ML051260439

Revised Examination Outline for the Duane Arnold Initial Examination - Jan/Feb 2005

ML051260439
Person / Time
Site:	Duane Arnold
Issue date:	01/31/2005
From:	Thullen G Nuclear Management Co
To:	Office of Nuclear Reactor Regulation
Shared Package
ML050800491	List: ML051260422 ML051260435 ML051260437 ML051260439
References
50-331/05-301 50-331/05-301
Download: ML051260439 (28)

Text

REVISED EXAMINATION OUTLINE FOR THE DUANE ARNOLD INITIAL EXAMINATION JANlFEB 2005

Form ES 301-1 and 2 for JPMs.

The following are the changes that were requested on ES 301-1 and 2 , based on a phone call the NRC lead examiner, Pete Petersen; 0 For this form he requested that we insert the actual title of the JPM.

o Done.

The following were errors that were on forms ES 301-2. These were discussed with Pete Petersen and the changes made per the discussion:

The KA number for JPM g, was written incorrectly. I had, 4000, and it should have been 400000.

The below concern is based on the interpretation of ES301 Preparing Initial Operating Tests, D.4.a.

Also a concern here in that Safety Function 8 is titled Component Cooling Water. In the NRCs eyes, there is only ONE component cooling system.

At DAEC we have I The reason I bring this up is that according to the K and A catalog, JPM g and k are on the same system. This would make one of them not unacceptable.

After a long discussion, it was accepted that the Well Water system and RWS system are two different systems and both JPMs are acceptable.

Pete had the same concern about the JPMs t and i. They both mention the RPS system. We explained that this JPM is to isolate the Instrument AC Regulating Transformer, [electrical]. Pete agreed Another Concern was that there was no ESF system in the SRO-U JPMS o This was changed so the SRO-U will now perform JPMs j and k for the in-plant systems Had the Wrong K and A number for the Switching of the CRD suction Filters. I had 264000, and it really is 201001.

o Changed.

On JPM k, the K and A was from our exam bank and was listed as an Emergency system per the K/A catalog.

o Pete stated that the JPM had to have a Safety function 8 K and A.

1 The 29501 8 K/A number was changed to 400000.

ES-301 Administrative Topics Outline Form ES-301-1

acility: DAEC Date of Examination: 0 113 1/05 2xam Level (circle one):SRO I/U 0peration Test No.: 2005-01 Administrative Topic Type Describe Activity to be performed (see note) Code*

onduct of Operations

Title:

Interpret REACTOR COOLANT LEAKAGE

alculations per STP 3.0.0-01 Interpret the 1200 DW Equipment and Floor drain sumps, calculation per STP 3.0.0-01.

Determine that the reading is out of spec high.

Take the directed actions of STP 3.0.0-01 12.1.71

onduct of Operations ritle:

valuate License Maintenance and Over Time iequirements.

Worker Call out. Determine if it is acceptable for RO to assume the watch in a Licensed Control Room position.

The SRO will ensure that the Overtime limits are not exceeded and if their license is currently active.

Based on the information given, the operator will not be eligible to stand the watch.

[2.1.2]

quipment Control S. N Me:

leview a Work Order for closure IAW ACP 1408.1 WORK ORDERS Review a Work Order for closure IAW ACP 1408.1 12.2. I91

ladiation Control I

Title:

Survey Map review and dose calculation to determine the adequacy of the RWP dose setting and determine if a Dose Extension is Required.

Review a survey map and RWP for an area in the plant. Determine the exposure, the exposure limit are acceptable when compared

-+

to the RWP. (HPPs 31 33.3 for Survey map, and 3101.5 for the RWP requirements. In addition determine if the worker will need a dose extension.

r2.3.101 Smergency Plan

Title:

Declare an Emergency Action Level and fill out Note 5 in preparation for notification of Linn, Benton, and State.

Given plant conditions, determine the proper EAL, fill out Emergency Plan Note 5, (Notification).

r2.4.411 VOTE; All items (5 total) are required for SROs. RO applicants require only 4 items unless they u-e retaking only the administrative topics, when all 5 are required.

~

'Type Codes & Criteria (C)ontrol Room (D)irect from hank ) 5 3 for ROs; I 4 for SROs and RO retakes (N)ew or (M)odified form hank including (21)

(P)reious 2 exams (<-1; randomly selected (Shulator

ES-301 Administrative Topics Outline Form ES-301-1

'acility: D f + C c Date of Examination: 01 / 3 l / z ~ u S 3xam Level (circle one):RO Operation Test No.: br Administrative Topic Describe Activity to be performed (see note)

Zonduct of Operations

Title:

Perform REACTOR COOLANT LEAKAGE calculation per STP 3.0.0-01.

Pump the DW Equipment and Floor drain sumps for the 1200 readings. Perform the calculation per STP 3.0.0-01. Determine that the reading is out of spec high and recommend that the SRO take the prescribed actions of the STP.

12.1.71

onduct of Operations

Title:

Evaluate License Maintenance and Over Time Requirements.

Worker Call out. Determine if it is acceptable to assume the watch as an RO.

Ensuring that the Overtime limits are not exceeded and that their license is currently active does this.

Based on the information provided, the operator will not be able to assume the watch.

[2.1.2]

Equipment Control

Title:

Peer check STP 3.8.1-01. Offsite Power Sources.

Determine that the STP was done incorrectly. Re-performs STP.

Perform STP 3.8.1-01 for Offsite Sources inoperable.

The RO will have to perform the STP and determine if the proper alignment of off site sources exists.

Based on th conditions given the RO, the required number of offsite sources will not exist.

2.2.12

Radiation Control Emergency Plan s, N

Title:

Survey Map review and dose calculation to determine the adequacy of the RWP dose setting for the stated job.

Review a survey map and RWP for an area in the plant. Determine the exposure, the exposure limit are acceptable when compared to the RWP. (HPPs 31.03.3 for Survey map, and 3101.5 for the RWP requirements.

2.3.1 0 NOTE; All items ( 5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all 5 are required.

• Type Codes & Criteria (C)ontrol Room (D)irect from bank ) 2 3 for ROs; 5 4 for SROs and RO retakes (N)ew or (M)odified form bank including (21)

(P)reious 2 exams (<or = to I ; randomly selected Wimulator

U

-~

ES-301

-~ Control Room/ln-plant Systems Outline Form ES-301-2 Facility: DAEC Date of Examination: 0113 1/05 Exam Level (circle one): R O 0peration Test No.: 2005-01 Control Room Systems (8 for RO: 7 for SRO-I: 2 or 3 for SRO-U)

SystemiJPM Title Type Code* Safety Function

a. Perform a Control Rod Drive Exercise, Alternate Path to D, A, S 1 Carry out Required Actions for an Uncoupled Control Rod.

(20 1003-06)

b. Defeat the RClC Low RPV Pressure Isolation and 21 1 interlock and iniect with RClC into the RPV. (217000-12)

I D, S, L l 2

c. Isolate an MSlV at power. (239001-03) I N,S I 3

d. Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling. (209001 -04) I N,S I 4

e. Drain the Torus to Radwaste. AP must install defeat 13.

(2 19000-04) 1 N,A,S

f. Perform Manual Scram Functional Test STP 3.3.1.1-21 7 (212000-15)

g. Install Defeat 4 to restore Drywell Cooling. (Alternate Path, N, A, S 8 requires WELL WATER to be secured prior to installing Defeat 4, then WELL WATER must be restarted. (400000-02)

h. Establish a Leakage Path to the Main Condenser LAW AOP N, S 9 672.2, Offgas RadiatiodReactor Coolant High Activity.

(272000-03)

~

i. Shutdown of Regulating Transformer IY IA for N, A 6 maintenance. (AP requiring transfer from 1Y16 to 1Y26)

[262002-041

i. Switch CRD Pump Discharge Filters. (201001-03) I R, D I 1

k. Establish Make-up to the RHRSWlESW pits from GSW.

(400000-03) 1 D,E, 1 8 All control room (and inplant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO I SRO-I I SRO-U

(A)ltemate path 4-6 14-6 12-3 (C)ontrol Room (D)irect from bank s9 58 54 (E)mergency or abnormal in-plant 21 / > I I21 (L)ow -power 21 I21 / > l (N)ew or (M)odified form bank including 1(A) 22 i 22 I 21 (P)reious 2 exams 53 I 5 3 / 52 (randomly selected)

(WCA 21 121 I21 (S)imulator

ES-301 Control RoomlIn-plant Systems Outline Form ES-301-2 Facility: DAEC Date of Examination: 01/31/05 Exam Level (circle one): SRO-I 0peration Test No.: 2005-01 Control Room Systems (8 for RO: 7 for SRO-I: 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function

a. Perform a Control Rod Drive Exercise, Alternate Path to Carry out Required Actions for an Uncoupled Control Rod.

(201003-06)

b. Defeat the RClC Low RPV Pressure Isolation and 21 I interlock and iniect with RClC into the RPV. (217000-12)

c. Isolate an MSlV at power. (239001 -03)

d. Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Cooling. (209001-04)

e. Drain the Torus to Radwaste. AP must install defeat 13.

(2 19000-04)

T f.

g. Install Defeat 4 to restore Drywell Cooling. (Alternate Path, N, A, S requires WELL WATER to be secured prior to installing Defeat 4, then WELL WATER must be restarted. (400000-02)

h. Establish a Leakage Path to the Main Condenser IAW AOP N, S 9 672.2, Offgas RadiatiodReactor coolant High Activity.

(272000-03)

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. Shutdown of Regulating Transformer 1Y I A for maintenance. (AP requiring transfer from 1Y16 to 1Y26) 1262002-041

.i.Switch CRD Pump Discharge Filters. (201001-03) I D,R I I

k. Establish Make-up to the RHRSW/ESW pits from GSW (400000-03)

All control room (and inplant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for ROISRO-IISRO-U

(A)lternate path 4-6 14-6 12-3 (C)ontrol Room (D)irect from bank <9 I 1 8

- 14 (E)mergency or abnormal in-plant 21 / > I / t l (L)ow -power 21 / t l I t 1 (N)ew or (M)odified form bank including 1(A) 22 I t 2 I t 1 (P)reious 2 exams 13 1 4 / 12 (randomly selected)

(R)CA t l / 21 / 21 (S)imulator

~ -~

ES-301 . Control Roomnn-plant . S y s t i i s Outline Form ES-301-2 ..

Fac i lit, : DAEC. I)atc ofEwmiiLtiun: 0 1 3 I 03 ~-

Exam I.e\cl (circle one): SHO-1 Operation Test . .h.: 2005-01 Control Room Syslems (8 for RO: 7 liir SRO-I: 2 or 3 lor SRO-U System/JPM Title Type Code* Safety Function

a. l I

b. Defeat the RClC Low RPV Pressure Isolation and 21 1 interlock and inject with RClC into the RPV. (217000-12)

C. I D, S, L II 2 I I d.

e. Drain the Torus to Radwaste. AP must install defeat 13.

(2 19000-04)

f. II I I

g.

672.2, Offgas RadiationIReactor coolant High Activity (272000-03)

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

I. I I

i. Switch CRD Pump Discharge Filters. (201001-03) I R. D I 1

k. Establish Make-up to the RHRSWIESW pits from GSW.

(400000-03)

~ D, E, 1 ~~

8 All control room (and inplant) systems must be different and serve different safety functions: in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for ROISRO-IISRO-U (A)ltemate path 4-6 / 4-6 12-3 (C)ontrol Room (D)irect from bank 29 I 1 8 1 4 (E)mergency or abnormal in-plant 21 /21 / 21 (L)ow -power 2 1 /21 121 (N)ew or (M)odified form bank including 1(A) 22 122 I 2 1 (P)reious 2 exams <3 1 13 1 1 2 (randomly selected)

(R)CA 21 I21 / 2 1 (S)imulator

S-301 Administrative Topics Outline Form ES-301-1

'acility: DAEC Date of Examination: 01/31-05 ixam Level (circle one):SRO I N 0peration Test No.: 2005 Administrative Topic Describe Activity to be performed (see note)

onduct of Operations

Title:

Interpret REACTOR COOLANT LEAKAGE

alculations per STP 3.0.0-0 I Interpret the 1200 DW Equipment and Floor drain sumps, calculation per STP 3.0.0-01.

Determine that the reading is out of spec high.

Take the directed actions of STP 3.0.0-01

onduct of Operations

Title:

Determine Administrative Requirements for an Automatic Initiation of HPCl and injection into the RPV Candidate will be asked to determine his Administrative and Regulatory responsibilities for this event.

[2.1.12]

3quipment Control S, N

Title:

Review a Work Order for closure IAW ACP 1408.1 WORK ORDERS Review a Work Order for closure IAW ACP 1408.1

[2.2.19]

Radiation Control I S,N

Title:

Survey Map review and dose calculation to determine the adequacy of the RWP dose setting and determine if a Dose Extension is Required.

Review a survey map and RWP for an area in the plant. Determine the exposure, the exposure limit are acceptable when compared to the RWP. (HPPs 3 I .03.3 for Survey map, and 3101 .S for the RWP requirements. In addition determine if the worker will need a dose extension.

[2.3. IO]

Emergency Plan i S,N

Title:

Declare an Emergency Action Level and fill out Note S in preparation for notification of Linn, Benton, and State.

Given plant conditions, determine the proper EAL, fill out Emergency Plan Note 5, (Notification).

r2.4.411 NOTE; All items (5 total) are required for SROs. RO applicants require only 4 items unless they are retaking only the administrative topics, when all S are required.

• Type Codes & Criteria (C)ontrol Room (D)irect from bank ) 5 3 for ROs; 5 4 for SROs and RO retakes (N)ew or (M)odified form bank including (>I)

(P)reious 2 exams (< I ; randomly selected (S)imulator Revised following NRC Validation Week, 01110105

(A)ltemate path 4-6 14-6 12-3 (C)ontrol Room (D)irect from bank 19 I 1 8 14 (E)mergency or abnormal in-plant 21 121 / > l (L)ow -power 21 / > I 121 (N)ew or (M)odified form bank including 1(A) >2/22/>1 (P)reious 2 exams 13 / 1 3 1 12 (randomly selected)

(R)CA 21 / > l / > l (S)imulator

ES-301 Control R o o d n - p l a n t Systems Outline Form ES-301-2 Facility: DAEC Date of Examination: 01/31/04 Exam Level (circle one): SRO-I Operation Test No.: 2005-01 Control Room Svstems (8 for RO: 7 for SRO-I 2 or 3 for SRO-U System/JPM Title Type Code* Safety Function

a. Perform a Control Rod Drive Exercise, Alternate Path to I Carry out Required Actions for an Uncoupled Control Rod.

(201003-06)

b. Defeat the RCIC Low RPV Pressure Isolation and 21 I L interlock and in~jectwith RCIC into the RPV. (21 7000-12)

c. Isolate an MSIV at power. (239001-03) N.S 3

d. Manually inject into the RPV with Core Spray to achieve 4 Alternate Shutdown Cooling. (209001 -04)

e. Drain the Torus to Radwaste. AP must install defeat 13. N,A, S 5 (2 19000-04) f.

g. Install Defeat 4 to restore Drywell Cooling. (Alternate Path, N,A, S 8 requires WELL WATER to be secured prior to installing Defeat 4, then WELL WATER must be restarted. (400000-02)

h. Establish a Leakage Path to the Main Condenser IAW AOP 9 672.2, Offgas RadiatiodReactor coolant High Activity.

(272000-03)

i. Shutdown of Regulating Transformer IY 1.4 for N,A 6 maintenance. (AP requiring transfer from 1 Y I6 to 1 Y26)

[262002-041

i. Switch CRD Pumo Discharge Filters. (201001-03) D, R 1

k. Perform Required Actions for RPV Injection with the SBLC Test Tank. (29503 1-10)

All control mom (and iuplant) systems must be different and 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

ES-301 Control Room/In-plant Systems Outline Form ES-301-2 Fac i I ity : Date of Examination:

Exam Level (circle one): SRO-U Operation Test No.:

SystemlJPM Title Type Code* Safety Function a.

b. Defeat the RCIC Low RPV Pressure Isolation and 21 1 D, S, L L interlock and inject with RCIC into the RPV. (217000-12)

C.

d.

e. Drain the Torus to Radwaste. AP must install defeat 13. N,A, S 5 (2 19000-04) f.

g.

h. Establish a Leakage Path to the Main Condenser IAW AOP N,S 9 672.2. Offeas RadiatiodReactor coolant High Activitv.

(272000-03)

In-Plant Systems (3 for RO; 3 for SRO-I; 3 or 2 for SRO-U)

i. Switch CRD Pump Discharge Filters. (201001-03) 1 I

R, D

k. Perform Required Actions for RPV Injection with the SBLC D. E, 2 Test Tank. (295031-10)

All control room (and inplant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO/SRO-VSRO-U (A)lternate path 4-6 I 4-6 / 2-3 (C)ontrol Room (D)irect from bank 19 / 1 a 14 (E)mergency or abnormal in-plant 21 121 / 2 1 (L)ow -power 21 I 2 1 / 21 (N)ew or (M)odified form bank including 1(A) 22 I 2 2 I21 (P)reious 2 exams S3 53 / 1 2 (randomly selected)

(RKA 21 / 2 1 / 2 1 (S)imulator Revised following NRC Validation Week, 01/10/1

ES3UI Control RoodIn-plant Systems Outline Form ES-301-I r--_-

Facility: DAEC Date of Examination: 113 1/04 Exam Level (circle one): RO Operation Test No.: 2005-01 I Control Room Systems (8 for RO: 7 for SRO-I: 2 or 3 for SRO-U SystemlJPM Title Type Code* Safety Function

a. Perform a Control Rod Drive Exercise, Alternate Path to 1 Carry out Required Actions for an Uncoupled Control Rod.

(201003-06)

b. Defeat the RClC Low RPV Pressure Isolation and 21 I 2 interlock and iniect with RClC into the RPV. f217000-12)

c. Isolate an MSlV at power. (239001-03) N, S 3

d. Manually Inject into the RPV with Core Spray to achieve Alternate Shutdown Coolinn. (209001-04)

e. Drain the Torus to Radwaste. AP must install defeat 13.

(2 19000-04)

N, A, S I 5 1 f. Perform Manual Scram Functional Test STP 3.3.1.1-21 (2 12000- 15)

g. Install Defeat 4 to restore Drywell Cooling. (Alternate Path, N,S, N, A, S I 7 8

requires WELL WATER to be secured prior to installing Defeat 4, then WELL WATER must be restarted. (400000-02)

h. Establish a Leakage Path to the Main Condenser IAW AOP N, S 9 672.2, Offgas RadiatiodReactor Coolant High Activity.

(272000-03)

i. Shutdown of Regulating Transformer l Y l A for N, A 6 maintenance. (AP requiring transfer from IY 16 to 1Y26)

[262002-041

i. Switch CRD Pump Discharge Filters. (201001-03) R, D 1

k. Perform Required Actions for RPV Injection with the SBLC Test Tank. (29503 1 - 1 0)

I D,E, 2 All control room (and inplant) systems must be different and serve different safety functions; in-plant systems and functions may overlap those tested in the control room

• Type Codes Criteria for RO I SRO-I I SRO-U

Form ES-D1 for ESG 1 The following are the changes made after discussing the 75-day submittal with the NRC.

Removed some information in the Initial Conditions about needing to cycle PSV 4407. It was stated that this was a turnover item, not an initial condition.

Removed direction to pull rods to achieve the desired bypass valve positions required in the STP.

For Event #2, had the plant in a situation where an IRM was bypassed. Did not mention it in the turn over information. Added a statement as to why the A IRM is bypassed.

Altered Event 7 so the SRV would not close following the cycling. This will require the crew to scram the plant. This is also the pre-event to the feedwater rupture.

Added another component failure for the BOP during the Major event. This is to determine that the RHR inject valve did not open, and take actions to open the valve via the handswitch.

Based on validation comments and time considerations, it was determined that the Condensate Vibration problem should be deleted. This was a BOP bean, and there are still 3 BOP beans and 2 RO beans.

Appendix D Scenario Outline Form ES-D-1 Facility : DAEC Scenario No.: ESG#I Op-Test No. 2005-01 Examiners: Operators:

Initial Conditions: Reactor start UP is in progress. The reactor is currently at 150 psip. Work was performed on PSV 4407 while the plant was shutdown, it is currently inoperable Turnover: Reactor start up is in progress. The plant was shut down due to PSV 4407 leaking. It has been fixed. We are currently at 150 psie and holding.

STP 3.4.3-03, MANUAL OPENING AND EXERCISING OF THE ADS AND LLS RELIEF VALVES, for LLS PSV 4407 must be run Drior to raising reactor Dower.

Currently one bypass valve is open 75%. The STP reauires that one bypass valve be opened 100% and the second be open 15%. When he STP is complete continue with the plant start UP.

Torus Cooling has been Dlaced in service preparation of the STP. and TS 3.5. I Condition B has been entered.

STP 3.6.2.1-01, SuDpression Pool Water Temperature Surveillance, is available for when you open the SRV.

STP 3.8.1-04, Standby Diesel Generators Operability Test, (Slow Start From Norm Start Air) is in progress. The A EDG has been tested satisfactorily. The B EDG test is in progress. The STP is complete through step 7.2.25. It is currently in its one hour run for TS, and the 2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> run for stabilization of the Generator Stator and Main Bearing temperatures.

U n g the start up the Start 1Jp-d Rex Valve \\as sticking. It Mas dccidcd that thr SI&

Feed Kcl: .Valve be isolated and Ipcl he controlled via the B. Feed Reg Valve. At tlic beginning of)nir.shift, there arc 2 9 & C techs going to look at thegerator. I he\ maycall for your assistance to cycle the vahc.

I & C has asked that the A IRM be bypassed for a short time. They are working near the preamp and do not want to give the plant any half scrams. The work should take about 45 minutes, then the A IRM may be unbyuassed.

There is a severe thunder storm warning for the next 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> for the Linn and Benton Counties.

Event 1 Malf 1 Event Event No. 1 No: I Type* Description I R (RO) A control rod pull briefwill be conducted. At the end of the brief, the RO will raise power with control rods to achieve I bypass valve 100% open and the second bypass valve 15% open. During the power ascension, the C IRM will fail up scale resulting in a half scram. When the target conditions are met, the STP can be run.

2 1 I The RO will respond to annunciators lC05A 8-3, C-3, and A-2.

(ROISRO) C IRM will fail up scale resulting in a half scram. The RO will bypass the failed IRM and reset the half scram. This is a TS entry due to the loss of the C IRM and another IRM bypassed. The actions of the TS are already met, and the TS is exited when the operable IRM is unbypassed and the failed IRM is bypassed. TS is 3.3.1 . I Condition A is momentarily entered 3

I N (BOP) Performance of STP 3.4.3-03, Manual Opening and Exercising of the ADS and LLS Relief Valves for PSV 4407 will be run.

The B Feed Reg valve will lock up due to an air line being broken 4 ! 2 off during the repairs to the Start Up Feed Reg Valve. The RO will respond IAW ARP I C05A F- I .

Shortly after the lock up, the I & C Techs working on the start up feed reg valve, will call and confess that they inadvertently caused the lock up and the condition for the lock up is cleared.

i The RO will unlock the B feed reg valve IAW the ARP.

C (BOP) The B EDG will develop a problem. The BOP will send the Aux man to investigate. The report back from the EDG room will state and that there are 2 annunciators on IC94, A-3, JACKET COOLANT TS (SRO) LEVEL LOW, and A-4, JACKET COOLANT TEMPERATURE HIGH OR LOW. The report will also state that the jacket coolant temperature is currently 195 degrees and going up.

The BOP will remove the B EDG from service and the SRO will enter the applicable TS 614 C

BOPISRO)

PSV 4407 will not close when the HS is taken to the Auto position.

AOP 683 will be entered. Per the AOP, the valved will be cycled.

After the cycling, it will be determined that the SRV did not close.

Based on the AOP, the crew will insert a manual scram.

7 5 M The condensate pump transient will result in a rupture of feedwater piping in the DW. The rupture will occur at the feed water check valve. This will result in a drywell high pressure and entry into EOP I and EOP 2.

On the 2-psig signal, 1A3 will lock out due to a short in the A CS motor.

The B CS pump will trip For EOP 2, the crew will have to spray the drywell. The Crew will also have to monitor Torus water level and secure Condensate and Feed to stop the torus water level rise.

Because RPV pressure is so low, HPCl and RClC will isolate shortly after the event.

The RHR inject valve will fail to automatically open The BOP will have to control his injection into the RPV with CS and/or LPCI.

The BOP will determine that the inject valve for RHR did not open automatically and take actions to manually open the valve.

(N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Form ES-Dl for ESG 2 The following are the changes made after discussing the 75 day submittal with the NRC.

Requested that the group 2 be able to be reset. This will allow the BOP to reposition the closed valves.

Asked if the GEMAC level transmitter failure would be better if it were to happen when power was being raised.

o After validation, it was determined that this event be moved just prior to the ESG going into its Major event.

It was requested that Event 7 and 8 be combined. The Lube oil problem and the BOPS actions to start the pumps is a stand-alone event.

This left Event 8 to be the continuing deterioration of the turbine lube oil and the beginning of the ATWS It was suggested that the BOP be able to get a component failure by pulling the fuses for the ATWS. This became event # 9.

Deleted the follow-up for a new event 10. Not necessary as the crew will pick up the actions when the ATWS is complete.

4ppendix D Scenario Outline Form ES-D-1

acility: DAEC Scenario No.: ESG 2 Op-Test No.: 2005-01 lxaminers: Operators:

nitial Conditions: The plant is at 1 SOOMWth.A CS D u m is tagged out to repair a lower tearing. TS 3.5.1 Condition B has been entered.

urnover: Power has been lowered to perform NS-930002. Turbine Stop Valve and Combined ntermediate Valve Test.

he A CS pump is taeged out for replacement of the lower bearing. TS 3.5.1 Condition B has ieen entered. and are currentlv in dav 3 of 7 of the LCO. Work is expected to be complete in 2

,ast shift the I & C Techs just finished work on the LT-4559. which feeds into the feedwater eve1 control circuit and the A GEMAC level indicator. The I & C Techs and Svstem Eneineer vould like to maintain level control in A over night to observe its response.

T-pF Event Event Type*

N (BOP)

Event Description Performance of NS-930002, Main Turbine Stop and Combined Intermediate Valve Test R (W Begin raising power with reactor recirc to achieve 80%

capability.

C B recirc speed controller will fail and will begin to run (RO/SRO) away requiring the RO to lock it up. This will require a TS check to determine if the speed mismatch between the two recirc pumps is with in the required hand.

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C Spurious Group 2 isolation with the failure of CV 3729

BOP/SRO) failing to isolate. This will require entry into TS for a failed primary containment isolation valve.

This spurious group 2 will he able to he reset. This will allow the BOP to re-align the non failed valves of the isolation.

C (BOP) The running River Water Supply pump trips requiring entry into AOP 410. The operator will assess the situation and start another RWS pump.

C (BOP) A slow leak in the Turbine Lube oil system will develop requiring entry into ARP IC07A A-7.

IAW ARP 1C07A A-7 the operator is to verify that additional turbine lube oil pumps start. These pumps fail to auto start requiring the BOP operator to manually start them Lube oil will recover after the EBOP is started.

I The A GEMAC level transmitter will fail upscale (ROiSRO) requiring that level control be transferred to B. This is also a TS for GEMAC level instruments being > 2.5 apart.

M (all) The lube oil pressure will momentarily recover. However as the leak worsens, the system pressure continue to lower.

This will force the crew to enter AOP 693, Main TurbineEHC Failures When the crew attempts to scram the plant they will determine that an electrical ATWS prevents the rods from inserting.

They will enter Power Level control, (EOP Contingency) to lower reactor power.

C (BOP) The control rods will be inserted by pulling the RPS fuses per RIP 101.2.

I* (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor

Form ES-Dl for ESG 3 The following are the changes made after discussing the 75-day submittal with the NRC.

Asked to have some equipment out of service at the beginning of the event.

o Broke the RCIC o Had 3 1T136 tank high level a l m s come in the past shift.

Asked to move event 4 to just before the conductivity event. The transformer trouble is to set up the ALC, but they are performing a JPM on the offsite sources and it was discussed that it could be a double jeopardy. So it was moved to the end while the conductivity event is occurring so the STP will not have to be performed.

For Event 4, it was stated that the crew would call the control rod inoperable.

It was requested that event 7 and 8 be combined into 1.

Added another component failure for the BOP after the LOCA. HPCI flow controller will fail in automatic. The BOP will transfer to manual and be able to inject for a short period of time.

m n d i x. I). Scenario Outline .......... Form KS-11-1 Facility: DAEC Scenario No.: ESG 3 Op-Test No.:2005-01 Examiners: Operators:

Initial Conditions: The plant is operating at 100% capabilitv. RClC is inoperable. The crew has been receiving IT136 tank hi level alarms.

Turnover: The plant is operating at 100% capabilitv. It is a warm summer dav. The B RHRSW pump is to be started for chernistrv to obtain a sample. You are to start the B RHRSW pump, IAW 0 1 416, and then call the Chemists.

RClC is inoperable due to finding water in the oil. The RClC turbine has been tripped. The mechanics are down looking at the RClC turbine. They are working with the WCC on how the tagout should be written. The WCC will inform you when they are ready to tag out the RClC turbine. Because of RClC inoperable, TS 3.5.3 Condition A has been entered. Currently in day 1 of 14.

The plant received 3 1T136 high-level alarms, 1C07B D-IO. Each alarm staved in for about 90 seconds.

Event Event Type* Description 1 N (BOP) IAW 01 416, start the B RHRSW pump.

2 1 An APRM flow unit will fail down scale. This will result in a half scram. RO will respond to ARP IC05A E-2 for the flow unit, and 1C05A A2 for the half scram. Per the actions of ARP 1C05A E-2 the RO will remove the A flow unit from service and reset the half scram.

3 2 C The B RHRSW pump will develop a motor bearing (BOP/SRO) problem and begin to seize up. The BOP will have to remove the RHRSW pump from service.

The SRO will enter TS 3.7.1 Condition A.

4 4 C A control rod will drift in, (OE 18716). Per the actions of (ROISRO) ARP IC05 A D-6, the RO will stop the drifting by applying an Emergency In signal to the control rod. TS will be entered for either an inoperable control rod.

5 5 C (BOP) The #3 feed water heater controller will fail in AUTOMATIC. This will require controlling the feedwater heater in manual.

6 3 C The Start up transformer will receive annunciator IC08A A-(BOP/SRO) 7, Start Up Transformer Trouble. When investigated the problem will require the transformer to be removed from service.

This will require entry into TS 3.8.1 Condition A, for loss of one offsite power source.

7 6 Condenser Hot Well conductivity will begin to rise due to a tube leak. The crew will enter AOP 639 IAW AOP 639 when the influent conductivity of the condensate demineralizers reaches 1 micro mho, the crew will perform a fast power reduction with recirc to 27 million Ibm/hr flow and scram the plant 8 7 M (all) When the plant gets to 27 million lbmlhr flow, a manual scram will be inserted Following the reactor scram a LOCA will develop.

The crew will enter EOP 1 and 2 Torus and Drywell sprays will be initiated to protect the containment.

HPCl will malfunction and trip.

Due to failure high-pressure injection systems, ALC will be entered.

The available inject systems will be lined up. When RPV level lowers to +I5 inches an ED will be performed.

8 C (BOP) HPCls flow controller will fail in automatic. The BOP will diagnose the problem and place the flow controller in manual and inject into the RPV for a short period of time.

HPCl will eventually trip so the ED can occur.

1 (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor