ML030780097
| ML030780097 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 01/27/2003 |
| From: | Pierson J FirstEnergy Nuclear Operating Co |
| To: | NRC/RGN-III |
| References | |
| 50-440/03-301 50-440/03-301 | |
| Download: ML030780097 (30) | |
Text
OUTLINE SUBMITTAL WITH NRC COMMENTS FOR THE PERRY EXAMINATION - JAN/FEB 2003
f- ,
FENOC ý Perry Nuclear Power Plant 10 Center Road FirstEnergyNuclear OperatingCompany P0. Box 97 Perry, Ohio 44081 August 8, 2002 PY-CEI/OIE-0567L United States Nuclear Regulatory Commission 801 Warrenville Road Lisle, Illinois 60532-4351 Attention: Mike Bielby, Chief Examiner Operations Branch Region III Perry Nuclear Power Plant Docket No. 50-440 NRC Initial License Examination Outline Submittal
Dear Mr. Bielby:
In accordance with NUREG-1021, ES-201, enclosed are the required examination materials that document the NRC initial license examination outline for the Perry Nuclear Power Plant.
The examination materials are being developed in accordance with the guidelines specified in NUREG-1021, Revision 8, Supplement 1.
It is hereby requested that these examination materials be withheld from public disclosure until after the initial license examinations are completed. The tentative examination start date is January 27, 2003.
In addition to Form ES-201-2, the following additional forms are also included to complete the examination outline:
Written Examination Form ES-401-1 for a BWR SRO Examination Form ES-401-5 for a BWR SRO Examination Form ES-401-10 for a BWR SRO Examination Form ES-401-2 for a BWR RO Examination Form ES-401-5 for a BWR RO Examination Form ES-401-10 for a BWR RO Examination Administrative Topics Form ES-301-1 for a BWR SRO Examination Form ES-301-1 for a BWR RO Examination Memo which describes the safety significance of the proposed SRO and RO Admin JPMs TO
I I PY-CEI/OIE-0567L August 8, 2002 Page 2 of 2 Control Room Systems and Facility Walkthrough (JPMs)
Form ES-301-2 for a BWR SRI(l)/RO Examination Form ES-301-2 for a BWR SRO(U) Examination Memo which describes the safety significance of the proposed SRO and RO JPMs Simulator Scenarios Form ES-D-1 for 5 proposed simulator scenarios Memo which describes the safety significance of each proposed simulator scenario Justification Memo Annotates the justifications for deleting various items from the examination outlines.
OTG: 18, Initial License Examination, Development, Validation, and Administration Describes the sampling process used to generate the Written Examination outlines and the security procedures incorporated for the entire examination process.
As a follow-up to our phone conversation on July 17, 2002, in addition to the materials required for the outline submittal, samples of examination materials are included for your review and feedback.
You may contact Joseph D. Pierson at (440) 280-5277 ifyou have any further questions.
Sincerely, Joseph D. Pierson Robert J. Sochia Nuclear Qualification Instructor - Author Facility Representative
ES- 201 Examination Outline Forrn ES-201-2 Ouality Checklist Facility: Date of Examination:
Item Task Description Initials a b" c#
I
- 1. a. Verify that the outline(s) fit(s) the appropriate model per ES-401.
W R b. Assess whether the outline was systematically and randomly prepared in accordance with 4- /
I Section D.1 of ES. 401 and whether all K/A categories are appropriately sampled.
T T c. Assess whether the outline over-emphasizes any systems, evolutions, or generic topics.
N d, Assess whether thejustifications for deselected or rejected K/A statements are appropriate. - A J,* I
- 2. a. Using Form ES. 301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, and major transients. 0 S
I b. Assess whether there are enough scenario sets (and spares) to test the projected number and M mix of applicants in accordance with the expected crew composition and rotation schedule without compromising exam integrity; ensure each applicant can be tested using at least one new or significantly modified scenario, that no scenarios are duplicated from the applicants' audit test(s)
- and scenarios will not be repeated over successive days.
- c. To the extent possible, assess whether the outline(s) conform(s) with the qualitative and quantitative criteria specified on Form ES- 301-4 and described in Appendix D.
- 3. a. Verify that:
(1) the outline(s) contain(s) the required number of control room and in-plant tasks, W (2) no more than 30% of the test material is repeated from the last NRC examination, I (3)* no tasks are duplicated from the applicants' audit test(s), and,*
T (4) no more than 80% of any operating test is taken directly from the licensee's exam banks. "4s M/e
- b. Verify that:
(1) the tasks are distributed among the safety function groupings as specified in ES-301, (2) one task is conducted in a low-power or shutdown condition, (3) 40% of the tasks require the applicant to implement an alternate path procedure, (4) one in- plant task tests the applicant's response to an emergency or abnormal condition, and 5[I ,
(5) the in-plant walk-through requires the applicant to enter the RCA.
- c. Verify that the required administrative topics are covered, with emphasis on performance based activities.
- d. Determine if there are enough different outlines to test the projected number and mix of * ** .
applicants and ensure that no items are duplicated on successive days.
- 4. a. Assess whether plant-specific priorities (including PRA and IPE insights) are covered in the appropriate exam section.
G E b. Assess whether the 10 CFR 55.41/43 and 55.45 sampling is appropriate. - A*"
N E c. Ensure that K/A importance ratings (except for plant-specific priorities) are at least 2.5. ' ,,'
R A d. Check for duplication and overlap among exam sections. R 4f5,S L e. Check the entire exam for balance of coverage.
Print Nam / Signature . Date
- a. Author )c*,e-4 0, , /
- b. Facility Reviewer (*) 7,*'- ,','. / - ," 2
- c. NRC Chief Examiner (#) 'v41Cftoe &i e t y1 /M3
/ M A Al
- d. NRC Supervisor -- e,'&!UfX, Note:
- Not applicable for NRC-developed examinations.
- Independent NRC reviewer initial items in Column "c;" chief examiner concurrence required.
23 of 24 NUREG-1021, Revision 8, Supplement 1
ES-301 Administrative Topics Outline Form-ES-301-1 Facility: Perry Date of Examination: 1/27/2003 Examination Level:R SRO Operating Test Number: 2003-301 Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Overtime K/A 2.1.2 (3.0) - Knowledge of Operator Responsibilities during all Modes of Plant Guidelines Operation JPM: Evaluate Proposed Work Schedule Against Established Overtime Guidelines Electrical Print K/A 2.1.24 (2.8) - Ability to Obtain and Interpret Station Electrical and Mechanical Reading Drawings JPM: Determine the Effect of Relay 1E5 IA-K51 Removal A.2 Independent K/A 2.2.13 (3.6) - Knowledge of Tagging and Clearance Procedures Verification of Tags JPM: Perform Independent Verification of Tag Placement A.3 Contamination K/A 2.3.4 (2.5) - Knowledge of Radiation Exposure Limits and Contamination Control /
Control Including permissible Levels in Excess of Those Authorized JPM: Determine Dress Out Requirements for a Contaminated Area A.4 Personnel 2.4.39 (3.3) - Knowledge of RO's Responsibilities in Emergency Plan Implementation Accountability JPM: Perform Site Accountability Actions for Control Room Staff NUREG-1021, Revision 8, Supplement 1
ES-301 Administrative Topics Outline Form-ES-301-1 Facility: Perry Date of Examination: 1/27/2003 Examination Level: RO R Operating Test Number: 2003-301 Administrative Describe method of evaluation:
Topic/Subject 1. ONE Administrative JPM, OR Description 2. TWO Administrative Questions A.1 Overtime K/A 2.1.2 (4.0) - Knowledge of Operator Responsibilities during all Modes of Plant Guidelines Operation JPM: Evaluate Proposed Work Schedule Against Established Overtime Guidelines Notification / K/A 2.1.17 (3.6) - Ability to Make Accurate / Clear and Concise Verbal Reports Reporting Requirements JPM: Make a Four Hour (10CFR50.72 Non-Emergency) Notification A.2 Containment K/A 2.2.15 (2.9) - Ability to Identify and Utilize As-Built Design and Configuration Penetration Change Documentation to Ascertain Expected Current Plant Configuration Isolation and Operate the Plant JPM: Controlling Containment Penetration to Meet the Isolation Requirements of Tech Spec 3.6.1.3 A.3 Contamination K/A 2.3.4 (3.1) - Knowledge of Radiation Exposure Limits and Contamination Control /
Control Including permissible Levels in Excess of Those Authorized JPM: Determine Dress Out Requirements for a Contaminated Area A.4 E-Plan Protective K/A 2.4.44 (4.0) - Knowledge of Emergency Plan Protective Action Recommendations Action Recommendation JPM: Issue a Revised Off-Site Protective Action Recommendation (PAR)
Change Following a Change in Meteorological Conditions NUREG-1021, Revision 8, Supplement 1
ES-301 Control Room Systems and Facility Walk-Through Test Outline Form-301-2 Facility: Perry Date of Examination: 1/27/2003 Exam Level: ; SRO(U) Operating Test No.: 2003-301 B.1: Control Room Systems System / JPM Description Type Safety Code* Function
- a. Withdraw Control Rod (Substitute Position) 201005 N /A / S 1
- d. Remotely Transfer Bus EH12 to the Alternate Preferred Source from the D/S 6 Diesel Generator 264000
- e. Shift Reactor Recirculation Pump from Slow to Fast Speed 202001 D/L/S 4
- f. Shift EHC Hydraulic Pumps 241000 N/S 3
- g. Startup Area Radiation Monitor to Full Operation 272000 D/S 7 B.2: Facility Walk-Through
- b. Initiate Control Room Subfloor CO 2 from Outside Control Room 286000 D/A 8
- c. Level Control Using RCIC from the Remote Shutdown Panel 295016 D/L 7
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator, (L)ow-Power, (R)CA NUREG-1021, Revision 8, Supplement 1
ES-301 Control Room Systems and Facility Walk-Through Test Outline Form-301-2 Facility: Perry Date of Examination: 1/27/2003 Exam Level: RO / SRO(I) < Operating Test No.: 2003-301 B.1: Control Room Systems System / JPM Description Type Safety Code* Function a.
- e. Shift Reactor Recirculation Pump from Slow to Fast Speed 202001 D/L/S 4 f.
g.
B.2: Facility Walk-Through
- c. Level Control Using RCIC from the Remote Shutdown Panel 295016 D/L 7
- Type Codes: (D)irect from bank, (M)odified from bank, (N)ew, (A)lternate path, (C)ontrol Room, (S)imulator, (L)ow-Power, (R)CA NUREG-1021, Revision 8, Supplement 1
Appendix D Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 2 Op-Test No.: 2003-301 Examiners: Operators:
Initial Conditions: The plant is operating at 100% power. RHR A is in secured status for preventive maintenance on the pump breaker. RHR A was declared inoperable five hours ago per Tech. Spec.3.5.1, Action A; 3.6.1.7, Action A; and 3.6.2.3, Action A. The OPRMs are functional but are inoperable per Tech. Spec. 3.3.1.3. Required Action A.3 has been implemented. HPCS System operation is scheduled to support flow rate testing. Control rods are at step 79, all rods out. 101-3, Section 4.5, Step 35.
Turnover: 1. BOP operator place HPCS in full flow test mode to the suppression pool. The RSE is standing by to take flow measurements locally. Suppression Pool water is Transfer Quality and a HPCS system flush at the completion of the test is not required. HPCS ESW and HPCS Pump Room Cooler are in operation. 2. Maintain 100% power.
Event Malf. No. Event Event No. Type* Description 1 N (BOP) Start HPCS in Full Flow Test Mode to the Suppression Pool (TS 3.5.1. B and C)
N (SRO) 2 CP03: C (BOP) HPCS Pump Flow Degradation/Shutdown HPCS (2 minute ramp) 1 E22C0001 C (SRO) 100%
3 ADOIN C (BOP) ADS/SRV B21-F047H Cycling (TS 3.5.1.E, F and H /TS 3.0.3)
C (SRO)
R (RO) Lower reactor power < 90% using Recirc flow R(SRO)
Reactor Narrow Range Level Transmitter C34-NO04A Offset High (3 minute 4 PT02: I (RO) ramp) (ORM 6.2.1.3) 1C34N0004A I (SRO) 17%
5 RF FW66 C (RO) RFPT A Spurious Trip / Reactor Recirculation FCV B Runback Failure (TS 3.4.1)
TH12B C (SRO) 6 ED061 Loss of 480Vac Bus F-1-E TC05 Turbine Control EHC leak / Main Turbine trip and reactor scram 10%
7 RD15 M (All) ATWS (failure of RPS and ARI to automatically shutdown the reactor)
SL01A SLC Squib Valves Fail to Fire (includes indicating lamp overrides to support SLI01B failure mode)
CB01:
8 1N27CO001A C Loss of All Feedwater Capability (all RFBPs trip)
CB01:
1N27C00011B CB01:
1N27CO001C CB01:
1N27C0001D 9 M (All) RPV Emergency Depressurization / Inject with low pressure ECCS to maintain adequate core cooling klr)ormal, ýR)eactivay, (I)nstrumenl, (t)omponent, [ivi)ajor NUREG-1021, Revision 8, Supplement 1
Appendix D Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 3 Op-Test No.: 2003-301 Examiners: Operators:
Initial Conditions: Reactor startup is in progress with the plant at 5% of rated power. The OPRMs are functional but are inoperable per Tech. Spec. 3.3.1.3 (PLCO). Control Rods at step 48, Gangs 40 and 39 at position 08.
101-1, Section 4.9, Step 1. Service Water Pump C is tagged out for motor refurbishment.
Turnover: 1. Continue plant startup. Withdraw control rods to 10% power, transfer the Reactor Mode Switch to RUN, and continue power ascension. All required MODE change paperwork has been reviewed and approved. 2.
BOP operator shift NCC Pumps from A and B running, to A and C running.
Event Malf. No. Event Event No. Type* Description 1 N (BOP) Shift NCC Pumps from A and B running, to A and C running N (SRO) 2 RD01 :R1 043 R (RO) Increase reactor power to 10% using control rods 8% R(SRO)
C (RO) Control rod 10-43 stuck at position 8 C (SRO) 3 NM02H I (RO) IRM H Failure Upscale 100% I (SRO) (TS 3.3.1.1 and ORM 6.2.3) 4 RD1 7A C (BOP) CRDH Pump A trip due to loss of lube oil / perform CRD Pump trip recovery 50% C (SRO)
RD05R5443 Accumulator fault HCU 54-43 (TS 3.1.5) (1 minute time delay)
RD05R2215 Accumulator fault HCU 22-15 (TS 3.1.5) (2 minute time delay) 5 CP02: C (BOP) Service Water Pump B trip due to shaft seizure OP41CO01B C (SRO) 6 bat M (All) Seismic Event or/seismic_2 TH02A / TH02B Recirc Loop pipe rupture and reactor scram 100% (TH02A - 6 minute time delay &5 minute ramp)
(TH02B - 8 minute time delay &5 minute ramp)
MV08: NCC Drywell Isolation Valve, P43-F215, fails closed OP43F0215 7 bat C Loss of all RPV level indication ms/losslevel2 Emergency Depressurization / RPV Flooding to restore and maintain adequate core cooling
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 8, Supplement 1
Appendix D Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 4 Op-Test No.: 2003-301 Examiners: Operators:
Initial Conditions: The plant is operating at 80% power. RHR A is in secured status for preventive maintenance on the pump breaker. RHR A was declared inoperable five hours ago per Tech. Spec.3.5.1, Action A; 3.6.1.7, Action A; and 3.6.2.3, Action A. The OPRMs are functional but are inoperable per Tech. Spec. 3.3.1.3. Required Action A.3 has been implemented. Performing a normal plant shutdown per 101-3, Section 4.6 step 2. 101-3, Step 4.6.4a, has been performed. Control rods are at step 62, position 36.
Turnover: BOP operator shift AEGTS trains from A to B running. Continue the plant shutdown by reducing power using Recirculation Flow to 58 Mlbm/hr. Hold power there for Reactor Engineering.
Event Malf. No. Event Event No. Type* Description 1 N (BOP) Shift AEGTS trains from A to B N (SRO) 2 R (RO) Reduce Reactor Power using Recirculation Flow R(SRO) 3 CN02: I (BOP) RFPT A Lube Oil Temp controller failure in Auto mode 1P44R0450 I (SRO) 0%
4 NMO4D I (RO) APRM D failure upscale (TS 3.3.1.1.A and ORM 6.2.1.B) 125% I(SRO) 5 CN03:1C34R0 I (RO) Reactor Feed Pump B controller oscillations (1 minute ramp) 601B I (SRO) 20%
6 CP02: C(BOP) TBCC Pump A trip (start standby TBCC Pump) 1P44C0001A C(SRO)
SWO3 TBCC System Process Piping Leakage (2 minute time delay and 5 minute ramp) 10% Fast Reactor Shutdown required 7 TH28 M (All) MSL Break in Drywell 1%
PC01A DW-CNTMT Bypass Leakage (to be modified in Event #8) 0%
CB04: C (BOP) RHR Pump B fails to auto start on Drywell high pressure (required for 1E12C0002B C (SRO) Containment Spray mode) 8 CB01: C RHR Pump B trips when flow is aligned to containment spray 1E12C0002B RPV emergency depressurization to control Containment pressure
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 8, Supplement 1
Appendix D Scenario Outline Form ES-D-1 Facility: Perry Scenario No.: 5 Op-Test No.: 2003-301 Examiners: Operators:
Initial Conditions: The plant is operating at 45% power. SLC Pump A is Red Tagged OOS for a coupling alignment. SLC A was declared inoperable per Tech Spec 3.1.7, Condition A, 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> ago.
SPCU is operating through the SPCU Demineralizer, returning via RHR A. SOI-G42, Sections 4.1 and 5.1 were performed. The OPRMs are functional but are inoperable per Tech Spec 3.3.1.3. Required Action A.3 has been implemented. Performing a normal plant startup per 101-3, Section 4.5, step 11.
101-3, steps 4.5.16 and 4.5.18 have been performed. Control Rods are at step 71, position 36 Turnover: Secure from SPCU operations per SOI-G42. Continue the plant startup per 101-3. Withdraw control rods to 50% power and hold for Reactor Engineering.
Event Malf. Event Event No. No. Type* Description 1 N(BOP) SPCU Pump Shutdown from the Normal SPCU to Suppression Pool Return Line N(SRO) 2 R(RO) Withdraw Control Rods to increase reactor power to 50%
R(SRO) 3 RD02R5431 C(RO) Uncoupled Control Rod 54-31 C(SRO) 4 MC04A C(BOP) Cirw Pump A Suction Chamber Low Level / Cirw Pump A shutdown C(SRO) 5 MS1 1 C(BOP) Steam Seal Header Pressure Control Valve failure closed I Manual control of C(SRO) Steam Seal Header pressure 6 MV08, MV03 C Loss of NCC Cooling Water flow to Drywell loads (P43-F400 fails closed) 0P43F0400 7 RY02:1 C71 I(RO) Failure of RPS to shutdown the reactor/Manual initiation of ARI K14A, C, E, G I(SRO) 8 RD15 M(AII) ATWS - 50%
9 MS05A,B,C, C MSIV closure / Loss of Main Condenser D,E,F,G,H MV03:1 B21 F 0016,19 1 1 f +
I 1- 1
- (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor NUREG-1021, Revision 8, Supplement 1
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, Sl)
Facility: Perry Date of Exam: 1/03 Exam Level: SRO K/A Category Points Tier Group Point K K K K K K A A A A G Total 1 2 3 4 5 6 1 234
- E m e rg e n cy & 2 3 3 4 3 3 1 1 Abnormal Plant 2 3 3 4 ".
Evolutions Tier 8 10 7 8 7 3 43 Totals I I I I I 1 1 2 1 3 1 3 2 2 4 2 2 23 2.
Plant 2 3 1 2 1 2 1 0 1 0 2 0 13 Systems 3 0 0 0 1 1 0 1 1 0 0 0 4 Tier 4 3 3 5 4 4 3 4 4 4 2 40 Totals I
- 3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 17 4 5 2 6 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., 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 exam must total 100 points.
- 3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category/tier.
6.* The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) Imp. Points 1 2 3 1 2 295003 Partial or Complete Loss of AC Pwr / 6 .06 2.4.22 Containment isolation / Knowledge of the bases for prioritizing safety 3.7/4.0 2 functions during abnormal/emergency operations 295006 SCRAM / 1 .03 .03 Reactivity Control / CRD hydraulic system 4.0/3.8 2 295007 High Reactor Pressure / 3 .02 Reactor power 4.1 1 295009 Low Reactor Water Level / 2 .03 Recirculation system 3.2 1 295010 High Drywell Pressure / 5 .03 .01 Drywell/containment differential pressure: Mark III/ Leak rates 3.1/3.8 2 295013 High Suppression Pool Temp. / 5 .01 Suppression pool cooling 3.7 1 295014 Inadvertent Reactivity Addition / 1 .03 Cause of reactivity addition 4.3 1 295015 Incomplete SCRAM / 1 .07 Neutron monitoring system 3.7 1 295016 Control Room Abandonment / 7 2.1.20 Ability to execute procedure steps 4.2 1 295017 High Off-site Release Rate / 9 .04 Plant ventilation systems 3.3 1 295023 Refueling Accidents Cooling Mode / 8 .03 Inadvertent criticality 4.0 1 295024 High Drywell Pressure / 5 .07 PCIS/NSSSS 3.9 1 295025 High Reactor Pressure / 3 .11 Reactor water level 3.6 1 295026 Suppression Pool High Water Temp. / 5 .02 Suppression pool level 3.9 1 295027 High Containment Temperature / 5 .02 Containment spray 3.2 1 295030 Low Suppression Pool Water Level / 5 .04 Suppression pool make-up system 4.0 1 295031 Reactor Low Water Level / 2 .01 .01 Adequate core cooling / Low pressure coolant injection (RHR) 4.7/4.4 2 295037 SCRAM Condition Present and Power .07 .10 Shutdown margin / Reactor pressure 3.8/4.1 2 Above APRM Downscale or Unknown / 1 295038 High Off-site Release Rate / 9 .03 .04 Meteorological effects on off-site release/Emergency depressurization 3.8/3.9 2 500000 High Containment Hydrogen Conc. / 5 .01 Primary containment hydrogen instrumentation 3.3 1 K/A Category Totals: 5 7 1 5 4 2 Group Point Total: 26
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) Imp. Points 1 2 3 1 2 295001 Partial or Complete Loss of Forced Core .05 Jet pump operability 3.4 1 Flow Circulation / 1 & 4 295002 Loss of Main Condenser Vacuum / 3 .06 Reactor/turbine pressure regulating system 3.1 1 295004 Partial or Total Loss of DC Pwr / 6 .05 1 Loss of breaker protection 3.4 1 295005 Main Turbine Generator Trip / 3 .02 Recirculation pump downshift/trip 3.5 1 295008 High Reactor Water Level / 2 Randomly Deleted 295011 High Containment Temperature / 5 .01 Containment pressure 4.1 1 295012 High Drywell Temperature / 5 .01 Increased drywell cooling 3.6 1 295018 Partial or Total Loss of CCW / 8 .02 System loads 3.4 1 295019 Partial or Total Loss of Inst. Air / 8 2.4.11 Knowledge of abnormal condition procedures 3.6 1 295020 Inadvertent Cont. Isolation / 5 & 7 .03 Containment ventilation system 3.1 1 295021 Loss of Shutdown Cooling / 4 .02 RHR/shutdown cooling system flow 3.4 1 295022 Loss of CRD Pumps / 1 .03 Accumulator pressures 3.4 1 295028 High Drywell Temperature /5 Randomly Deleted 295029 High Suppression Pool Water Level / 5 .02 Lowering suppression pool water level 4.0 1 295032 High Secondary Containment Area .03 Isolating affected systems 3.9 1 Temperature / 5 295033 High Secondary Containment Area .01 Area radiation monitoring system 4.0 Radiation Levels / 9 295034 Secondary Containment Ventilation High .05 Fuel building ventilation 3.7 1 Radiation / 9 295035ISecondary Containmenit Hig Difrnt.i 2Pressue1 4Not Applicable toPerry~
295036 Secondary Containment High Sump/Area .02 Water level in the affected area 3.1 1 Water Level / 5 600000 Plant Fire On Site / 8 .01 Fire Classifications by type 2.8 1 K/A Category Point Totals: 3 3 14133 1133111 Group PointTotal: 17
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, Si)
Plant Systems - Tier 2/Group 1 System # / Name K K K K K K A A A A G K/A Topic(s) Imp. Points 1 2 3 4 5 6 1 2 3 4 Ability to locate control room 201005 RCIS 2.1.31 switches/controls and indications and to 3.9 1 determine that they are correctly reflecting the desired plant lineup 202002 Recirculation Flow Control .01 Flow control valve operation 3.4 1 203000 RHR/LPCI: Injection Mode .03 Emergency generator 3.9 1 206000 HPCI ,>NotApplicablie -. to Perr 207000 Isolation ýEmerqenoy Condenser Not Applicable to Perry 209001 LPCS .05 System venting 2.5 1 209002 HPCS .06 Lights and alarms 2.8 1 211000 SLC .09 SBLC system lineup 4.1 1 Close/open SCRAM instrument volume 212000 RPS .12 vent and/or drain valves 3.9 1 215004 Source Range Monitor .04 Upscale and downscale trips 3.7 1 Display control system / APRM (gain 215005 APRM / LPRM .08 1 .07 adjustment factor) 3.0/3.4 2 216000 Nuclear Boiler Instrumentation .10 Automatic recirculation pump speed 3.1 1 control 217000 RCIC .04 Manually initiated controls 3.6 1 218000 ADS .03 Loss of air supply to ADS valves 3.6 1 223001 Primary CTMT and Auxiliaries .09 Drywell cooling fans 2.9 1 223002 PCIS/Nuclear Steam Supply Shutoff .01 1 1 Redundancy 3.2 1 226001 RHR/LPCI: CTMT Spray Mode .07 Pump start 3.5 1 Allows tor SRV operation trom more than 239002 SRVs .05 one location 3.7 1 Knowledge ot the purpose and tunction of 241000 Reactor/Turbine Pressure Regulator 2.1.28 major system components and controls 3.3 1 259002 Reactor Water Level Control .04 Recirculation system 3.0 1 261000 SGTS .01 A.C. electrical distribution 3.0 1 262001 AC Electrical Distribution .01 Off-site sources of power 3.6 1 264000 EDGs .06 Cooling water system operation 3.2 1 290001 Secondary CTMT .03 SBGT 4.0 1 K/A Category Point Totals: 2 1 3 1 3 2 4 2 2 Group PointTotal: - 23
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, Si)
Plant Systems - Tier 2/Group 2 System # / Name K K K K K K A A A A G K/A Topic(s) Imp Points 1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic .03 Control rod drive mechanisms 3.2 1 201002 S *M Not App licable to Per*
201004 RSCSF NotApplicable to Perr 201006 RWM NotApplicable to Perr 202001 Recirculation .04 D.C. power 28 1 204000 RWCU - - Randomly
...... Deleted . __..
205000 Shutdown Cooling .02 Valve operation 2.9 1 214000 RPIS - - - -- - - - -Not Applicable to Perry 215002 RBM Not Applicable to Perry 215003 IRM .01 1 Detector operation 2.7 1 219000 RHR/LPCI: Torus/Pool Cooling Mode .06 Valve logic reset following automatic 3.7 1 initiation of LPCI/RHR in injection mode 230000 RHRILPCI: Torus/Pool Spray Mode -- -- -_ Not Applicable to Perry 234000 Fuel Handling Equipment Deleted .Randomy 239003 MVSIV Leakage Control ___Not Applicable to Perry ____
245000 Main Turbine Gen. and Auxiliaries .03 Reactor power 4.0 1 259001 Reactor Feedwater .07 A.C. electrical power 2.9 1 262002 UPS (AC/DC) .19 Power range neutron monitoring system 3.1 1 263000 DC Electrical Distribution Randomly Deleted 271000 Offgas - _ __Randomly Deleted 272000 Radiation Monitoring .12 Refuel floor handling accidents/operations 4.0 1 286000 Fire Protection .05 Fire protection capability during loss of off- 3.8 1 site power 290003 Control Room HVAC .04 Environmental conditions 3.0 1 300000 Instrument Air .01 Instrument air compressor 2.8 1 400000 Component Cooling Water .04 Reactor coolant system in order to 3.1 1 determine source(s) of RCS leakage into I I_ CCWS K/A Category Point Totals: I3 1 112 l1 2 1 0 1 1 I02 0 Group PointTotal: 13
ES-401 BWR SRO Examination Outline Form ES-401-1 (R8, Si)
Plant Systems - Tier 2/Group 3 System # / Name K K K K K K6 Al A2 A3 A4 G K/A Topic(s) Imp. Points 1 2 3 4 5 201003 Control Rod and Drive Mechanism .05 Rod position indication 3.3 1 215001 Traversing In-core Probe ___Rand omlylDeleted 233000 Fuel Pool Cooling and Cleanup .05 Valve closures 2.5 1 239001 Main and Reheat Steam .07 Reactor water level 256000 Reactor Condensate, Randomly Deleted 268000 Radwaste Randomly Deleted 288000 Plant Ventilation Randoml Deleted 290002 Reactor Vessel Internals .05 Brittle fracture 3.3 1 K/A Category Point Totals: 0 0 0 1 1 0 1 1 0 0 0 Grou Point Total: 4 Plant-Specific Priorities System / Topic Recommended Replacement for... Reason Points 295003 Generic 2.4.22 (Partial or Complete Loss of AC Power) 295003 AA1 Revised station procedure I1 I
-t +/-
t + F
+ IL t I F
+/- 1 4 i I I _ _
t j I4 i I -I
________________________ .1._____
Plant-Specific Priority Total (limit 10): 1 I______________
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 (R8, Si)
Facility: Perry Date of Exam: 2/03 Exam Level: SRO -]
Category K/A # Topic Imp. Points 2.1.17 Ability to make accurate/clear and concise verbal reports. 3.6 1 2.1.21 Ability to obtain and verify controlled procedure copy. 3.2 1 Conduct of 2.1.27 Knowledge of system purpose and or function. 2.9 1 Operations 2.1.4 Knowledge of shift staffing requirements. 3.4 1 Total 4 2.2.22 Knowledge of limiting conditions for operations and safety limits. 4.1 1 2.2.11 Knowledge of the process for controlling temporary changes. 3.4 1 Knowledge of RO duties in the control room during fuel handling 2.2.30 such as alarms from fuel handling area/communication with fuel 3.3 1 Equipment storage facility/systems operated from the control room in Control support of fueling operations/and supporting instrumentation.
2.2.12 Knowledge of surveillance procedures. 3.4 1 2.2.25 Knowledge of bases in technical specifications for limiting 3.7 1 conditions for operations and safety limits.
Total 5 2.3.9 Knowledge of the process for performing a containment purge. 3.4 1 2.3.11 Ability to control radiation releases. 3.2 1 Radiation Control Total 2 2.4.43 Knowledge of emergency communications systems and 3.5 1 techniques.
2.4.1 Knowledge of EOP entry conditions and immediate action steps. 4.6 1 Emergency 2.4.27 Knowledge of fire in the plant procedure. 3.5 1 Procedures/
Plan 2.4.8 Knowledge of how the event-based emergency/abnormal 3.7 1 operating procedures are used in conjunction with the symptom based EOPs.
2.4.6 Knowledge of symptom based EOP mitigation strategies. 4.0 1 2.4.17 Knowledge of EOP terms and definitions. 3.8 1 Total -- 6 Tier 3 Point Total (RO .(4)) 13@
ES-401 Record of Rejected K/As Form ES-401-10 (R8, Si)
Tier / Group Randomly Selected K/A Reason for Rejection 1/1 295030 EA1.05 Not applicable to Perry.
1/2 295008 Randomly deleted due to number of items in the group greater than the required number of points for the group.
1/2 295028 Randomly deleted due to number of items in the group greater than the required number of points for the group.
2/2 234000 Randomly deleted due to number of items in the group greater than the required number of points for the group.
2/2 263000 Randomly deleted due to number of items in the group greater than the required number of points for the group.
2/2 204000 Randomly deleted due to number of items in the group greater than the required number of points for the group.
2/2 271000 Randomly deleted due to number of items in the group greater than the required number of points for the group.
2/3 288000 Randomly deleted due to number of items in the group greater than the required number of points for the group.
2/3 256000 Randomly deleted due to number of items in the group greater than the required number of points for the group.
2/3 268000 Randomly deleted due to number of items in the group greater than the required number of points for the group.
2/3 215001 Randomly deleted due to number of items in the group greater than the required number of points for the group.
1/1 295010 AK2.02 Not applicable to Perry Mark III Containment.
1/1 500000 EA1.04 There is no relationship between Drywell Cooling Fans and H2 concentration at Perry.
1/1 295016 AKM No items exist for this category. Substituted category specific Generic item.
1/2 295019 AKI No items exist for this category. Substituted category specific Generic item.
2/1 290001 K5 Not applicable to Perry.
2/1 290001 K6.08 No Cause/Effect relationship with the Plant Air System at Perry.
2/1 290001 K6.05 No Cause/Effect relationship with the Auxiliary Building Ventilation System at Perry.
2/3 233000 A2.13 Importance rating < 2.5.
2/3 201003 K4.02 Rejected due to overlap with operating test.
r I.
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, Sl)
Facility: Perry Date of Exam: 1/03 Exam Level: RO K/A Category Points Tier Group K K K K K K A A A A Point G Total 1 2 3 4 5 6 1 2 3 4 *
- 1. 1______ 3 3 1 2 0 1 Em ergency & 2 3 5 4 3 2.....
Abnormal Plant 2 3 5 4 Evolutions 3 1 0 1 0 2 0 4 Tier 7 8 6 7 6
- 2 36 Totals
- 2. 3 11 3 3 3 2 3 2 3 3 2 28 Plant 2 2 2 1 2 2 2 2 2 2 2 0 19 Systems 3 0 0 0 0 1 0 0 2 0 1 0 4 Tier 5 3 4 5 6 4 5 6 5 6 2 51 Totals
- 3. Generic Knowledge and Abilities Cat 1 Cat 2 Cat 3 Cat 4 13 3 3 2 5 Note: 1. Ensure that at least two topics from every K/A category are sampled within each tier (i.e., 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 exam must total 100 points.
- 3. Select topics from many systems; avoid selecting more than two or three K/A topics from a given system unless they relate to plant-specific priorities.
- 4. Systems/evolutions within each group are identified on the associated outline.
- 5. The shaded areas are not applicable to the category/tier.
6.* The generic K/As in Tiers 1 and 2 shall be selected from Section 2 of the K/A Catalog, but the topics must be relevant to the applicable evolution or system.
- 7. On the following pages, enter the K/A numbers, a brief description of each topic, the topics' importance ratings for the SRO license level, and the point totals for each system and category. K/As below 2.5 should be justified on the basis of plant-specific priorities. Enter the tier totals for each category in the table above.
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 1 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) Imp. Points 1 2 3 1 2 295005 Main Turbine Generator Trip / 3 .02 Recirculation pump downshift/trip 3.4 1 295006 SCRAM / 1 .03 Reactivity Control 3.7 1 295007 High Reactor Pressure / 3 .02 Reactor power 4.1 1 295009 Low Reactor Water Level / 2 .03 Recirculation system 3.1 1 295010 High Drywell Pressure / 5 .03 Drywell/containment differential pressure: Mark III 3.0 1 295014 Inadvertent Reactivity Addition / 1 .03 Cause of reactivity addition 4.0 1 295015 Incomplete SCRAM / 1 .07 Neutron monitoring system 3.6 1 295024 High Drywell Pressure / 5 .07 PCIS/NSSSS 3.8 1 295025 High Reactor Pressure /3 .11 Reactor water level 3.5 1 295031 Reactor Low Water Level / 2 .01 .01 Adequate core cooling / Low pressure coolant injection (RHR) 4.6/4.4 2 295037 SCRAM Condition Present and Power .07 Shutdown margin 3.4 1 Above APRM Downscale or Unknown / 1 500000 High Containment Hydrogen Conc. / 5 .01 Primary containment hydrogen instrumentation 3.4 K/A Category Totals: 13 3 1 412 0 Group Point Total: 1 13
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 2 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) Imp. Points 1 2 3 1 2 295001 Partial or Cornplete Loss of Forced Core .05 Jet pump operability 3.1 1 Flow Circulation / i1 &
295002 Loss of Main Condenser Vacuum / 3 .06 Reactor/turbine pressure regulating system 3.0 1 295003 Partial or Complete Loss of AC Pwr / 6 .06 Containment isolation 3.7 1 295004 Partial or Complete Loss of DC Pwr / 6 .05 Loss of breaker protection 3.3 1 295008 High Reactor Water Level / 2 Randomly Deleted 295011 High CTMT Temperature / 5 .01 Containment pressure 4.0 1 295012 High Drywell Temperature / 5 .01 Increased drywell cooling 3.5 1 295013 High Suppression Pool Temp. / 5 .01 Suppression pool cooling 3.6 1 295016 Control Room Abandonment / 7 2.1.20 Ability to execute procedure steps 4.3 1 295017 High Off-site Release Rate / 9 .04 Plant ventilation systems 3.1 1 295018 Partial or Complete Loss of CCW / 8 .02 System loads 3.3 1 295019 Part. or Comp. Loss of Inst. Air / 8 2.4.11 Knowledge of abnormal condition procedures 3.4 1 295020 Inadvertent Cont. Isolation / 5 & 7 .03 Containment ventilation system 2.9 1 295022 Loss of CRD Pumps / 1 .03 1 Accumulator pressures 3.4 1 295026 High Suppression Pool Water Temp. / 5 .02 Suppression pool level 3.8 1 295027 High Containment Temperature / 5 .02 Containment spray 3.2 1 295028 High Drywell Temperature / 5 Randomly Deleted 295029 High Suppression Pool Water Level / 5 .02 Lowering suppression pool water level 3.6 1 295030 Low Suppression Pool Water Level /5 - - - - -Randomly Deleted ____
295033 High Sec. Cont. Area Rad. Levels / 9 .01 Area radiation monitoring system 3.8 1 295034 Sec. Cont. Ventilation High Rad. / 9 .05 Fuel building ventilation 3.5 1 295038 High Off-site Release Rate / 9 Randomly Deleted 600000 Plant Fire On Site / 8 .01 Fire Classifications by type 2.5 1 K/A Category Point Totals: IT15[4_ 3 2 2 [Group Point Total: 1 19
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, Si)
Emergency and Abnormal Plant Evolutions - Tier 1/Group 3 E/APE # / Name / Safety Function K K K A A G K/A Topic(s) Imp. Points 1 2 3 1 2 295021 Loss of Shutdown Cooling / 4 .02 RHR/shutdown cooling system flow 3.4 1 295023 Refueling Accidents / 8 .03 Inadvertent criticality 3.7 1 295032 High Secondary Containment Area .03 Isolating affected systems 3.8 1 Temperature / 5 295036 Secondary Containment High Sump/Area .02 Water level in the affected area 3.1 1 Water Level / 5 I 1-t--+-1 ______ I t r-1-t----+/- I I _______
t--t-1-t--t t I _______
t-i----I f -l--i-- I ______ _______
1.-I- I._________ L ___________
t t-t-t-t-1 I ______
F-1--t- + 1-I I -I r+/- t +/------i-t L_____ I _______
K/A Category Point Totals: 1 0 1 0 2 0jo Group Point Total: 4
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, Si)
Plant Systems - Tier 2/Group 1 System # / Name K K K K K K A A A A G K/A Topic(s) Imp. Points 1 2 3 4 5 6 1 2 3 4 201001 CRD Hydraulic __ .03 Control rod drive mechanisms 3.1 1 201o002 RMCS Not Applicable t Perry Rod sequences i Ability to locate control 201005 RCIS .04 2.1.31 room switches/controls and indications and 2.7/4.2 2 to determine that they are correctly reflecting the desired plant lineup 202002 Recirculation Flow Control .01 Flow control valve operation 3.6 1 203000 RHRILPCI: Injection Mode .03 Emergency generator 3.7 1 206000 HPCI 1 Not Applicable to Perry 207000 Isolation (Emerg.) Condenser - Not Applicable to Perry 209001 LPCS .05 System venting 2.5 1 209002 HPCS .06 Lights and alarms 2.8 1 211000 SLC .09 SBLC system lineup 4.0 1 Close/open SCRAM instrument volume 212000 RPS .12 vent and/or drain valves 3.9 1 215003 IRM .01 .07 Detector operation / Verification of proper 2.6/3.6 2 functioning/operability 215004 SRM .04 Upscale and downscale trips 3.5 1 Display control system / APRFM (gain 215005 APRM / LPRM .08 .07 adjustment factor) 3.0/3.0 2 216000 Nuclear Boiler Instrumentation .12 .10 Reactor water level control system / 3.6/2.9 2 Automatic recirculation pump speed control 217000 RCIC .04 Manually initiated controls 3.6 1 218000 ADS .03 Loss of air supply to ADS valves 3.4 1 223001 Primary CTMT and Auxiliaries .09 Drywell cooling fans 2.7 1 223002 PCIS/Nuclear Steam Supply Shutoff .01 Redundancy 3.0 1 Allows totr SRV operation from more than 239002 SRVs .05 one location 3.6 1 Bypass valves / Knowledcge ot the purpose 241000 Reactor/Turbine Pressure Regulator .06 2.1.28 and function of major system components 4.1/3.2 2 and controls 259001 Reactor Feedwater .07 A.C. electrical power 2.9 1 Recirculation system / 1-WHV/startup level 259002 Reactor Water Level Control .04 .05 control position 2.9/2.9 2 261000 SGTS 1.01 A.C. electrical distribution 2.9 1 264000 EDGs I__II L__] .06 Cooling water system operation 3.1 1 K/A Category Point Totals: 1 3][3 3 1 31 [13 3 2 Group PointTotal: 28
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, $1)
Plant Systems - Tier 2/Group 2 System # / Name K K K K K K A A A A G K/A Topic(s) Imp. Points 1 2 3 4 5 6 1 2 3 4 201003 Control Rod and Drive Mechanism .05 Rod position indication 3.2 1 201004 RSCS., ,~ Not Appicable to Perr 201006 RWM No l*cable to Perry 202001 Recirculation .04 D.C. power 2.7 1 204000 RWCU 04 Response to interlocks and trips designed to 3.4 1 protect system components 205000 Shutdown Cooling .02 Valve operation 2.8 1 245000 Ma TNbt dble AppnGn tA Per*y...re.0..
219000 RHR/LPCh Torus/Pool Cooling Mode .06 Valve logic initiation of reset following LPCI/RHR automatic in injection mode 3.9 1 226001 RHR/LPCI: CTMT Spray Mode .07 Pump start 3.5 1 239001 Main and Reheat Steam .07 Reactor water level 3.7 1 245000 Main Turbine Gen. and Auxiliaries .03 Reactor power 3.9 1 256000 Reactor Condensate .10 Main turbine trip 3.1 1 262001 AC Electrical Distribution .01 Off-site sources of power 3.3 1 262002 UPS (AC/DC) .19 Power range neutron monitoring system 2.9 1 263000 DC Electrical Distribution .01 Battery charging/discharging rate 2.5 1 271000 Offgas .09 Hydrogen and oxygen recombination 2.6 1 272000 Radiation Monitoring .12 Refuel floor handling accidents/operations 3.3 1 286000 Fire Protection .05 Fire protection capability during loss of off- 3.7 1 site power 1 290001 Secondary CTMT .03 SBGT 3.8 1 290003 Control Room HVAC .04 Environmental conditions 2.8 1 300000 Instrument Air .01 Instrument air compressor 2.8 1 400000 Component Cooling Water .04 Reactor coolant system in order to 2.9 1
__ C at e g o ry P o n oa s 12 2
Ii 112 2 1 0 determine source(s) of RCS leakage into WS 1 G o p P in o a :1CC K/A Category Point Totals: I2 1 2 I2 12 1 2 I2 12 1 0 Group Point Total: - 19
ES-401 BWR RO Examination Outline Form ES-401-2 (R8, Si)
Plant Systems - Tier 2/Group 3 _7G ___ __Topi_ _ s)_Imp._Points System # / Name K K K K K K A A A A K/A Topic(s) Imp. Points 1 2 3 4 5 6 1 2 3 4 215001 Traversing In-core Probe Randomly Deleted 233000 Fuel Pool Cooling and Cleanup .05 Valve closures 2.5 1 234000 Fuel Handling Equipment - - - - - - -- Randomly Deleted 239003 MSIV Leakage Control Not Applicable to Perry___
268000 Radwaste I_1_.01 Sump integrators 3.4 1 288000 Plant Ventilation 1 .05 Extreme outside weather conditions 2.6 1 290002 Reactor Vessel Internals .05 Brittle fracture 3.1 1 K/A Category Point Totals: I0 10 (0 10 I o0 [0 12 10 TI 0 Group PointTotal: 4 Plant-Specific Priorities System / Topic Recommended Replacement for...] Reason Points i j I _
t iI
+ I I.
1- 1 -I.
i I.
i i I. _ _
f i I-1 1 4-Plant-Specific Priority Total: (limit 10)
I
ES-401 Generic Knowledge and Abilities Outline (Tier 3) Form ES-401-5 (R8, S1)
Facility: Perry Date of Exam: 2/03 Exam Level: RO Category K/A # Topic Imp. Points 2.1.17 Ability to make accurate/clear and concise verbal reports. 3.5 1 2.1.21 Ability to obtain and verify controlled procedure copy. 3.1 1 Conduct of 2.1.27 Knowledge of system purpose and or function. 2.8 1 Operations Total 3 2.2.22 Knowledge of limiting conditions for operations and safety limits. 3.4 1 2.2.11 Knowledge of the process for controlling temporary changes. 2.5 1 Knowledge of RO duties in the control room during fuel handling 2.2.30 such as alarms from fuel handling are/communication with fuel 3.5 1 Equipment storage facility/systems operated from the control room in Control support of fueling operations/and supporting instrumentation.
Total 3 2.3.9 Knowledge of the process for performing a containment purge. 2.5 1 2.3.11 Ability to control radiation releases. 2.7 1 Radiation Control Total 2 2.4.43 Knowledge of emergency communications systems and 2.8 1 techniques.
2.4.1 Knowledge of EOP entry conditions and immediate action steps. 4.3 1 Emergency 2.4.27 Knowledge of fire inthe plant procedure. 3.0 1 Procedures/
Plan 2.4.8 Knowledge of how the event-based emergency/abnormal 3.0 1 operating procedures are used in conjunction with the symptom based EOPs.
2.4.6 Knowledge of symptom based EOP mitigation strategies. 3.1 1
_Total 5 Tier 3 Point Total (6 SRO) 9 17
ES-401 Record of Rejected K/As Form ES-401-10 (R8, S1)
Tier / Group Randomly Selected K/A Reason for Rejection 1/1 295010 AK2.02 Not applicable to Perry Mark III Containment.
1/1 500000 EA1.04 There is no relationship between Drywell Recirculation Fans and H2 concentration at Perry.
1/2 295008 Randomly deleted due to number of items in the group greater than the required number of points for the group.
1/2 295028 Randomly deleted due to number of items in the group greater than the required number of points for the group.
1/2 295030 Randomly deleted due to number of items in the group greater than the required number of points for the group.
1/2 295038 Randomly deleted due to number of items in the group greater than the required number of points for the group.
1/2 295016 AK1 No items exist for this category. Substituted category specific Generic item.
1/2 295019 AKM No items exist for this category. Substituted category specific Generic item.
2/1 201005 K2.01 Importance Rating < 2.5.
2/2 290001 K5 Not Applicable to Perry.
2/2 290001 K6.08 No Cause/Effect relationships with the Plant Air System at Perry.
2/2 290001 K6.05 No Cause/Effect relationships with the Auxiliary Building Ventilation System at Perry.
2/3 215001 Randomly deleted due to number of items in the group greater than the required number of points for the group.
2/3 234000 Randomly deleted due to number of items in the group greater than the required number of points for the group.
2/3 233000 A2.13 Importance Rating < 2.5.
2/3 268000 K6 All items have an Importance Rating < 2.5.
2/3 288000 K2 All items have an Importance Rating < 2.5.
3/2 2.2.16 Importance Rating < 2.5.
3/2 2.2.20 Importance Rating < 2.5.
3/4 2.4.42 Importance Rating < 2.5.
2/2 201003 K4.02 Rejected due to overlap with operating test.
Perry Outline Review NRC Comments/ LIC Response 8/12/02 WRITTEN:
- 1. NRC: How do you randomly select KAs?
LIC: Procedure OTG 18.
- 2. NRC: Were any KAs suppressed/rejected?
LIC: Yes. Suppressed KA list submitted with package.
ADMIN JPMs:
- 1. Make sure the admin JPMs have significant, verifiable consequences such that if they are performed incorrectly, the task cannot be successfully completed.
- 3. Make sure the JPM is significant enough to make a pass/fail license decision.
NRC: This topic (print reading, diagnostic skill) belongs under A.2, Equipment Control, ...use of P&IDs....
LICENSEE: KA 2.1.24 comes from "Conduct of Operations" in KA Catalog. Appears to be a conflict with NUREG-1021 list for A.2.
OPERATING JPMs:
General: Want alternate path JPMS to follow guidance in Appendix C, ie, procedurally driven (ARPs or ABNs are good), completes the task or mitigates the problem without reliance on actions by other control room operators...
- 1. I need to review a list of audit exam JPMs (to verify none of those JPMs are repeated on the NRC exam).
- 2. Make sure none of JPMs are performed in the scenarios.
SCENARIOS:
- 1. Verify each scenario has Tech Specs
- 2. Verify each scenario has 2-3 critical tasks.
- 3. Verify 1-2 malfunctions after EOP entry.
Scenario 2 NRC: Will count Event I as N and Event 2 as C providing they occur in separate "stages."
Otherwise, it would appear to be a single event C (BOP) failure.
LICENSEE: Event I N is completed before Event 2 occurs.
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