ML070240185

Examination Outline Submittals for the Kewaunee Retake Examination - August 2006

ML070240185
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Site:	Kewaunee
Issue date:	01/23/2007
From:	Mcneil D NRC/RGN-III/DRS/OLB
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EXAMINATION OUTLINE SUBMITTALS FOR THE KEWAUNEE RETAKE EXAMINATION AUGUST 2006

Dominion Energy Kewaunee, Inc.

N490 Highway 4 2 . Kewaunee, Wl 54216-951 1 Dominion APR 21 2006 Regional Administrator, Region Ill Serial No.06-364 U.S.Nuclear Regulatory Commission KPS/LIC/GR: RO 2443 Warrenville Road, Suite 210 Docket No. 50-305 Lisle, Illinois 60532-4352 License No. DPR-43 DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION RETAKE EXAMINATION OUTLINE In accordance with the guidelines NUREG 1021, Op 3ting Li en e Examination Standard for Power Reactors Revision 9, Dominion Energy Kewaunee, Inc. (DEK) is providing the enclosed Senior Reactor Operator outline for the retake examination of Mr. Randall W. Beck and Mr. Timothy J. Bunkelman scheduled for the week of August 7, 2006.

As discussed in a telephone conversation between Mr. Dell McNeil of Nuclear Regulatory Commission (NRC) Region Ill and Mr. Frank Winks of DEK, the outline was also provided on April 24, 2006 to the NRC Senior Resident Inspector assigned to the Kewaunee Power Station for delivery to Mr. Dell McNeil.

NUREG-1021 physical security requirements state that the enclosed examination materials must be withheld from public disclosure until after the examinations are complete.

If you have questions or require additional information, please feel free to contact Mr.

Frank Winks at 920-388-8303.

Very truly yours, Site Vice President, Kewaunee Power Station EncIosure Commitments made by this letter: NONE cc without enclosure:

NRC Senior Resident Inspector Kewaunee Power Station

Dominion Energy Kewaunee, Inc.

N490 Highway 4 2 , Kewaunee. WI 54216-951 1 ominion' JUN 5 2006 Regional Administrator, Region Ill Serial No.06-416 U. S. Nuclear Regulatory Commission KPS/LIC/GR: RO 2443 Warrenville Road, Suite 210 Docket No. 50-305 Lisle, IL 60532-4352 License No. DPR-43 DOMINION ENERGY KEWAUNEE, INC.

KEWAUNEE POWER STATION RESPONSE TO FURNISH WRllTEN EXAMINATIONS, OPERATING TESTS, AND SUPPORTING REFERENCE MATERIALS In response to a letter from the NRC dated April 27, 2006 regarding the administration of licensing re-take examinations at the Kewaunee Power Station, enclosed are the written examination and the following documents as required by NUREG 1021 Revision 9:

ES-401-2 PWR Exam Outline (Revised)

ES-401-3 Generic WA Outline (Revised)

ES-401-4 Record of Rejected WAS ES-401-6 Written Exam Quality Checklist ES-401-7 RO Written Exam Cover Sheet and RO Written Exam (Ready to give with handouts)

ES-401-8 SRO Written Exam Cover Sheet and SRO Written Exam (Ready to give with handouts)

NUREG-1021 physical security requirements state that the enclosed examination materials must be withheld from public disclosure until after the examinations are complete.

If you have questions or require additional information, please feel free to contact Mr.

Frank Winks at 920-388-8303.

Very truly yours, c-:;y7/4f 7 Leslie N. Hartz Site Vice President, Kewaunee Power Station Enclosures Commitments made by this letter: NONE

Serial No.06-416 Page 2 of 2 cc: Without enclosures Mr. S. C. Burton NRC Senior Resident Inspector Kewaunee Power Station Madison, WI 53707 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555

ES-PO1 Examination Outline Qualitv Checklist Form ES-201-2 Facility: Kewaunee Power Station Date of Examination: 08/09/06 Initials Item Task Description a [ b * ( c #

1. a. Verlfy that the outline(s) fit@)the appropriate model, in accordance with ES-401.

w ,

R b. Assess whether the outline was systematically and randomly prepared in accordance with I Section D.l of ES-401 and whether all KIA categories are appropriately sampled. $& hub

c. Assess whether the outline overemphasizes any systems, evolutions, or generic topics.

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d. Assess whether the justifications for deselected or rejected K/A statements are appropriate.

v 2 a. Using Form ES-301-5, verify that the proposed scenario sets cover the required number of normal evolutions, instrument and component failures, technical specifications.

S and major transients.

I M b. Assess whether there are enough scenario sets (and spares) to test the projected number U and mix of applicants in accordance with the expected crew composition and rotation schedule L without compromising exam integrity, and ensure that each applicant can be tested using A at least one new or significantly modified scenario, that no scenarios are duplicated T from the applicants' audit test@), and that scenarios will not be repeated on subsequent days. hIA 0 c. To the extent possible, assess whether the outline@) conform(s) with the qualitative R and quantitative criteria specified on Form ES-3014 and described in Appendix D.

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3. a. Verify that the systems walk-through outline meets the criteria specified on Form ES-301-2:

(1) the outline(s) contain(s) the required number of control room and in-plant tasks W distributed among the safety functions as specified on the form I (2) task repetition from the last two NRC examinations is within the limits specified on the form T (3) no tasks are duplicated from the applicants' audit test@)

(4) the number of new or modified tasks meets or exceeds the minimums specified on the form $

(5) the number of alternate path, low-power, emergency, and RCA tasks meet the criteria Y

a. Author

b. Facility Reviewer r)

c. NRC Chief Examiner (#)

d. NRC Supervisor Note. # Independent NRC reviewer initial items in Column -c", chief examiner concurrence required ES-201, Page 25 of 27

ES-401 PWR Examination Outline Form ES-401-2 Categories lote: 1. Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one categoty in Tier 3 of the SRO-only outline, the "Tier Totals" in each KIA 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 i 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 KIA statements.

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

5. Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected.

Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6. Select SRO topics for Tiers 1 and 2 fiom 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 lefl side of Column A2 for Tier 2, Group 2 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

9. For Tier 3. select topics from Section 2 of the WA catalog, and enter the WA numbers, descriptions, IRs, and point totals on Form ES-401-3. Limit SRO selections to WAS that are linked to 10 CFR 55.43.

PWR Examination Outline F o ES-401-2

~

id Abnormal Plant Evolutions - Tier 1 I G r o w 1 RO EIAPE # I Name I Safety Function A G KA Topic(s) IR #

2 I 000007 Reactor Trip - Stabilization -

Recovery I 1 EA2 04 If reactor should have tnpped but has not done so.

manually trip the reactor and carry out actions in ATWS EOP 000008 Pressurizer Vapor Space Accident /

AK2 01 -Valves 000009 Small Break LOCA I 3 EK3 14 - RCP tripping requirement 41 1 AA1 05 - RCS flow 38 1

-1 -

AK1.O1 Loss of RHRS during all modes of operation I 1 3.9 1 000027 Pressurizer Pressure Control System AK3 01 - Isolation of PZR spray followng loss of PZR heaters Malfunction / 3 I 000029 ATWS I 1 X -

EA2 05 System component valve position indications 34' 1 I 000038 Steam Gen Tube Rupture / 3 -

EA1 04 PZR spray, to reduce coolant system pressure 1 4 3 1 1 AKl 01 - MFW line break depressurizes the S/G (similar to a steam 000054 Loss of Main Feedwater I 4 line break) 2 4 20 - Knowledge of operational implications of EOP warnings 000055 Station Blackout I 6 cautions. and notes I 000056 Loss of Off-site Power I 6 2 1 14 Knowledge of system status criteria which require the notification of plant personnel I 000057 Loss of Vital AC lnst Bus 16 AA1 01 - Manual inverter swapping 3 7' 1 Y 000062 Loss of Nuclear Svc Water I 4 X 2 1 32 Ability to explain and apply all system limits and precautions

~ 34 1 I 000065 Loss of Instrument Air / 8 AK3 08 - Actions contained in EOP for loss of instrument air 1 3 7 1 1 WE05 Inadequate Heat Transfer - Loss of EK2 1 Components and functions of control and safety systems including instrumentation. signals, interlocks, failure modes and Secondary Heat Sink 1 4 automatic and manual features

/ E l 1 Loss of Emergency Coolant Recirc. I EK1 2 - Normal, abnormal and emergency operating procedures associated with Loss of Emergency Coolant Recirculation WE12 Steam Line Rupture - Excessive Heat Transfer I 4

PWR Examination Outline ES - 401 Form ES-401-2 Emergency and Abnormal Plant Evolutions Tier II Group 2 RO

_c

/APE # I Name I Safety Function K 1

K 2

K 3

A 1

A 2 =I KA Topic(@ IR AK3 09 - Recording of group bank position for dropped rod 000003 Dropped Control Rod I 1 X (reference point used to withdraw dropped rod to equal height with 3 0 other rods in the bank) 100024 Emergency Boration I 1 2 4 45 - Ability to prioritize and interpret the significance of each 3.3 1 annunciator or alarm 100032 Loss of Source Range NI I 7 X AK3 02 Guidance contained in EOP for loss of source-range 3 7 1 nuclear instrumentation 100036 Fuel Handling Accident I 8 X -

AK1 01 Radiation exposure hazards 35 1 100061 ARM System Alarms I 7 X -

AK2 01 Detectors at each ARM system location 25 1 NE03 LOCA Cooldown - Depress I 4 X 2 1 27 - Knowledge of system purpose and or function 2.8 1 EA2 2 -Adherence to appropriate procedures and operation within ME10 Natural Circ I4 X 34 1 the limitations in the faciliNs license and amendments ons of control and safety systems N/E13 Steam Generator Over-pressure I4 X Is interlocks failure modes and 30 1 WE16 High Containment Radiation I 9 X 1 29 WA Category Totals: 1 1 1 4 2 1 11 1

- 9 1

i -401 PWR Examination Outline Form ES-401-2 Plan K

I

'stem # I Name KA Topic@)

1 13 Reactor Coolant Pump K5 02 - Effects of RCP coastdown on RCS parameters 3 Reactor Coolant Pump 84 Chemical and Volume Control X A4 08 - RCP cooling water supplies IK1 23 - RWST

+

2 1 28 - Knowledge of the purpose and function of major I4 Chemical and Volume Control system components and controls 15 Residual Heat Removal K5 09 - Dilution and boration considerations 16 Emergency Core Cooling K6 02 - Core flood tanks (accumulators)

A3 01 Components which discharge to the PRT 27.1

+

17 Pressunzer Relief/Quench Tank 1 I8 Component Cooling Water K4 01 -Automatic start of standby pump 31 I A2 07 - Consequences of high or low CCW flow rate and

)8 Component Cooling Water temperature. the flow rate at which the CCW standby pump will start

-t 10Pressurizer Pressure Control K3 03 - ESFAS I 2 Reactor Protection A2 06 - Failure of RPS signal to trip the reactor I3 Engineered Safely Features IK6 01 - Sensors and detectors luation 13 Engineered Safely Features A3 02 - Operation of actuated equipment ctuation I

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22 Containment Cooling K3 02 - Containment instrumentation readings K4 04 - Reduction of temperature and pressure in containment afler a LOCA by condensing steam to reduce

!6 Containment Spray radiological hazard, and protect equipment from corrosion damage (spray) i 19 Main and Reheat Steam K3 03 - AFW pumps i9 Main Feedwater K4 16 -Automatic tnps for MFW pumps 3 1'

$1AuxiliaryEmergency Feedwater -

K1 01 SIG system 2 4 45 -Ability to pnoritize and interpret the significance of j l AuxiliatyIEmergency Feedwater each annunciator or alarm

$2AC Electrical Distribution K2 01 - Major system loads

$3 DC Electrical Distribution A3 01 - Meters annunciators dials recorders and indicating lights 27 I 1 1

b 064 Emergency Diesel Generator 064 Emergency Diesel Generator A1 01 - Radiation levels L t 073 Process Radiation Monitorin 076 Service Water 078 Instrument Air 078 Instrument Air 2

IES - 401

~ Form a - ESdOi-2 KA Topic@) IR 002 Reactor Coolant A2.01 - Loss of coolant inventory 43 01 1 Pressurizer Level Control -

A1 02 Charging and letdown flows 33 015 Nuclear Instrumentation 1 K6 01 - Sensors detectors and indicators 29 IK1 01 - Plant computer 3 2' K4 01 - SIG level control 36 K3.01 - Remainder of the plant 29 A4 02 - Remote radwaste release 3 2' 2 1 32 -Ability to explain and apply all system limits and 34 precautions K2.03 - Emergencylessential SWS pumps 2 6' 31 K/A Category Totals:

1

ES-401 PWR Examination Outline Form ES-401-2 Facility: Kewaunee Power Station Date Of Exam: 08/09/2006 I I II Tier Group K 1

K 2

K 3 4 RO WA Categoy Points K K K A A A A 5 6 1 2 3 4 G

• Total txl-k-p SRO-On1 Points 1 0 0 0 0 0 1 , o Emergency & 2 0 0 0 NIA 0 0 N/A 0 0 Abnormal Plant TierTotals 0 0 0 0 0 0 0 5 10 Evolutions 1 0 0 0 0 0 0 0 0 0 0 0 2 2 0 0 0 0 0 0 0 0 0 0 0 0 Plant Systems TierTotals 0 0 0 0 0 0 0 0 0 0 0 0 5 3 8

3. Generic Knowledge and Abilities 1 2 3 10 Categories 0 0

~

0 0

~

Note 1 Ensure that at least two topics from every applicable WA category are sampled within each tier of the RO and SRO-only outlines (Le., except for one category in Tier 3 of the SRO-only outline, 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 fl 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 Systemslevolutions 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.

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

5 Absent a plant-specific priority, only those WAS having an importance rating (IR) of 2.5 or higher shall be selected Use the RO and SRO ratings for the RO and SRO-only portions, respectively.

6 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 (Note #1 does not apply). Use duplicate pages for RO and SRO-only exams.

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

P -

ES 401 PWR Examination Outline Emergency and Abn mal Plant Evolutions -Tier 1 I Group 1 SRO Form ES-401-i c _

1 -

E/APE # I Name I Safety Function K K K A A KA Topic(s) #

1 2 3 1 2 000022 Loss of Rx Coolant Makeup I 2 X IAA2 02 - Charging pump problems I 37 1 000026 Loss of Component Cooling Water -

2 2 25 Knowledge of bases in technical specifications for limiting 1

18 conditions for operations and safetv limits EA2 08 - Viable alternatives for placing plant in safe condition when 000038 Steam Gen Tube Rupture I 3 1 condenser is not available 000040 Steam Line Rupture - Excessive X 2 1 32 - Ability to explain and apply all system limits and precautions 38 1 Heat Transfer I 4 000058 Loss of DC Power I 6 X 1 -

AA2 02 125V dc bus voltage, lowlcritical low, alarm I 36 1

WIE04 LOCA Outside Containment / 3 1 KIA Category Totals: 6 1

PWR Examination Outline is - 401 FO~III ES-401-2 2 4 4 Ability to recognize abnormal indications for system operating

~

UE10 Natural Circ I 4 abnormal operating procedures UE14 Loss of CTMT Integrity I 5 I

(IES -

I 401 Syntem # I Name 005 Residual Heat Removal 006 Emergency Core Cooling 059 Main Feedwater 3

1 K

2 K

3 PWR Examination Outline r 2 I Group 1 SRO 01 T

I KA Topic(s)

A2 02 - Pressure transient protection during cold shutdown 2 4 30 - Knowledge of which events related to system operations/s!atus should be reported to outside agencies A2 04 - Feeding a dry S/G 4

F o ES-401-2 36 134'

~

1 2 4 49 - Ability to perform without reference to procedures 062 AC Electrical Distnbution X those actions that require immediate operation of system 4 1 components and controls 103 Containment A2 02 - Necessary plant conditions for work in containment 1

=

KIA Category Totals: 6 I

PWR Examination Outline Form ES-401-1 r nt Svstems -Tier 2 I Group 2 SRO I 1 1 KA Topic(8)

A2 02 - Loss of power to the RPlS 2 4 45 - Ability to pnoritize and interpret the significance of each annunciator or alarm A1 02 - Water level in the refueling canal Group Point Total:

I

ES .401 Gensnc Knowkdpe and A b h l k ~ sOutline (Tnr 3) Form ES4Ol.l 234 Knowledpe of rsdfalion exposure llmils and wnlamlnalion conlrol mcludmng permissible levels m excess of those aulhonzed 31 1 2 3 ! Knowledge 01 the wocess for perlorminp a containment prpe 34 I 1 I

2 3 11 Abilily to wnlrol radialion releases 27 1 1

SuMolal 2 2 Ablllly lo r e q n l z e abnwmal indicaIiOnS for Synem operaling paramelen which are enlry-level wndnmns for emergency and abnormal 244 operating pmcedures 40 1 I

249 Knowledge of low power Ishutdown implicallonsIn a a d e n l (e g LOCA or loss of RHR) mitigation lralegler 1 3 3 ) 1 Knowledge of Ihe parameten and lwlc used lo assess lhe status of safely IunnlOnS includfng 1 Reauivny wnlrol 2 Core Vxrlinp j 1

' 4 21 and heal removal, 3 Reanor wolanl system inlwmy. 4 Containment w n d m n s , 5 Radloadivily release control  ! 1 7 , 1 I

2 4 38 Abolny to lake anions called lor in the facclily emerpency plan. Including (11 requlrea) s u w m n g or ading as emergency coordinator I  ! 1 4 0 I I 24 SUMOlal 3 1

ES-401, Rev. 9 Record of Rejected WAS Form ES-401-4 Tier I Randomly Reason for Rejection Group Selected WA "FIRST OUT" annunciators do not exist at KPS. Unable to 111 007EA2.05 generate question for topic. Replaced with randomly selected KA 007EA2.04.

KA 038EA2.08 was selected for the SRO outline. This KA 111 038EA2.04 overlaps the same area. Replaced with randomly selected KA 038EA1.04.

KA 058AA2.08 was selected for the SRO outline. This KA 111 058AA1.03 overlaps the same area. Replaced with randomly selected KA that is from a previously unselected APE, 054AK1.01 KA WlE04 2.4.48 was selected for the SRO outline. This KA 111 WlE04 2.4.10 overlaps the same area. Replaced with randomly selected KA that is from a previously unselected APE, 062A 2. I.32.

KA W/E14EA2.1 was selected for the SRO outline. This KA 1I 2 WlE14EA2.2 overlaps the same area. Replaced with randomly selected KA that is from a previously unselected APE, 003AK3.09.

Two KAs had already been chosen from SRO and RO outlines for 005. This KA resulted in overpopulation of the 211 005A4'05 system and overlap. Replaced with randomly selected KA from less populated system, 003A4.08.

Two KAs had already been chosen from SRO and RO outlines. Also KA 006 2.4.30 was selected for the SRO 211 006 2.4.45 outline. This KA resulted in overpopulation of the system and overlap. Replaced with randomly selected KA from less populated system, 004 2.1.28.

Two KAs had already been chosen from SRO and RO 211 ' O3 2'1 '23 outlines for 103. This KA resulted in overpopulation of the system and overlap. Replaced with randomly selected KA from less populated system, 064 2.1.33.

KA 029 2.4.45 was selected for the SRO outline. This KA overpopulates the system and overlaps the same area.

212 029A1 '03 Replaced with randomly selected KA from a system previously not sampled, 01 1Al.02.

KA 034A1.02 was selected for the SRO outline. This KA overpopulates the system and overlaps the same area.

212 034K1 '02 Replaced with randomly selected KA from a system previously not sampled, 017K1.01.

This KA was selected for the SRO outline. Replaced with 3 2.1.25 randomly selected KA 2.1.10.

Tier / Randomly Reason for Rejection Group Selected WA 1/1 A question could not be developed suitable to the event.

040A 2.1'33

[SRO] Replaced with randomly selected KA 040A 2.1.32.

This KA is the same KA that was selected for another APE W/E04E 2.2.25 in the same group (026A 2.2.25). To prevent overlap, it was

[SROI replaced with randomly selected KA WlE04E 2.4.48.

112 An SRO level question could not be developed for this KA.

067AA2.02

[SRO] Replaced with randomly selected KA 067AA2.08.

1 I WlE15E 2.1.33 A question at SRO level could not be developed suitable to Replaced with randomly selected KA W/E06 A question at SRO level could not be developed since 211 103A2.01 operations involvement in leak rate testing is minimal.

tSRO1 Replaced with randomly selected KA 103A2.02.

2/2 An SRO level question could not be developed for this KA.

0I 4A2.03

[SRO] Replaced with randomly selected KA 014A2.02.

The combined RO and SRO tier 3 was imbalanced with 5 WAS selected in Categories 2 and 3, and only 3 KAs selected in Category 4. Category 3 was selected for 3 2.3.2 reduction due to the limited number of KAs as compared to Category 2. Replaced with randomly selected KA 2.4.9 in Category 4.

(Post-submittal) The KA supports only questions that overlap in area with the other selected KA 007A3.01. To prevent 2/1 007K4'01 double jeopardy condition selected KA from next System in Group, 008K4.01 ( only selected once previously)

(Post-submittal) An operationally valid question could not be 2/1 063A2.01 developed for KA. Replaced with random-selected KA 063A3.01.

(Post-submittal) An operationally valid question could not be 211 064K2.01 developed for KA. Replaced with random-selected KA 064K2.02.

(Post-submittal) A question could not be developed to fit KA.

212 035K4.05 Redaced with random-selected KA 035K4.01.

(Post-submittal) A SRO-only level appropriate question could 112' W/E06 2.4.7 not be developed for KA. Replaced with random-selected KA

[SROI W/E06 2.1.12.

~ ~~

(Post-submittal) An operationally valid question could not be 2.4.43 developed for KA. Replaced with random-selected KA

(1 Tier/

Grow I Randomly Selected WA 1 Reason for Rejection (Post NRC Comments) An acceptable level of difficulty 111 029EA2.05 question could not be written. Replaced with KA 029EA2.01.

1 'I1 lSROl 1 058AA2.02 1 (Post NRC Comments) An acceptable SRO-only level auestion could not be written. Redaced with KA 058AA2.01 211 (Post NRC Comments) An acceptable SRO-only level