ML13263A066

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2013 Davis-Besse Initial License Examination Administrative Admin
ML13263A066
Person / Time
Site: Davis Besse Cleveland Electric icon.png
Issue date: 06/03/2013
From:
NRC/RGN-III
To:
FirstEnergy Nuclear Operating Co
Michael Bielby
Shared Package
ML11354A427 List:
References
Download: ML13263A066 (19)


Text

ES-201 Examination Preparation Checklist Form ES-201-1 Facility: Davis-Besse Nuclear Power Station Date of Examination: Week of 6/3/2013 Developed by: Written - Facility NRC // Operating - Facility NRC Target Date*

Task Description (Reference)

Chief Examiners Initials

-180

1.

Examination administration date confirmed (C.1.a; C.2.a and b) meb

-120

2.

NRC examiners and facility contact assigned (C.1.d; C.2.e) meb

-120

3.

Facility contact briefed on security and other requirements (C.2.c) meb

-120

4.

Corporate notification letter sent (C.2.d) meb

[-90]

[5.

Reference material due (C.1.e; C.3.c; Attachment 3)]

NA

{-75}

6.

Integrated examination outline(s) due, including Forms ES-201-2, ES-201-3, ES-301-1, ES-301-2, ES-301-5, ES-D-1's, ES-401-1/2, ES-401-3, and ES-401-4, as applicable (C.1.e and f; C.3.d) meb

{-70}

{7.

Examination outline(s) reviewed by NRC and feedback provided to facility licensee (C.2.h; C.3.e)}

meb

{-45}

8.

Proposed examinations (including written, walk-through JPMs, and scenarios, as applicable), supporting documentation (including Forms ES-301-3, ES-301-4, ES-301-5, ES-301-6, and ES-401-6, and any Form ES-201-3 updates), and reference materials due (C.1.e, f, g and h; C.3.d) meb

-30

9.

Preliminary license applications (NRC Form 398's) due (C.1.l; C.2.g; ES-202) meb

-14

10.

Final license applications due and Form ES-201-4 prepared (C.1.l; C.2.i; ES-202) meb

-14

11.

Examination approved by NRC supervisor for facility licensee review (C.2.h; C.3.f) meb

-14

12.

Examinations reviewed with facility licensee (C.1.j; C.2.f and h; C.3.g) meb

-7

13.

Written examinations and operating tests approved by NRC supervisor (C.2.i; C.3.h) meb

-7

14.

Final applications reviewed; 1 or 2 (if >10) applications audited to confirm qualifications / eligibility; and examination approval and waiver letters sent (C.2.i; Attachment 5; ES-202, C.2.e; ES-204) meb

-7

15.

Proctoring/written exam administration guidelines reviewed with facility licensee (C.3.k) meb

-7

16.

Approved scenarios, job performance measures, and questions distributed to NRC examiners (C.3.i) meb

  • Target dates are generally based on facility-prepared examinations and are keyed to the examination date identified in the corporate notification letter. They are for planning purposes and may be adjusted on a case-by-case basis in coordination with the facility licensee.

[Applies only] {Does not apply} to examinations prepared by the NRC.

NUREG-1021, Revision 9 Supplement 1 Page 1 of 2 FENOC Facsimile Rev. Final ES-401 Record of Rejected K/As Form ES-401-4 Facility: Davis Besse Date of Exam 6/3 thru 6/14 2013 Operating Test No.:

Tier /

Group Randomly Selected K/A Reason for Rejection RO OUTLINE 1/1 000011 EA2.12 Question # 3 Davis Besse does not have a system for throttling or stopping reflux boiling spray. Randomly selected 000011 EA2.10 as a replacement.

1/1 000025 AK3.01 Question # 6 Davis Besse does not have an alternate RHR flowpath. Randomly selected 000025 AA1.01 as a replacement.

1/2 000059 AK2.01 Question # 21 Davis Besse does not have any gas monitors on the liquid waste discharge system. Randomly selected 000059 AK2.01 as a replacement.

2/1 025 2.4.4 Question # 40 Davis Besse does not have Ice Condensers. Randomly selected 004 2.4.4 as a replacement.

2/1 025 K1.02 Question # 41 Davis Besse does not have Ice Condensers. Randomly selected 062 K1.02 as a replacement.

2/1 064 K4.08 Question # 50 Davis Besse does not have any design features or interlocks for EDG fuel isolation valves. Randomly selected 064 K4.03 as a replacement.

2/1 073 K5.03 Question # 51 Unable to write a discriminatory question for the process radiation monitoring system that depicts the relationship between radiation intensity and exposure limits. Randomly selected 073 K5.01 as a replacement.

3 2.4.40 Question # 75 Unable to write an RO discriminatory question regarding SRO responsibilities during E-Plan implementation. Randomly selected 2.4.35 as a replacement.

2/2 034 A3.01 Question # 59. Deleted from the exam to achieve balance. There are too many fuel handling questions (5) already being addressed on this exam. Discussed with chief examiner and determined that this K/A should be deleted to obtain a better balance. Randomly selected 041 A2.02 as a replacement.

2/1 073 K5.01 Question # 51 During NRC review of the exam materials, it was determined that this K/A is not supportive of a licensing decision and the K/A should be deleted from this exam and replaced with a Randomly selected K/A. Deleting this K/A will result in Tier 2 total for K5 to be less than the suggested value of 2. Discussed with the chief examiner on 4/29/13. This will result in exercising note 2 of the outline that allows this deviation (+ 1) based on NRC review. Documented this deviation on ES-401-2 PWR Examination Outline cover page. Randomly selected 073 K1.01 as a replacement.

NUREG-1021, Revision 9 Supplement 1 Page 2 of 2 FENOC Facsimile Rev. Final ES-401 Record of Rejected K/As Form ES-401-4 Facility: Davis Besse Date of Exam 6/3 thru 6/14 2013 Operating Test No.:

Tier /

Group Randomly Selected K/A Reason for Rejection SRO OUTLINE 2/2 027 A2.01 Question # 92 Davis Besse does not have an iodine removal system. Iodine is removed with the passive sodium triphosphate baskets. Randomly selected 015 A2.01 as a replacement.

1/1 057 AA2.16 Question # 77 Unable to write a discriminatory SRO level question for loss of vital AC impact on PZR level. Randomly selected 038 EA2.01 as a replacement.

ES-401 Written Examination Review Worksheet Form ES-401-9 Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 1

H 2.0 N

S 2

F 2.0 N

E NRC: Change necessary to required in distracter (b.) to match others.

Licensee: Changed necessary to required in distracter (b.)

3 H

2.0 N

S 4

F 2.0 N

S 5

F 2.0 N

E NRC: distracter (b.) changed place to placed.

Licensee: Changed place to placed in distracter (b.)

6 H

2.0 N

S 7

H 2.0 B

E NRC: Add to the plant conditions: in a normal 100% lineup.

Licensee: Added all systems in normal alignment for this power level to the initial plant conditions.

8 H

2.0 N

S Instructions

[Refer to Section D of ES-401 and Appendix B for additional information regarding each of the following concepts.]

1.

Enter the level of knowledge (LOK) of each question as either (F)undamental or (H)igher cognitive level.

2.

Enter the level of difficulty (LOD) of each question using a 1 - 5 (easy - difficult) rating scale (questions in the 2 - 4 range are acceptable).

3.

Check the appropriate box if a psychometric flaw is identified:

The stem lacks sufficient focus to elicit the correct answer (e.g., unclear intent, more information is needed, or too much needless information).

The stem or distracters contain cues (i.e., clues, specific determiners, phrasing, length, etc).

The answer choices are a collection of unrelated true/false statements.

The distracters are not credible; single implausible distracters should be repaired, more than one is unacceptable.

One or more distracters is (are) partially correct (e.g., if the applicant can make unstated assumptions that are not contradicted by stem).

4.

Check the appropriate box if a job content error is identified:

The question is not linked to the job requirements (i.e., the question has a valid K/A but, as written, is not operational in content).

The question requires the recall of knowledge that is too specific for the closed reference test mode (i.e., it is not required to be known from memory).

The question contains data with an unrealistic level of accuracy or inconsistent units (e.g., panel meter in percent with question in gallons).

The question requires reverse logic or application compared to the job requirements.

5.

Check questions that are sampled for conformance with the approved K/A and those that are designated SRO-only (K/A and license level mismatches are unacceptable).

6.

Enter question source: (B)ank, (M)odified, or (N)ew. Check that (M)odified questions meet criteria of ES-401 Section D.2.f.

7.

Based on the reviewers judgment, is the question as written (U)nsatisfactory (requiring repair or replacement), in need of (E)ditorial enhancement, or (S)atisfactory?

8.

At a minimum, explain any U ratings (e.g., how the Appendix B psychometric attributes are not being met).

ES-401 2

Form ES-401-9 Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 9

F H

2.0 N

E NRC: Requires comprehension and analysis. May be higher skill Licensee: Changed cognitive level to higher.

10 H

2.0 B

E NRC: Distracter (d.) provides additional info in the distracter. Redo the distracter so no additional information need be provided.

Licensee: Deleted unnecessary additional information from distracter (d.).

11 F

2.0 N

U NRC: Steam flow out the break increasing is implausible. Because it appears in two distracters the question is unsatisfactory. Replace or rework the question Licensee: Replaced rising with remains the same for item 2 in both distracters (b. & d.).

12 H

2.0 N

S 13 H

2.0 N

S 14 F

2.0 B

S 15 H

2.5 N

S 16 F

2.0 B

S 17 F

2.0 B

S 18 H

2.0 N

S 19 H

F 2.0 N

E NRC: Probably fundamental. Cant get to the answer without memorization.

Licensee: Changed cognitive level to lower.

20 F

2.0 N

S 21 F

2.0 N

E NRC: Plant conditions are not necessary. The question should simply state, which of the following is monitored by RE 4686?

Licensee: Removed all references to a SG tube leak. Revised question to ask for possible leakage.

22 F

2.0 N

S 23 F

2.0 N

S 24 H

2.0 N

S

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 25 H

2.0 B

S 26 H

2.5 N

S 27 H

2.5 N

S 28 H

2.0 N

S 29 H

2.5 N

S 30 F

2.0 N

S 31 H

2.5 N

S 32 F

2.0 N

S 33 F

2.0 N

E NRC: Add plant conditions, add Given to stem.

Licensee: Determined pant conditions are necessary. Added Given the following to the stem of the question.

34 H

2.0 N

S 35 F

2.0 N

S 36 H

2.0 B

S 37 H

2.0 x

N U

NRC: Question does not address both sides of the K/A. The author should be able to add the part about what is to be done under the conditions.

Licensee: Revised question to address both parts of the K/A.

38 H

2.5 N

S 39 H

2.0 N

S 40 H

2.0 N

S 41 H

2.5 N

S 42 H

2.0 N

S 43 F

1.0 x

N U

NRC: The only distracter that deals with the loud noise is the lowering Tave.

Licensee: Deleted the reference to a loud noise. Re-phrased the question to address a short time later.

44 H

F 2.0 B

E NRC: This is not a higher skill question. It has to be done from memory.

Licensee: Changed cognitive level to lower.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 45 H

2.0 N

E NRC: Why LOK=H?

Licensee: Higher skill since it requires analysis of the conditions in the stem to answer the question.

46 H

2.5 N

E NRC: Distracter (a.) is implausible. The stem states AFW Train 1 is steam bound. No one should believe Train 1 is still operable.

Rework/replace distracter (a.).

Licensee: Revised the (a.) distracter to make it a plausible distracter.

47 F

2.0 B

E NRC: The first sentence in the stem provides training and is not necessary. Remove the first statement in the stem.

Licensee: Removed first sentence of the stem 48 H

2.4 N

S NRC: Why LOK=H?

Licensee: Higher level since it requires analysis of the conditions and prediction of final DC bus alignment.

49 H

2.5 B

S 50 H

2.5 B

S 51 F

1.0 N

U NRC: Not a useful licensing question. See if there is a question that can be developed that involves effects of the PRM.

Licensee: Difficult to write question to this KA, will select new KA and write new question. Replaced the question.

52 H

2.5 N

S 53 H

2.0 N

S 54 F

2.0 N

S 55 F

2.0 N

S 56 H

2.0 N

S 57 H

2.0 N

S 58 H

2.0 N

S 59 H

2.5 N

E NRC:Reword the stem so it shows 100% power in the past tense.

Licensee: Revised to reflect past tense. Changed is to was in the first sentence.

60 H

2.0 N

S NRC: Why LOK=H?

Licensee: Discussed skill level. Left at higher. Question does require comprehension of the sequence of events to determine final plant condition.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 61 H

2.0 N

S 62 F

2.0 N

S 63 F

2.0 N

S 64 F

2.5 B

S 65 H

2.0 N

S 66 F

H 2.0 N

E NRC: Probably requires some analysis - higher skill.

Licensee: Changed cognitive level to higher.

67 F

2.0 N

S 68 F

2.0 B

S 69 F

2.0 N

S 70 F

2.0 B

S 71 F

2.0 B

E NRC: Consider changing distracter (a.) to 5 minutes - 5 Rem dose.

Licensee: Changed distracter (a.) to 5 minutes 72 H

2.0 N

S 73 F

2.5 N

S 74 F

2.0 N

S 75 H

2.0 B

S LOK (F/H) 32/43=43%/57% (H=38-45)

B/M/N 16/0/59=21%/0%/79% (B56; M11, N@H=10, N@H8)

UNSAT for RO Only 4/75=5%

E for RO Only 15/75=20%

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 76 H

2.5 x

N U

S NRC: As written, the question is at the RO level. Change the question to read: At the appropriate time the SRO will direct implementation of. The diagnosis is expected of an RO. The question does not ask when the Specific Rules is to be implemented

- RO knowledge.

Licensee: Question matches example provided on NRC SRO Only White Paper. After discussion and clarifications, the question is OK as written.

77 H

2.5 x

N U

S NRC: The question requires diagnosis of plant conditions, a skill required of an RO. The question is an RO question.

Licensee: Question matches example provided on NRC SRO Only White Paper. The question is OK as written.

78 H

2.5 x

N U

NRC: As written, the question is an RO question. The RO is required to be able to diagnose plant conditions and take appropriate actions.

The only answer with the correct actions is the only answer containing those actions and is therefore, an RO question.

Licensee: Rewrote the question at the SRO level. Modified to 1 of 2 twice format, using procedure selection and action, and possible Tech Spec action (>1 hr) in each choice.

79 H

2.5 x

N U

NRC: The question requires system knowledge to answer the question. ROs monitor their panels and would be expected to know this system knowledge. The question is an RO level question.

Licensee: Rewrote the question at the SRO level by including a portion of question addressing the TS bases.

80 H

2.0 x

N U

S NRC: The answer can be determined with RO knowledge. Although an entry is required and is SRO knowledge, the actions taken are RO and since the correct RO action is in the only correct answer, the question is an RO question..

Licensee: Question matches example provided on NRC SRO Only White Paper. After discussion and clarifications, the question is OK as written.

81 H

2.0 x

N S

NRC: This is an RO question. Requires only diagnosis, general knowledge of a procedure and system operating skill. If an operator knows to use Main Feedwater, he arrives at the correct answer - RO skill.

Licensee: After discussion and clarifications, the question is OK as written.

82 H

2.0 x

N S

NRC: This is an RO question. Requires only system and operating procedure knowledge. Accident analysis is not an SRO only item.

Licensee: After discussion and clarifications, the question is OK as written.

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 83 F

2.0 x

N S

84 H

2.0 x

N U

NRC: This is an RO question. This information would be taught in systems training. Operators should know which instruments in the control room have safety functions.

Licensee: Rewrote the question at the SRO level by including a portion of question addressing TS application.

85 H

4.0 x

N S

NRC: The question requires recollection of a NOTE on page 15 of DB-OP-02508. Applicants are not required to memorize notes, cautions, and precautions, but when supplied with those notes, cautions and precautions, they are required to be able to explain and implement them. The K/A calls for the ability to explain and apply system limits and precautions. The question asks for a classification that is a direct look-up.

Licensee: After discussion and clarifications, the question is OK as written.

86 H

2.0 x

N U

S NRC: This is an RO question. This information would be taught in procedures classes and ROs are required to be familiar with material in procedures. Just like the example.

Licensee: Question matches example provided on NRC SRO Only White Paper, no change requested. After discussion and clarifications, the question is OK as written.

87 H

2.0 x

N S

88 H

2.0 x

N U

NRC: This is an RO question. The RO is required to be able to diagnose plant conditions and know which procedure/Attachment should be used to correct system lineups. System knowledge after diagnosis.

Licensee: Rewrote the question at the SRO level by including a portion of question procedure selection and actions contained in that section. Modified to 1 of 2 twice format, using procedure selection and action, and possible Tech Spec action (>1 hr) or transition, or Tech Spec bases, or procedure transition in each choice. Rewrote the question at the SRO level by including a portion of question procedure selection and actions contained in that section.

89 H

2.0 x

N S

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 90 H

2.0 x

N U

NRC: This is an RO question. The answer can be found without any SRO knowledge because it asks what actions will be required. The correct answer has the actions that would be performed by an RO.

Since the question can be answered with RO knowledge, the question is not an SRO Only question.

Licensee: Modified to 1 of 2 twice format, using procedure selection and action, and possible Tech Spec action (>1 hr) or transition, or Tech Spec bases, or procedure transition in each choice. Rewrote the question at the SRO level by including procedure selection in the question.

91 H

2.0 x

N S

92 H

2.0 x

N S

93 H

5.0 x

N U

S NRC: The correct answer requires the applicant to memorize supplemental steps in a procedure and place them in the correct order. Do you feel SROs should know this level of detail?

Licensee: Does not require applicants to place in correct order. Yes we expect SROs to know this level of detail. Correct order not required for this question. After discussion and clarifications, the question is OK as written.

94 H

2.0 x

N S

95 H

2.0 x

x N

U NRC: Distracters (c.) and (d.) are implausible. The applicant should know what the status of S/G blowdown is (in service/out of service) during power operations. Accident analysis is not SRO Only.

Suggest having SRO make decision of whether or not to put into service based on Chemistry results.

Licensee: Correct order not required for this question. Rewrote the question at the SRO level by including a portion of question addressing TS application.

96 H

2.0 x

N U

NRC: This is an RO question. The control room operator should recognize that DH7A and DH7B are closed, with power removed because it occurs on his panels. He has responsibility to recognize the condition of the valves during shutdowns.

Licensee: Modified to 1 of 2 twice format, using procedure selection, transition, Tech Spec Action or bases in each choice.

Rewrote the question at the SRO level by including procedure selection in the question. Question is now lower level.

97 H

2.0 x

N S

Q#

1.

LOK (F/H)

2.

LOD (1-5)

3. Psychometric Flaws
4. Job Content Flaws
5. Other
6.

B/M/N

7.

U/E/S

8.

Explanation Stem Focus Cues T/F Cred.

Dist.

Partial Job-Link Minutia

  1. /

units Back-ward Q=

K/A SRO Only 98 H

2.0 x

N S

NRC: Question doesnt match the K/A. The K/A asks for generic knowledge concerning rad monitoring systems. The question asks for an emergency classification. The question may be a direct lookup.

Licensee: After discussion and clarifications, the question is OK as written.

99 H

2.0 x

N S

NRC: To be actually correct, this should be in a 1 of 2 taken twice format.

Licensee: After discussion and clarifications, the question is OK as written.

100 H

2.0 x

N S

NRC: The K/A calls for generic knowledge of PARs. This question asks for a specific PAR based on specific plant parameters.

Question does not match the K/A.

Licensee: After discussion and clarifications, the question is OK as written.

LOK (F/H) 1/24=4/96% (H=38-45)

B/M/N 0/0/25=0/0/100% (B19; N2@H, M11)

UNSAT for SRO Only 7/25=28%

E for SRO Only 0/25=0%

2013 Davis-Besse Initial Licensed Operator Exam Outline Review I.

JPMs A. RO Admin COM: Describe how RO A1.1 is different from RO A1.1 on 2011 Exam.

ANS: Will verify JPM is different.

COM: RO A3 appears to be more of a Systems JPM ANS: Title is misleading and should be changed to Perform Administrative Checks for RW Discharge. JPM requires manipulation of switches to reset the setpoint; however, the RM is not performing its system function of alarming and/or isolation if setpoint is exceeded.

As a result we feel this is admin vice system JPM. We do have a replacement admin JPM for R.4 which would be Notification of Offsite Agencies for UE.

B. SRO Admin COM: SRO A1.1 - A notification to the FAA doesnt appear to match the K/A; seems to fit 2.4.30 instead.

ANS: Understand focus is more on filling out report vice making the report. Will replace with new SRO admin JPM for reviewing the SDM that is performed by the ROs. Will have mistakes to be identified by the reviewer. The KA 2.4.30 doesnt fit either because R.4 section is for EP, at least for initial exams (ES 301-1). Probably KA 2.1.17, ability to makeverbal reports is a better fit.

C. Control Room Systems COM: Explain how de-energizing an instrument transmitter (S2) is related to the Reactor Coolant System Inventory Control; seems to be more related to the Instrumentation Safety Function.

ANS: This system (ECCS) is only listed in the the Reactor Coolant System Inventory Control Safety Function. Not listed under the Instrumentation Safety Function COM: Explain how S3, HPI Flow Balance is related to the Reactor Pressure Control Safety Function; Inventory Control seems more appropriate.

ANS: Because plant is in LOCA, operator balances flow is based on pressure, have a related curve and graph to balance flow based on pressure.

D. In-Plant Systems COM: Explain how P3, Service Water Header Pressure control relates to the Heat Removal Safety Function; Plant Service Systems seem more appropriate.

ANS: Change KA, put under Safety Function 8, Plant Service Systems.

II.

Scenarios A. Scenario 1 COM: Recommend adding an additional I/C failure for the ATC prior to the major. This scenario is the only scenario that 2 of the 3 SROI will be on the panel.

ANS: Will modify alignment such that one crew of 3 SRO-Is, and two crews of one SRO-U and two ROs, changeout the SRO-U on second set with the remaining SRO-U. Run Scenarios 1&3, 2 ROs get minimum C/I failures (will add another ATC C/I), 2 ROs get 1 greater than minimum C/I; run Scenario 2 for third SRO-Is crew. Scenario 4 is backup.

COM: I dont believe I would classify event 8 as M, unless the leak is driving the condition to scram and not simply the failure to isolate.

ANS: Unisolable steam leak, isolate S/G and blowdown, trip reactor. Separate M.

COM: What is the probability that the BOP operator could be assigned the task of establishing MU/HPI/PORV cooling on Event 10?

ANS: The ATC will handle while BOP is on backpanel.

B. Scenario 2 COM: Event 1, does bi-stable tripping require the operator to leave the ATC area? If so, wouldnt the BOP operator be the one tripping bi-stables? If so, the ATC operator would not receive credit.

ANS: Mislabeled, should be BOP.

COM: What will be done to ensure that the ATC-RO responds and mitigates events 7 & 8?

ANS: ATCs will handle SFAS and ECCS actions; BOP will monitor secondaries.

C. Scenario 3 COM: Should Event 2 only be BOP and SRO vice ALL?

ANS: No. Should be ALL. Sufficient actions for ATC stop and BOP in Rack to swap input.

COM: Recommend adding an additional I/C failure for the ATC prior to the major. This scenario is the only scenario that the 3rd SROI will be on the panel.

ANS: See comment answer on Scenario 1.

D. Scenario 4 None III.

Written COM: Provide description of methodology used to develop outline.

ANS: It is provided in the letter submitting the outline.

Page 1 of 5 DAVIS-BESSE 2013 OPERATING TEST COMMENTS 4/23/2013 Admin JPMs NRC Licensee Response/Action NA RO-1.1 Initial Conditions - Reactor Engineer reports should not be provided until asked for by the applicant.

Revised JPM to include an examiner cue to provide Reactor Engineer data when requested by the candidate.

Performance Step (PS) 2 - recommend tightening the standard to 12.45 to 12.5%K/K Revised standard to recommended band.

PS recommend tightening the standard for BCF to 1.007 to 1.008 and the resultant calculation to -12.18 to -12.30.

Revised standard to recommended band.

PS recommend tightening the standard to 0.160 to 0.161%K/K Revised standard to recommended band.

PS with all the above changes the final value standard should be 6.24 to 6.44 Revised standard to recommended band.

NA RO-1.2 NO COMMENTS NA RO-2 PS-2 and 4 - The interpolated specific volumes should be rounded to the fifth decimal place (0.02168 and 0.02167 respectively)

Revised specific volumes to recommended values.

NA RO-3 If the current warning setpoint is 1.23 E4 as stated in PS-4, then PS-10 and 11 would not be critical since no change to the exponent digit required.

Revised steps 10 and 11 to be non-critical.

PS-13, -14, -25 and -26 are verification steps and should not be critical.

Revised steps 13, 14, 25, and 26 to be non-critical.

What is the normal position for the function switch? Does it matter what position it is left in?

The normal position is the as left position and it does not matter what position the switch is left in.

NA SRO-1.1 See comments for NA RO-1.1 See responses for NA RO-1.1 Add step to evaluate whether SDM requirements are satisfied or not.

Added a follow-up step to evaluate whether SDM requirements are satisfied or not.

NA SRO-1.2 Recommend adding a step or steps indicating that Sam could not be contacted and an evaluation of whether it is necessary to complete a waiver (two possible choices a) minimum shift staffing will be met with the additional RO or b) minimum shift staffing will not be met and a waiver is required)

Added a follow-up step to address when a waiver would be necessary.

Change the word available in the 1st sentence of the INITIATING CUE to prospective: The task will determine if they are available or not.

Changed the word available in the 1st sentence of the initiating cue to prospective:

Page 2 of 5 Reword the last two sentences of the INITIAL CONDITIONS to state: Bill, Joe, and Sam are scheduled to be off on 6/3/13 and are being considered for call-out.

Their work hour history is included below.

Reworded the last two sentences of the INITIAL CONDITIONS to state:

Bill, Joe, and Sam are scheduled to be off on 6/3/13.

Recommend including Work Hour History on the Cue Page Unable to fit work hour history on the candidate cue sheet. Left as a separate page to be given as part of the cue.

PS Bill will exceed MWH26/48 after 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> not 3; additionally Bill would need authorization for the short turn-around (MBBS8).

Revised to address 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> NOT 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br />.

NA SRO-2 Change INTIATION CUE to:

1) Perform the Work Group Supervisor review. (shouldnt have to tell them to determine operability.
2) Add step to determine required LCO actions.
1. Revised initiating cue to read:

Review/Approve completed surveillance.

2. Added a cue at the end of the JPM to ask, if necessary what is the impact on pump operability NA SRO-3 INITIATION CUE - change Perform to Complete Changed Perform to Complete in the initiating cue.

NA SRO-4 Recommend the following changes to the INTITIAL CONDITIONS:

1) Move the You are the Emergency Director to the Initial Conditions
2) Revise the 1st bullet to include that a Site Area Emergency was declared 30 minutes ago and that all notifications had been completed, but ERO facilities activation is still in progress. (Provide a marked up copy RA-EP-01800 completed through step 6.2.1.l)
3) Change you have just declared a GE to you have just upgraded to a General Emergency per EAL RG1 based on the below Off-site Dose Assessment Data (moved to the INITIAL CONDITIONS)
1. Moved the You are the Emergency Director to the Initial Conditions
2. Revised initial conditions to include that a Site Area Emergency was declared 30 minutes ago and that all notifications had been completed, but ERO facilities activation is still in progress.
3. Provided a marked up copy RA-EP-01800 completed through step 6.2.1.l.
4. Revised initial conditions to include:

..you have just upgraded to a General Emergency per EAL RG1 based on the below Off-site Dose Assessment Data.

Revise INITIATION CUE to: Continue with implementation of RA-EP-01900, General Emergency, beginning at step 6.1.1.h.

Revised initiation cue to: Continue with implementation of RA-EP-01900, General Emergency, beginning at step 6.1.1.h.

Page 3 of 5 Provide a marked up copy of RA-EP-01900 completed through step 6.1.1.g WITH the time that the GE was declared entered as Current time minus 2 minutes Provided a marked up copy of RA-EP-01900 completed through step 6.1.1.g WITH the time that the GE was declared entered as Current time minus 2 minutes.

PS delete the word unknown from the standard.

Deleted the word unknown from step 4 standard.

Control Room System JPMs NS-1 Move RE cue to the INITIAL CONDITIONS Moved RE cue to the initial conditions.

Delete INITIAL CONDITION related to demin 1st use (procedure is already markedup).

Deleted initial condition related to demin 1st time use.

PS-22 does not appear as a step in either procedure. The next step of the ARP would have the operator verify the lineup and it also appears that step 3.5.22 of DB-OP-06001 may also be applicable.

Deleted step 22 of the JPM.

NS-2 PS-7 STANDARD; there is no procedure step to verify SFAS CH1, 2, & 3 1/2 trips on LO RCS Pressure Added a comment to step 7 that the verification is non-critical.

NS-3 This is not an alternate path JPM since the task is to balance flow with one pump failed (an initial condition) and it does not appear that there is any step to attempt to start the pump.

Added a step to attempt to start the failed pump.

NS-4 It seems that DB-OP-02543 sends the operator to DB-OP06401. What guidance would direct the applicant to DB-OP02000?

Procedure step 3.20 in 06401 does not look anything like the steps stated in the JPM. You have identified critical steps that are not included in 06401.

Revised steps 5 and 7 to address the actions necessary to open the AVVs.

NS-5 No Comments N/A NS-6 PS-1; Why is 3.8.2.a marked N/A Step is marked N/A since the plant is NOT on backfeed for this JPM.

PS-9; Why is 3.9.2.a marked N/A Step is marked N/A since the plant is NOT on backfeed for this JPM.

NS-7 No Comments N/A NS-8 PS-9 though PS-12; Not an alternate path even though the valves have failed to automatically close, the Attachment is performed to verify valve status and is successfully completed by simply closing the valves with the associated MCR control switch. To be an alternate path valve(s) would have to be closed by another method or an alternate valve closed to isolate path.

Revised JPM and ES-301-2 forms to reflect that this JPM is no longer an alternate path JPM.

Page 4 of 5 In-Plant System JPMs NP-1 Remove the cue related to required emergency equipment from the CUE Sheet and replace with a new 1st step requiring examinee to identify required equipment with a cue to ask if necessary.

Removed the cue related to required emergency equipment. There are no special PPE requirements for this task. The procedural step to obtain this equipment pertains to other steps within the procedure that are not related to this particular task.

Is there any special PPE required for the breaker/disconnect operations?

No NP-2 PS-3, 4, 5, 6, are not critical steps in that they have no impact on the physical ability to establish the desired pressure.

Based on the aggregate of all comments related to this JPM, this JPM was replaced with a JPM addressing Steam binding of the motor driven AFW pump.

PS-9 is not critical unless examinee simulates a local action to place valve in required position.

See above response for NP-2.

This JPM essentially has only ONE locally performed critical step (throttling the HX outlet valve) and one locally performed non-critical step (hang a placard). All other steps are/or could be performed from the MCR prior to dispatching the operator.

See above response for NP-2.

Where placards are to be prepared or hung, provide a handout for examinee (scanned image or picture)

See above response for NP-2.

NP-3 Shouldnt PS-11 be critical since it was positioned earlier?

Made step 11 critical.

PS-6&8; cues for engine speed should be coasting or trending to 0 RPM Revised cues for engine speed in steps 6 and 8 to be trending towards 0 RPM General JPM Comments/Questions Will examinees be provided with complete procedures or only sections?

Only the sections necessary to complete the task.

Scenario Comments Scenario 1 Event 5; include affected FUNCTION (where applicable) with instrumentation Tech Spec info Event 5; included affected FUNCTION with instrumentation Tech Spec information.

Scenario 2 Summary (page 2) - change ATC tripping bistables to BOP Summary page 2 - changed ATC tripping bistables to BOP.

Event 1; include affected FUNCTION/PARAMETER (where applicable) with instrumentation Tech Spec info Event 1; included affected FUNCTION with instrumentation Tech Spec information.

Event 3 - include (ATC) performance steps to be taken to initiate power Event 3 -Added (ATC) performance steps to be taken to initiate power

Page 5 of 5 reduction.

reduction.

Event 5; Does seal injection flow have to be restored to 30-32 gallons (20 plus minute evolution) before letdown is restored? Does letdown have to be restored before moving to the next event?

Consider using time compression, these two activities are needed for evaluation purposes.

Event 5 - Letdown will be restored first. Added a note to address that it is not necessary to wait the 20 minutes to completely restore seal injection flows back to the original values. It is only necessary to see the initial restoration.

Event 6; If intent is to observe small leak response per DB-OP-02522, ensure leak starts out small (or ramp rate is long enough) to ensure time for response.

Event 6 - It is not intended to evaluate the crew response to the small break.

No credit was taken for the Abnormal operating procedure entry. The intent is to merely provide a reason for a manual reactor trip.

Scenario 3 Event 2; include affected FUNCTION (where applicable) with instrumentation Tech Spec info Event 2 - Function not applicable.

Scenario 4 (Spare)

Event 1: Seems to be more of a NORMAL evolution rather than a REACTIVITY manipulation since it doesnt appear that any power change is taking place at this time; ICS appears to be maintaining a constant power in AUTO. Event 4 will probably result in more of a power change.

Event 1 - Revised to be a normal evolution.

Event 1; add procedure reference of procedure to be used.

Event 1 - Added IAW procedure DB-OP-06001.

Event 4; include affected FUNCTION (where applicable) with instrumentation Tech Spec info Event 4; included affected FUNCTION with instrumentation Tech Spec information.

Add section number for Overcooling Section on page 13.

Added section 7 for Overcooling on page 13.

Page 13; add OP-02000 Attachment 1 and 2 actions for ATC and BOP.

Deleted ATC and BOP actions for. These actions are not required for the scenario and do not contain any critical actions. The scenario is terminated at this point.