26 5 2.

Plant 2 11 3 Systems Tier Totals 37 8

3. Generic Knowledge and Abilities 1 2 3 4 6 1 2 3 4 7 Categories 2 2 1 1 Reactor Theory Thermodynamics

4. Theory 6 3 3 Note: 1. Ensure that at least two topics from every applicable K/A category are sampled within each tier of the RO and SRO-only outline sections (i.e., except for the Tier 3 radiation control and emergency plan categories in the RO portion of the examination and one category in Tier 3 of the SRO-only section, the Tier Totals in each K/A category shall not be less than two).

2. The point total for each group and tier in the proposed outline must match that specified in the table. The final point total for each group and tier may deviate by +/-1 from that specified in the table based on NRC revisions.

The final RO exam must total 75 points, and the SRO-only exam must total 25 points.

3. Systems/evolutions within each group are identified on the outline. Systems or evolutions that do not apply at the facility should be deleted with justification. Operationally important, site-specific systems/evolutions that are not included on the outline should be added. Refer to Section D.1.b of ES-401 for guidance regarding the elimination of inappropriate K/A statements.

4. Select topics from as many systems, evolutions, and subjects as possible. Sample every system or evolution in the group before selecting a second topic for any system or evolution.

5. Tier 4 topics selected must sample different theory subjects located within Section 6 of the K/A catalog. For example, only one question may test Reactor Theory subject 292001, Neutrons.

6. Absent a plant-specific priority, only those K/As having an importance rating (IR) of 2.5 or higher. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

7. Select SRO topics for Tiers 1 and 2 from the shaded systems and K/A categories.

8. The generic (G) K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A catalog. For the Tier 2 questions on the RO portion of the examination, K/As shall also be selected from Section 5 of the K/A catalog.

The topics selected must be relevant to the applicable evolution or system. Refer to Section D.1.b of ES-401 for the applicable K/As.

9. On the following pages, enter the K/A numbers, a brief description of each topic, the topics IRs for the applicable license level, and the point totals (#) for each system and category. Enter the group and tier totals for each category in the table above. If fuel-handling equipment is sampled in a category other than Category A2 or G* on the SRO-only exam, enter it on the left side of Column A2 for Tier 2, Group 2. (Note 1 does not apply.)

Use duplicate pages for RO and SRO-only exams.

10. For Tier 3, select topics from Section 2, and enter the K/A numbers, descriptions, IRs, and point totals (#) on Form ES-401-3. Limit SRO selections to K/As that are linked to 10 CFR 55.43.

11. For Tier 4, select topics from Section 6 of the K/A catalog and enter the K/A numbers, descriptions, IRs, and point totals(#) on Form ES-401-3. Tier 4 is limited to the RO portion of the examination only.

G* Generic K/As

These systems/evolutions must be included as part of the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan. They are not required to be included when using earlier revisions of the K/A catalog.

- These systems/evolutions may be eliminated from the sample (as applicable to the facility) when Revision 3 of the K/A catalog is used to develop the sample plan.

Enclosure 2

ES-401 2 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 1 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

295001 (APE 1) Partial or Complete Loss of Forced Core Flow Circulation / 1 & 4 295003 (APE 3) Partial or Complete Loss of AC Power / 6 295004 (APE 4) Partial or Total Loss of DC Power / 6 295005 (APE 5) Main Turbine Generator Trip /

3 295006 (APE 6) Scram / 1 295016 (APE 16) Control Room Abandonment

/7 295018 (APE 18) Partial or Complete Loss of CCW / 8 295019 (APE 19) Partial or Complete Loss of Instrument Air / 8 295021 (APE 21) Loss of Shutdown Cooling /

4 295023 (APE 23) Refueling Accidents / 8 295024 High Drywell Pressure / 5 295025 (EPE 2) High Reactor Pressure / 3 295026 (EPE 3) Suppression Pool High Water Temperature / 5 295027 (EPE 4) High Containment Temperature (Mark III Containment Only) / 5 295028 (EPE 5) High Drywell Temperature (Mark I and Mark II only) / 5 295030 (EPE 7) Low Suppression Pool Water Level / 5 295031 (EPE 8) Reactor Low Water Level / 2 295037 (EPE 14) Scram Condition Present and Reactor Power Above APRM Downscale or Unknown / 1 295038 (EPE 15) High Offsite Radioactivity Release Rate / 9 600000 (APE 24) Plant Fire On Site / 8 700000 (APE 25) Generator Voltage and Electric Grid Disturbances / 6 K/A Category Totals: Group Point Total: 20/7

ES-401-1 3 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Emergency and Abnormal Plant EvolutionsTier 1/Group 2 (RO/SRO)

E/APE # / Name / Safety Function K1 K2 K3 A1 A2 G* K/A Topic(s) IR #

295002 (APE 2) Loss of Main Condenser Vacuum / 3 295007 (APE 7) High Reactor Pressure / 3 295008 (APE 8) High Reactor Water Level / 2 295009 (APE 9) Low Reactor Water Level / 2 295010 (APE 10) High Drywell Pressure / 5 295011 (APE 11) High Containment Temperature (Mark III Containment only) / 5 295012 (APE 12) High Drywell Temperature /

5 295013 (APE 13) High Suppression Pool Temperature. / 5 295014 (APE 14) Inadvertent Reactivity Addition / 1 295015 (APE 15) Incomplete Scram / 1 295017 (APE 17) Abnormal Offsite Release Rate / 9 295020 (APE 20) Inadvertent Containment Isolation / 5 & 7 295022 (APE 22) Loss of Control Rod Drive Pumps / 1 295029 (EPE 6) High Suppression Pool Water Level / 5 295032 (EPE 9) High Secondary Containment Area Temperature / 5 295033 (EPE 10) High Secondary Containment Area Radiation Levels / 9 295034 (EPE 11) Secondary Containment Ventilation High Radiation / 9 295035 (EPE 12) Secondary Containment High Differential Pressure / 5 295036 (EPE 13) Secondary Containment High Sump/Area Water Level / 5 500000 (EPE 16) High Containment Hydrogen Concentration / 5 K/A Category Point Totals: Group Point Total: 6/3

ES-401 4 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 1 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

203000 (SF2, SF4 RHR/LPCI)

RHR/LPCI: Injection Mode 205000 (SF4 SCS) Shutdown Cooling 206000 (SF2, SF4 HPCIS)

High-Pressure Coolant Injection 207000 (SF4 IC) Isolation (Emergency) Condenser 209001 (SF2, SF4 LPCS)

Low-Pressure Core Spray 209002 (SF2, SF4 HPCS)

High-Pressure Core Spray 211000 (SF1 SLCS) Standby Liquid Control 212000 (SF7 RPS) Reactor Protection 215003 (SF7 IRM)

Intermediate-Range Monitor 215004 (SF7 SRMS) Source-Range Monitor 215005 (SF7 PRMS) Average Power Range Monitor/Local Power Range Monitor 217000 (SF2, SF4 RCIC) Reactor Core Isolation Cooling 218000 (SF3 ADS) Automatic Depressurization 223002 (SF5 PCIS) Primary Containment Isolation/Nuclear Steam Supply Shutoff 239002 (SF3 SRV) Safety Relief Valves 259002 (SF2 RWLCS) Reactor Water Level Control 261000 (SF9 SGTS) Standby Gas Treatment 262001 (SF6 AC) AC Electrical Distribution 262002 (SF6 UPS) Uninterruptable Power Supply (AC/DC) 263000 (SF6 DC) DC Electrical Distribution 264000 (SF6 EGE) Emergency Generators (Diesel/Jet) EDG 300000 (SF8 IA) Instrument Air 400000 (SF8 CCS) Component Cooling Water 510000 (SF4 SWS*) Service Water (Normal and Emergency)

K/A Category Point Totals: Group Point Total: 26/5

ES-401 5 Form ES-401-1 ES-401 BWR Examination Outline Form ES-401-1 Plant SystemsTier 2/Group 2 (RO/SRO)

System # / Name K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* K/A Topic(s) IR #

201001 (SF1 CRDH) CRD Hydraulic 201002 (SF1 RMCS) Reactor Manual Control 201003 (SF1 CRDM) Control Rod and Drive Mechanism 201004 (SF7 RSCS) Rod Sequence Control 201005 (SF1, SF7 RCIS) Rod Control and Information 201006 (SF7 RWMS) Rod Worth Minimizer 202001 (SF1, SF4 RS) Recirculation 202002 (SF1 RSCTL) Recirculation Flow Control 204000 (SF2 RWCU) Reactor Water Cleanup 214000 (SF7 RPIS) Rod Position Information 215001 (SF7 TIP) Traversing In-Core Probe 215002 (SF7 RBMS) Rod Block Monitor 216000 (SF7 NBI) Nuclear Boiler Instrumentation 219000 (SF5 RHR SPC) RHR/LPCI:

Torus/Suppression Pool Cooling Mode 223001 (SF5 PCS) Primary Containment and Auxiliaries 226001 (SF5 RHR CSS) RHR/LPCI: Containment Spray Mode 230000 (SF5 RHR SPS) RHR/LPCI:

Torus/Suppression Pool Spray Mode 233000 (SF9 FPCCU) Fuel Pool Cooling/Cleanup 234000 (SF8 FH) Fuel-Handling Equipment 239001 (SF3, SF4 MRSS) Main and Reheat Steam 239003 (SF9 MSVLCS) Main Steam Isolation Valve Leakage Control 241000 (SF3 RTPRS) Reactor/Turbine Pressure Regulating 245000 (SF4 MTGEN) Main Turbine Generator/Auxiliary 256000 (SF2 CDS) Condensate 259001 (SF2 FWS) Feedwater 268000 (SF9 RW) Radwaste 271000 (SF9 OG) Offgas 272000 (SF7, SF9 RMS) Radiation Monitoring 286000 (SF8 FPS) Fire Protection 288000 (SF9 PVS) Plant Ventilation 290001 (SF5 SC) Secondary Containment 290003 (SF9 CRV) Control Room Ventilation 290002 (SF4 RVI) Reactor Vessel Internals 51001 (SF8 CWS*) Circulating Water K/A Category Point Totals: Group Point Total: 11/3

ES-401 PWR Examination Outline Form ES-401-2 Facility: Date of Exam:

Tier Group RO K/A Category Points SRO-Only Points K1 K2 K3 K4 K5 K6 A1 A2 A3 A4 G* Total A2 G* Total

1. 1 18 6 Emergency and N/A N/A 2 8 4 Abnormal Plant Evolutions Tier Totals 26 10 1 28 5 2.

Plant 2 9 3 Systems Tier Totals 37 8