ML14290A304

301 Final Administrative Documents

ML14290A304
Person / Time
Site:	Catawba
Issue date:	10/27/2014
From:	Division of Reactor Safety II
To:	Duke Energy Corp
Shared Package
ML14290A363	List: CNS-14-056, 301 General Correspondence ML14240A626 ML14240A660 ML14240A666 ML14240A671 ML14240A675 ML14290A076 ML14290A304 ML14290A321 ML14290A326 ML14290A330 ML14290A332
References
50-413/14-301, 50-414/14-301
Download: ML14290A304 (31)

Text

ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM FINAL SUBMITTAL Facility: Catawba Nuclear Station Date of Examination: May 2014 Examination Level: RO SRO Operating Test Number: 2014301 Administrative Topic (See Note) Type Code* Describe activity to be performed Conduct of Operations R,D Determine License Status G2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc. Conduct of Operations R,D Calculate Boric Acid and Water Addition to FWST G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. Equipment Control R,N Tagout "A" KR (Recirc. Cooling Water) Pump for check valve inspection G2.2.15 Ability to determine the expected plant configuration using design and configuration control documentation, such as drawings, line-ups, tag-outs, etc. Radiation Control P,R Calculate Low Pressure Service Water Discharge Flow for Radioactive Release G2.3.11 Ability to control radiation releases. Emergency Procedures/Plan --- NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes) (N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected) ES 301, Page 22 of 27 ES-301 Administrative Topics Outline Form ES-301-1 NRC EXAM FINAL SUBMITTAL Facility: Catawba Nuclear Station Date of Examination: May 2014 Examination Level: RO SRO Operating Test Number: 2014301 Administrative Topic (See Note) Type Code* Describe activity to be performed Conduct of Operations R,D Determine License Status G2.1.4 Knowledge of individual licensed operator responsibilities related to shift staffing, such as medical requirements, "no-solo" operation, maintenance of active license status, 10CFR55, etc. Conduct of Operations R,D Calculate Boric Acid and Water Addition to FWST G2.1.25 Ability to interpret reference materials, such as graphs, curves, tables, etc. Equipment Control R,N Tagout 1EBC (Vital Battery) G2.2.13 Knowledge of tagging and clearance procedures. Radiation Control P,R Calculate Low Pressure Service Water Discharge Flow for Radioactive Release G2.3.11 Ability to control radiation releases. Emergency Procedures/Plan R,M Classify the Event, and determine Protective Action Recommendations (PAR) G2.4.44 Knowledge of emergency plan protective action recommendations NOTE: All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when 5 are required.

• Type Codes & Criteria: (C)ontrol room, (S)imulator, or Class(R)oom (D)irect from bank (< 3 for ROs; < 4 for SROs & RO retakes) (N)ew or (M)odified from bank (> 1) (P)revious 2 exams (< 1; randomly selected) ES 301, Page 22 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2014 Exam Level: RO SRO-I SRO-U Operating Test Number: 2014301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function a. Respond to inadvertent dilution while shutdown 004A2.06 Control/mitigate inadvertent dilution. 4.2/4.3 A,L,N,S 1 b. Transfer the ECCS to Cold Leg Recirc 006A4.07 Operate ECCS pumps and valves 4.4/4.4 A,M,EN,L,S 2 c. Cycle RCS PORV for periodic test 010A4.03 Operate/monitor PORV and block valves 4.0/3.8 N,L,S 3 d. Start 1B NC (RCS) Pump 003A1.01 Parameters for operating RCP controls - vibration 2.9/2.9 A,D,L,S 4P e. Synchronize the Generator to the Grid 045A4.02 Monitor/operate T/G controls, including breakers. 2.7/2.6 A,N,S 4S f. Restoration of Offsite Power 062A4.01 Operate/monitor All breakers in the control room 3.3/3.1 N,S 6 g. Shift Lower Containment Ventilation Units 022A4.01 Operate/monitor CCS fans 3.6/3.6 C,N 5 h. Shift KC (CCW) Trains 008A4.01 Operate/monitor CCW indications and controls 3.3/3.1 M,S 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Break Main Condenser Vacuum Locally - Unit 2 045A1.06 Monitor parameters following T/G trip 3.3/3.7 P,D,E 4S j. Shift Main Transformer Auxiliaries 062A2.01 Operate loads that would degrade plant operation. 3.4/3.9 P,D 6 k. Place 2A Hydrogen Analyzer in service 028A1.01 Monitor parameters for operating HRPS controls-H2 con. 3.4/3.8 D,E,L,R 5 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room. *Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 < 9 / < 8 / < 4 > 1 / > 1 / > 1 - / - / > 1 > 1 / > 1 / > 1 > 2 / > 2 / > 1 < 3 < 3 / < 2 (randomly selected) > 1 / > 1 / > 1 ES-301, Page 23 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2014 Exam Level: RO SRO-I SRO-U Operating Test Number: 2014301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function a. Respond to inadvertent dilution while shutdown 004A2.06 Control/mitigate inadvertent dilution. 4.2/4.3 A,L,N,S 1 b. Transfer the ECCS to Cold Leg Recirc 006A4.07 Operate ECCS pumps and valves 4.4/4.4 A,M,EN,L,S 2 c. Cycle RCS PORV for periodic test 010A4.03 Operate/monitor PORV and block valves 4.0/3.8 N,L,S 3 d. Start 1B NC (RCS) Pump 003A1.01 Parameters for operating RCP controls - vibration 2.9/2.9 A,D,L,S 4P e. N/A f. Restoration of Offsite Power 062A4.01 Operate/monitor All breakers in the control room 3.3/3.1 N,S 6 g. Shift Lower Containment Ventilation Units 022A4.01 Operate/monitor CCS fans 3.6/3.6 N,S 5 h. Shift KC (CCW) Trains 008A4.01 Operate/monitor CCW indications and controls 3.3/3.1 M,S 8 In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Break Main Condenser Vacuum Locally - Unit 2 045A1.06 Monitor parameters following T/G trip 3.3/3.7 P,D,E 4S j. Shift Main Transformer Auxiliaries 062A2.01 Operate loads that would degrade plant operation. 3.4/3.9 P,D 6 k. Place 2A Hydrogen Analyzer in service 028A1.01 Monitor parameters for operating HRPS controls-H2 con. 3.4/3.8 D,E,L,R 5 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room. *Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 < 9 / < 8 / < 4 > 1 / > 1 / > 1 - / - / > 1 > 1 / > 1 / > 1 > 2 / > 2 / > 1 < 3 < 3 / < 2 (randomly selected) > 1 / > 1 / > 1 ES-301, Page 23 of 27 ES-301 Control Room/In-Plant Systems Outline Form ES-301-2 NRC EXAM Facility: Catawba Nuclear Station Date of Examination: May 2014 Exam Level: RO SRO-I SRO-U Operating Test Number: 2014301 Control Room Systems (8 for RO); (7 for SRO-I); (2 or 3 for SRO-U, including 1 ESF) System / JPM Title Type Code* Safety Function a. N/A b. Transfer the ECCS to Cold Leg Recirc 006A4.07 Operate ECCS pumps and valves 4.4/4.4 A,M,EN,L,S 2 c. Cycle RCS PORV for periodic test 010A4.03 Operate/monitor PORV and block valves 4.0/3.8 N,L,S 3 d. N/A e. N/A f. Restoration of Offsite Power 062A4.01 Operate/monitor All breakers in the control room 3.3/3.1 N,S 6 g. N/A h. N/A In-Plant Systems@ (3 for RO); (3 for SRO-I); (3 or 2 for SRO-U) i. Break Main Condenser Vacuum Locally - Unit 2 045A1.06 Monitor parameters following T/G trip 3.3/3.7 P,D,E 4S j. N/A k. Place 2A Hydrogen Analyzer in service 028A1.01 Monitor parameters for operating HRPS controls-H2 con. 3.4/3.8 D,E,L,R 5 @ All RO and SRO-I control room (and in-plant) systems must be different and serve different safety functions; all 5 SRO-U systems must serve different safety functions; in-plant systems and functions may overlap those tested in the control room. *Type Codes Criteria for RO / SRO-I / SRO-U (A)lternate path (C)ontrol room (D)irect from bank (E)mergency or abnormal in-plant (EN)gineered safety feature (L)ow-Power / Shutdown (N)ew or (M)odified from bank including 1(A) (P)revious 2 exams (R)CA (S)imulator 4-6 / 4-6 / 2-3 < 9 / < 8 / < 4 > 1 / > 1 / > 1 - / - / > 1 > 1 / > 1 / > 1 > 2 / > 2 / > 1 < 3 < 3 / < 2 (randomly selected) > 1 / > 1 / > 1 ES-301, Page 23 of 27

FINAL SAMPLE PLAN IS A COMBINATION OF DRAFT SAMPLE PLAN AND ES-401-4.

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 #/ units Back-ward Q= K/A SRO Only 1 L 2 S 2 H 3 S 3 H 3 E S There is no way to know steam pressure. During LOCA, the steam generator can become a heat source as a combination of break flow and ECCS flow removes decay heat. See step 19 of E-1 and associated background. Add to stem that a cooldown is in progress Also change the distractor analysis to say that the steam pressure correlates to Tcold, not core exit temperature. I could not verify the info from Revised Data Book Figure 58 since I do not have it. Licensee included Figure 57 with the Question. Q now Sat. 4 H 3 E S -may not be needed consider deleting. The crew could not possibly know the location or nature of the LOCA. The stem contains enough info to answer the question without this bullet. Q now Sat. 5 L 2 S 6 H 3 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 #/ units Back-ward Q= K/A SRO Only 7 H 3 E S needs refinement. If the time delay is be on. I do not have the Lesson Plan to verify the correct answer, but the last bullet (the OATC notifies . . .) seems to be window dressing. How does the notification change the question or answer? Q now Sat. 8 H 3 U S DRPI actually changes at least twice every 6 steps of bank motion because the two groups in the bank move separately. Since each rod is measured independently, DRPI changes could occur much more frequently. If you want to ask for rod speed, just ask for rod speed. Q now Sat. 9 L 3 S 10 H 3 S 11 H 2 x U S The LCOs were entered when the plant met the associated applicability statements. Required actions are entered in this case, not LCOs. for loss of a single bus seems strange. Would the plant call this a blackout, or is this simply an attempt to make it appear to be a better K/A match? At the plants I am familiar with the most limiting action requirement in this condition is due to the loss of multiple battery chargers. If this is most limiting, it seems that the correct answer should contain this action. KA Match: Discuss KA Match with the licensee. The KA requires testing TS Entry Conditions with a Station Blackout present I.E. loss of both onsite and offsite AC power. Q now Sat. 12 H 3 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 #/ units Back-ward Q= K/A SRO Only 13 H 5 S Are the operators really expected to know the relationship between trip units and channels from memory? Q Sat. 14 H 4 S 15 H 3 E S ons for mitigating any adverse -ended. Since it is not credible that anyone would think that rising RCS pressure and PZR If I think the break is not isolated , then I will continue to try to isolate the leak (c and d close additional valves). But If think that the break is isolated then B is not credible , since it basically says that doing nothing will stop the loss of FWST inventory. Q now Sat. 16 L 3 S 17 L 2 S 18 L 3 S 19 H 3 E S The maximum time allowed to complete the required action of TS 3.1.4 is 5 days. Suggest: All required actions from TS 3.1.4 will be complete if RCCA H-8 is realigned within . . . Q now Sat. 20 H 3 S Have the licensee explain the third bullet. The current wording is confusing, but it may just a lack of understanding on my part. Q Sat.

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 #/ units Back-ward Q= K/A SRO Only 21 H 3 E S The current Catawba Unit 1 TS lists P-6 in units of amps, but the > 6E-11 amp Allowable Value and the 1 E-1 0 amp NOMINAL TRIP SETPOINT value apply to the Westinghouse-supplied compensated ion chamber Intermediate Range neutron detectors. The compensated ion chamber neutron detectors are being replaced with Thermo Scientific-supplied fission chamber neutron detectors. The > 6.6E-6% RTP Allowable Value and the 1 E-5% RTP NOMINAL TRIP SETPOINT value apply to the replacement fission chamber Intermediate Range neutron detectors. Is this MOD complete? See Q22 and evaluate for overlap. Discuss with licensee. O/L OK. 22 H 3 E S It seems that this has overlap with Q. 22. If I do not know how P-6 affects the source range I will miss both of these questions. See Q21 and evaluate for overlap. Discuss with licensee. O/L OK. 23 H 3 U S I do not have to know anything about Catawba area radiation alarms or the high flux at shutdown alarm to eliminate A and B. With a dropped fuel assembly and observed bubbles, one could never eliminate the possibility of an area rad alarm. Any answer that excludes this is not credible. Q now Sat. 24 H 3 S 25 H 3 S 26 H 3 S 27 H 3 E S Knowledge of entry conditions for yellow path procedures is SRO only knowledge. Is this really RO knowledge? Q now Sat.

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 #/ units Back-ward Q= K/A SRO Only 28 L 2 U S Overlap with Q. 5. Q 5 also tests that thermal barrier HX has no cooling after hi-hi containment pressure signal. O/L OK. 29 L 2 X U S If the switch is placed in the RHT position, it is not credible that it continues to send water somewhere else. Q now Sat. 30 L 2 S 31 L 2 S 32 L 2 S 33 H 3 E S 1. Why are both trains affected by a single leak(are they normally x-connected?) 2. Why is only one train showing high radiation if both surge tanks are rising? 3. Why is a 2% rise on one tank 50 gal. (25 gal/%) while a 3% rise on the other tank is 150 gal (50 gal.%)? Q now Sat. 34 L 3 S 35 H 3 S 36 H 3 S 37 H 3 S 38 L 3 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 #/ units Back-ward Q= K/A SRO Only 39 H 3 E S Evidently 1EADA/1VADA means 1EADA AND 1VADA. This is not evident from the question, I had to read the distractor analysis to figure this out. Also, at many Westinghouse plants, the need for P-4 to be met to reset SI is not a function of HOW SI was initiated, but whether an automatic SI signal is currently present. In other words, SI may be able to be reset following an automatic SI if the initiating signal were no longer present. Please verify that the question is technically correct in this regard. Q now Sat. 40 L 5 S Is this memory level knowledge for an RO at Catawba? Addressed. 41 H 2 E S A TS is not entered. A required action is entered. Entering a TS has no defined meaning (it is slang, at best). Consider a wording similar to : LCO 3.6.12 (Ice Bed) is (met or not met). Ice bed operability is based in part on (ice condenser door position or ice bed temperature). Q now Sat. 42 L 2 E S To help plausibility of distractors. The time requirement part would be better worded as Is or Is Not required to be restored within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />. This gets away from the 4 hour4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> requirement, which an applicant may know is beyond what is required from memory. Q now Sat. 43 L 3 S 44 H 3 E S drains open, and an excessive cooldown is prevented by throttling the MSIV bypass valves? It seems more credible to me to suppose that the operator inadvertently fully opens the MSIV bypass valves. Q now Sat.

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 #/ units Back-ward Q= K/A SRO Only 45 L 3 S 46 H 3 E S The referenced procedure CF Flow Venturi Correction Factorof the procedure. Q now Sat. 47 H 3 S 48 H 3 S Have licensee walk examiners through supporting documentation to ensure technical accuracy. OK 49 L 3 U S distractor. Q now Sat. 50 L 3 S 51 L 3 S 52 H 3 S 53 H 3 S 54 L 3 E S Consider removing - the info does not appear to be necessary. Q now Sat. 55 L 3 S 56 H 2 S 57 L 3 S 58 H 3 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 #/ units Back-ward Q= K/A SRO Only 59 H 3 S 60 H 3 S 61 L 3 E S rod drive shafts Q now Sat. 62 L 3 S 63 L 2 E S The paragraph beginning given the following . . . may be unnecessary info. If so, then consider deleting everything before (1) To limit . . . Q now Sat. 64 L 3 S 65 L 3 E S D is not a credible distractor. Seal return only re-directs when the header is isolated. This could not be used for pzr level control. Q now Sat. 66 L 2 S 67 L 2 S 68 L 2 S 69 H 3 S 70 L 2 S 71 L 3 S 72 H 3 S 73 H 3 S 74 L 2 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 #/ units Back-ward Q= K/A SRO Only 75 L 2 S 76 H 3 U S One success path in FR-C.1 is restoration of high head ECCS. If this is the success path, there is no way to know RCS pressure at the time of restoration. There is not enough information in the stem to eliminate high head restoration as a success path. Q now Sat. 77 H 4 S 78 H 3 S 79 H 3 S 80 H 3 S 81 H 3 S 82 H 3 U S This does not seem to be SRO only. I do not see the link to TS. This question does not appear to test TS or TS bases. Q now Sat. 83 H 3 U S TSAIL entry is active or for tracking is another way to say that the LCO is met or not met. With a failed PZR level instrument, the RO should know that 3.3.1 is not met and 3.4.9 is met. Q now Sat. 84 H 3 S 85 H 3 S 86 H 3 E S Explain further why this may be SRO. The justification says that this is linked to TS, but the screening block for SRO only does not appear to be met. Is this an SRO-only task at Catawba? If so, place that in the justification with the appropriate 55.43 link. Q now Sat.

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 #/ units Back-ward Q= K/A SRO Only 87 H 3 S 88 H 3 S 89 H 3 S 90 H 3 S 91 H 3 S 92 H 3 S 93 H 3 S 94 H 3 S 95 H 3 S Q now Sat. 96 H 3 S 97 H 3 S 98 H 3 S 99 H 3 S 100 H 3 S