ML062750232
| ML062750232 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 01/20/2006 |
| From: | Caruso J Operations Branch I |
| To: | |
| Sykes, Marvin D. | |
| References | |
| Download: ML062750232 (20) | |
Text
Calvert Cliffs Nuclear Plant FINAL Submital II Calvert and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, the Tier Totals in each WA category shall not be less than two).
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. Systemdevolutions within each group are identified on the associated outline; systems or evolutions that do not apply at the facility should be deleted and justified; operationally important, site-specific systems that are not included on the outline should be added. Refer to ES-401, Attachment 2, for guidance regarding the elimination of inappropriate WA statements.
group before selecting a second topic for any system or evolution.
selected. Use the RO and SRO ratings for the RO and SRO-only portions, respectively.
- 2. The point total for each group and tier in the proposed outline must match that specified in the table.
- 4. Select topics from as many systems and evolutions as possible; sample every system or evolution in the
- 5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be E.* Select SRO topics for Tiers 1 and 2 from the shaded systems and WA categories.
- 7. The generic (G) WAS in Tiers 1 and 2 shall be selected from Section 2 of the WA Catalog, but the topics must be relevant to the applicable evolution or system.
- 8. On the following pages, enter the WA numbers, a brief description of each topic, the topics importance ratings (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 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
- 9. For Tier 3, selectiopics from Section 2 of the WA Fsalog, and enter the WA numbers, descriptions, IRs, anc point totals (#) on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.
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. - - A Summary For Official Use Only
Calvert Cliffs Nuclear Plant EAPEs T I GI For Official Use Only
Calvert Cliffs Nuclear Plant EAPEs T1 G1 For Official Use Only
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Calvert Cliffs Nuclear Plant ing as they apply to the 2 Adherence to appropriate the facility*s license and EAPEs TI G2 For Official Use Only
Calvert Cliffs Nuclear Plant EAPEs T I G2 For Official Use Only
Calvert Cliffs Nuclear Plant System # / Name 003 Reactor Coolant Pump
// 004 Chemical Volume Control 004 Chemical Volume Control 005 Residual Heat Removal 006 Emergency Core Cooling 007 Pressurizer Relief/Quench Tank 007 Pressurizer RelieWQuench Tank 008 Component Cooling Water 008 Component Cooling Water 010 Pressurizer Pressure Control 010 Pressurizer Pressure Control I
012 Reactor Protection SYSTEMS T2 GI For Official Use Only
Calvert Cliffs Nuclear Plant 013 Engineered Safety Features 059 Main Feedwater 11062 AC Electrical Distribution I
I 11063 DC Electrical I
I water flow 3.2 3.3 SYSTEMS T2 G1 For Official Use Only
Calvert Cliffs Nuclear Plant SYSTEMS T2 G1 For Official Use Only
Calvert Cliffs Nuclear Plant It System # / Name I
01 1 Pressurizer Level Control 11016 Non-nuclear Instrumentation :
017 lncore Temperature Monitor 027 Containment Iodine Removal 028 Hydrogen Recombiner and Purge Control 029 Containment Purge 033 Spent Fuel Pool Cooling 034 Fuel Handling Equipment 035 Steam Generator SYSTEMS T2 G2 For Official Use Only
Calvert Cliffs Nuclear Plant SYSTEMS T2 G2 For Official Use Only
Calvert Cliffs Nuclear Plant Generics For Official Use Only
Calved Cliffs Nuclear Plant 3
Radiation Protection Generics For Official Use Only
Calvert Cliffs Nuclear Plant Category Conduct of Operations Equipment Control Generics For Official Use Only
Calvert Cliffs Nuclear Plant Generics For Official Use Only
Calvert Cliffs Nuclear Plant Group I
Randomly Selected KIA Tier and I
I Reason for Rejection T1 G 1 T I G 1 T1G2 T1G2 T1 G2 T1G2 T2G1 000027AA2.15 AA2.01 Conditions which will cause an increase in PZR level 3.4 3.8 This generic WA was alreadysampled in the generic section - tested in question 67 (2.1.14 Knowledge of system status criteria which require the notification of plant personnel. (CFR: 43.5 / 45.12) 2.513.3). The Chief Examiner directed that we shift WAS - systematically reselected EK1 Knowledge of the operational implications of the following concepts as they apply to the ATWS: (CFR 41.8/41.10/45.3) EKl.01 Reactor nucleonics and thermohydrualic behavior (2.8 3. I )
The rod motion lights at CCNP have been removed from service. Randomly reselected AK2.01 Knowledge of the interrelations between the Continuous Rod Withdrawal and the following: (CFR 41.7/45.7) AK2.01 Rod bank step Supressed G2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures. (CFR 4 1.10 / 43.2 /45.6) because it was deemed t tbe inappropriate for SRO level questions by the Chief Examiner. Randomly reselected AA2. Ability to determine and interpret the following as they apply to the Inoperable /Stuck Control Rod: (CFR: 43.5 / 45.13) AA2.03 Required actions if more than one rod is stuck or inoperable 3.5 4.4 Systematically reselected from AK3. Knowledge of the reasons for the following responses as they apply to the Loss of Intermediate Range Nuclear Instrumentation: (CFR 41.5,41.10/45.6/45.13) AK3.01 Termination of startup following loss of intermediate range instrumentation 3.2 3.6 because after spending the resources to develop a question for this WA, it was subsequently determined that the question was at the SRO level. It would have been inappropriate to develop an RO question for this WA if the SRO question was essentially on the same topic (SRO(l)s take the RO test and they would have 2 similar questions. Decided to systematically reselect AK2.01 because there were only 2 AK2s in the Tier 1 sample plan and there were 7 AK3s. AKZ. Knowledge of tht interrelations between the Loss of Source Range Nuclear Instrumentation and the following: (CFR 4 1.71 45.7)
AK2.01 Power supplies, including proper switch positions 2.7* 3.1 Supressed G2.4.4 Ability to recognize abnormal indications for system operating parameters which are entry-level conditions for emergency and abnormal operating procedures. (CFR 41.10 /43.2/45.6) because it was deemed t tbe inappropriate for SRO level questions by the Chief Examiner. Randomly reselected AA2. Ability to determine and interpret the following as they apply to the (Excess RCS Leakage) (CFR: 43.5/45.13) A M. I Facility conditions and selection of appropriate procedures during abnormal and emergency operations. IMPORTANCE RO 2.7 SRO 3.5 There are no seal return valves at Calvert Cliffs. Randomly reselected A4.06 "RCP parameters 2.9* 2.9" There are no chemical addition tanks in the containent spray flow path - CCNP used Na304 baskets instead.
000029G2.1.14 000001AK2.05 counters 2.0 3.2 000005G2.4.4 000032AK3.01 CUA-16 G2.4.4 003A4.07 T2G 1 I 026A.Z. 05 I Randomly reselected A2.02.
T2G1 IO6lK2 0.9 IThere are no diesel driven AFW pumps at Calvert Cliffs. Randomly reselected K2.02.
ES 401-4 For Official Use Only
Calvert Cliffs Nuclear Plant Randomly Selected K/A Tier and Group T2G 1 T2G 1 T2G 1 T3 Reason for Rejection The process radiation monitors only measure gasseous, liquid or particulate effluents. The nature of these processes are such that they do not respond to gamma sources at various distances from the detectors. It is not possible to vary the source distance on a PRM. K5.02 was an inappropriate WA for Calvert Cliffs. Randomly reselected WA K5.03 Relationship between radiation intensity and exposure limits 2.9* 3.4 - Unable to prepare a question within a reasonable amount of time - Systematically reselected K4.01 Release termination when radiation 06 1 K4.05 06862.7.30 G2.3.4 exceeds setpoint 4.0 4.3 There is no AFW swapover between MFW and AFW for a low suction pressure condition. Unable to understand 073K50.YK5.03 the K./A. Randomly reslected K4.13.
There were no local controls for the liquid Rad waste system that were within the purvue of operators to locate and operate. Unable to write an operationally valid question. Shifted to K4.01 Knowledge of design feature(s) andor interlock(s) which provide for the following: (CFR: 4 1.7) K4.01 Safety and environmental precautions for handling hot, acidic. and radioactive liquids 3.4 4.1 The decision was made by the Chief Examiner that 2 SRO test questions from the radiation control section constituted over-sampling GET level knowledge. Elected to use a rejected RO question (#24) that had been rejected because it was SRO-level knowledge - for the SR) exam. Shifted WAS from G2.3.4 Knowledge of radiation exposure limits and contamination control, including permissible levels in excess of those authorized.
(CFR: 43.4 / 45.10) IMPORTANCE RO 2.5 SRO 3.1 to G2.1.12 Ability to apply technical specifications for a system. (CFR: 43.2/43.5/45.3) IMPORTANCE RO 2.9 SRO 4.0 ES 401 -4 For Official Use Only