ML031130730

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Final - Section C Operating
ML031130730
Person / Time
Site: Hope Creek PSEG icon.png
Issue date: 04/01/2003
From: Reid J
Public Service Enterprise Group
To: Conte R
NRC/RGN-I/DRS/OSB
Conte R
References
50-354/03-301 50-354/03-301
Download: ML031130730 (22)
v • d • e


Text

Ann#endiiy D Scenario Outline Form ES-D-1 An~niyFl Scenari OutlIne For _ES-D..

Facility: Hope Creek Scenario No.: 1 Op Test No.: 1 Examiners: Candidates: LSRO

_LSRO

_LSRO Obiectives: Evaluate applicants' response to an SRM failure. Applicant determines requirements for CRB removal are not met. Evaluate applicants' response to a CRD Mechanism leak. Discuss the effects of lowering fuel pool level. Demonstrate knowledge of method to stop CRDM leak from above with CRB.

Initial Conditions: Operational Condition 5, core alterations in progress. The Reactor Mode Switch is Operable and locked in Refuel position. All Control Rods are inserted except rod 30-31 for friction testing.

The CRDM for 14-23 has been replaced after rebuild. All SRMs are operable. Shutdown Margin requirements are met. The Dominion Engineering Inc. (DEI) FSP tool with grid guide is attached to the Frame Mounted Aux Hoist. The Control Rod Grapple is on the Monorail Hoist.

Turnover: You are the Refueling SRO. All fuel is in the vessel except the 4 bundles of the 14-23 cell.

Control Rod Blade 14-23 needs to be removed and replaced. The Control Rod Blade 14-23 is fully withdrawn with the CRDM uncoupled from under-vessel. The double blade guide was just removed from cell 14-23 and is on the Main Hoist. You are at Step 5.3 of HC.RE-FR.ZZ-0002.

Event No.

l J

Malf.

No.

l Event Type*_

Event Description 1 Evaluator Guide 1 SRM A fails to zero (0) cps Reviews Tech Spec 3.9.2 for SRM Operability.

Determines core alterations may continue for 14-23.

2 N/A N Removal of the Control Rod Determines rod does not meet Blade. Tech Spec 3.9.10.1 requirements for a single control rod removal. Rod 30-30 must be fully inserted.

Discusses Restricted Core Operations Form (RCOF) to continue.

Remove fuel support piece.

Uses CRB Grapple on Monorail Hoist to remove CRB.

HC LSRO ES 1 Rev. 2/14/03 Page 1 of 2

_I 3 NA M Under vessel crew reports water Recognizes cavity level would pouring out 14-23 CRDM flange. be lowering and takes actions They are unable to stop the of HC.OP-AB.COOL-0004 Fuel leak. Pool Cooling.

-Evacuates the Refuel Floor

- Notifies Control Room.

- Notifies Reactor Engineer.

- Notifies Radiation Protection.

Recognizes that the CRB needs to be placed back into the guide tube to bottom in order to stop leak. (Not required for full credit) 4 N/A M Reactor Engineer and OS Puts CRB back into guide tube concurs with placing CRB back and lowers to the bottom to stop into guide tube. the leak.

I (N)ormal, (R)eactivity, (I)nstrument, (C)omponent, (M)ajor HC LSRO ES 1 Rev. 2/14/03 Page 2 of 2

Op-Test No. HC LSRO Scenario No. 1 Event No.: 1 Initial Conditions: Operational Condition 5, core alterations in progress.

  • The Reactor Mode Switch is Operable and locked in Refuel position.
  • The CRDM for 14-23 has been replaced after rebuild.
  • The Dominion Engineering Inc. (DEI) FSP tool with grid guide is attached to the Frame Mounted Aux Hoist.

Turnover: You are the Refueling SRO.

  • All fuel is in the vessel except the 4 bundles of the 14-23 cell.
  • Control Rod Blade 14-23 needs to be removed and replaced.
  • The Control Rod Blade 14-23 is fully withdrawn with the CRDM uncoupled from under-vessel.
  • You are at Step 5.3 of HC.RE-FR.ZZ-0002.

Event

Description:

SRM A fails to zero (0) cps.

Examiner Cue: SRM "A"DOWNSCALE alarm in the Control Room. The ROD OUT MOTION BLOCK annunciator is also in alarm. Analyze the effects of these alarms to continuing Core Alterations. When requested, CUE: SRM "A"is reading 0 cps.

Time I Position Applicant's Actions or Behavior LSRO Reviews Tech Spec 3.9.2 for SRM Operability.

LSRO

  • Determines core alterations may continue for 14-23.

LSRO Determines core alterations may continue for quadrants B, C, and D.

LSRO Requests RE to revise move sheets accordingly.

Last printed 03/20/2003 4:01 PM

Op-Test No. LSRO Scenario No. 1 Event No.: 2 Event

Description:

Removal of the Control Rod Blade.

Examiner Cue: Continue with Removal of Control Rod Blade 14-23

[Time ] Position Applicant's Actions or Behavior Cue: When asked, provide Restricted Core Operations Form (RCOF).

LSRO Reviews Restricted Core Operations Form (RCOF).

LSRO

Ref: Tech Spec 3.9.10.1.e Cue: Control Rod 30-31 is now re-inserted. The Control Room tells you to continue with 14-23.

Fuel Support Piece Removal using the Fuel Support Grapple.

Ref: HC.RE-FR.ZZ-0002 5.3 Cue: Step 5.3. I.A is already completed.

LSRO

  • 5.3.1.B. Ensure the ENGAGE push-button on the hoist pendant is DEPRESSED and the RED light is NOT illuminated.

LSRO 5.3.1.C Using the Frame Mounted Aux Hoist controls, position the fuel support grapple above the upper grid. Align the grapple with the grid diagonal.

Cue: Grapple is aligned.

LSRO 5.3.1 .D Lower the grapple through the grid.

LSRO 5.3.1 .E &F Lower the grapple into position above the FSP.

LSRO 5.3.1.G Lower the grapple through the coolant holes of the FSP. Continue lowering until the cable goes slack. Verify the engage air supply is on.

Cue: Cable is slack; Engage air supply is on.

LSRO

  • 5.3.1.H Verify the AMBER Light is on.

Cue: Amber light is illuminated on the fuel support piece grapple tool.

LSRO 5.3.1.1 Raise hoist and Verify engagement of FSP by observing weight increases to approximately 130 pounds.

Cue: Hoist reads 130 pounds.

LSRO

  • 5.3.1.J Slowly raise hoist until Amber signal is extinguished Last printed 03/20/2003 4:01 PM

Op-Test No. LSRO Scenario No. 1 Event No.: 2 Time Position [ Applicant's Actions or Behavior Cue: The Amber light is extinguished.

LSRO 5.3.1.K Continue raising the hoist.

LSRO

  • 5.3.1.L Raise the FSP to the level of the upper grid. When the FSP has cleared the grid then move to a storage location.

Cue: The Fuel Support Piece is above the upper grid and will remain on the hoist.

LSRO Control rod Removal using Control Rod Grapple.

Ref: HC.RE-FR.ZZ-0002 5.5 LSRO 5.5.1 Verify that prerequisite 2.16 was completed based on the control rod grapple.

Cue: Prerequisite 2.16 was completed 5.5.2 Install grid guide NA (already installed on FSP tool) Step 5.5.3 is NA.

LSRO 5.5.4 Verify with Ops that Control Rod is uncoupled from its drive.

Cue: Control Rod 14-23 is uncoupled from its drive.

LSRO 5.5.5 Maneuver the refuel platform and Monorail Hoist to obtain direct vertical alignment over the reactor core location where the control rod is to be removed.

Cue: The Monorail Hoist is directly above the stated core location.

LSRO 5.5.6 Lower the grapple to a level just above the upper core l _ grid.

Cue: The grapple has been lowered as stated.

LSRO

  • 5.5.7 Depress the DISENGAGE pushbutton.

Cue: The controls stated have been operated as stated.

LSRO 5.5.8 Rotate the hoist cable for alignment.

Cue: The hoist cable is aligned as stated.

LSRO

  • 5.5.9 Lower the control rod grapple through the upper core grid. Continue to lower the control rod grapple until the hoist cable is slack.

Cue: The grapple has been lowered until the cable is slack.

Last printed 03/20/2003 4:01 PM

LSRO

  • 5.5.10 Depress the ENGAGE pushbutton.

Cue: The controls stated have been operated as stated.

LSRO 5.5.11 Request operations continuously observe the control rod position indication to ensure that the position does not change as the control rod is moved.

Cue: Operations will observe as requested.

LSRO

  • 5.5.12 Raise the grappled control rod to the hoist upper limit.

Cue: The controls respond as stated. The CRB is grappled and the load cell reads 325 lbs. The hoist reaches the hoist upper limit.

Op-Test No. LSRO Scenario No. 1 Event No.: 3 Event

Description:

Under vessel crew reports water pouring out 14-23 CRDM flange.

They are unable to stop the leak.

Examiner Cue: The Under vessel crew reports waterpouring out 14-23 CRDM flange.

They are unable to stop the leak.

Time Position Applicant's Actions or Behavior LSRO Recognizes cavity level would be lowering and takes actions of HC.OP-AB.COOL-0004 Fuel Pool Cooling.

LSRO

  • Evacuates the Refuel Floor of non-essential personnel.

LSRO Notifies Control Room.

LSRO Notifies Reactor Engineer.

LSRO Notifies Radiation Protection.

LSRO

  • Recognizes that the CRB needs to be placed back into the guide tube to bottom in order to stop leak.

LSRO The operator requests permission to return the CRB to 14-23 cell.

Last printed 03/20/2003 4:01 PM

Op-Test No. LSRO Scenario No. 1 Event No.: 4 Event

Description:

Reactor Engineer and OS concurs with placing CRB back into guide tube.

Examiner Cue: The Reactor Engineer and operations Superintendent concurs with placing CRB back into guide tube.

Time [Position Applicant's Actions or Behavior LSRO

  • Operator returns CRB to cell 14-23 and lowers until fully seated to stop leak.

Cue: You have reached the termination point for the scenario.

Last printed 03/20/2003 4:01 PM

ATTACHMENT 2 RESTRICTED CORE OPERATIONS FORM Refuelinq Outaqe: 11 RCOF No. I I I SECTION A SECTION B SECTION C The reactor shutdown margin Control rod has been verified required by Technical The Requirements of The withdrawn control rod is to be inthe fully inserted CNRL Specification Limiting Technical Specification Th fetwithdrawn controlrodi The control rod cell contains position.

CONTROL Condition for Operation Limiting Condition for safety tagged and/or proper control rod supports to ROD 3.9.10.1.c or 3.9.10.2.c, as Operation 3.9.10.1 or 3.9.10.2 administraively controlled to permit control rod insertion NOTE: Fuel loading into the LOCATION appropriate, with specified items a, b, d, e, and f are prohibit Inadvertent control rod (e.g., double blade guide). core is NOT permitted control rod fully withdrawn is satisfied as appropriate. motion.UNLESS ALL control rods are satisfied fully inserted..

Reactor Engineer/Date OS/CRS/Date OS/CRS/Date OS/CRS/Date OS/CRS/Date 0 14-23 17; o I Re R F s, 7I a Z 4R 9,4sS4R7I TODA YS DATE TODAYS DATE TODAYS DATE 4 4 +

4 4 + 4 H 4 4 + 4 4 0

4 4 4 4 4 4 4 4 4 4 0

lot Last printed 03/20/2003 4:01 PM

HC.RE-FR.ZZ-0002(Q)

ATTACHMENT 5 CONTROL ROD MOVEMENT SHEET REFUEL NO. 11 SHEET NO. 1 CONTINUED ON SHEET N/A Step I.D. FROM TO Camera Time & Initials Number Number Location Location Verified Date Verified 01 DBG CORE MAIN HOIST N/A 5MINUTESAGO re 13-22/15-24 TODA YS DATE 02 FSP CORE FRAME N/A 14-23 14-23 MOU NTED 03 CRB CORE MONORAIL N/A 0

14-23 14-23 HOIST VACUUM CONTROL ROD GUIDE TUBE It 04 CRB 14-23 MONORAIL HOIST CORE 14-23 N/A H

05 FSP FRAME CORE 14-23 MOUNTED AUX HOIST 14-23 0

06 DBG MAIN HOIST CORE N/A 13-22/15-24

,to 0

3/17/03 3/17/03 3/17/03 Prepared By Date Verified By Date Supv.Reactor Eng. Date Hope Creek Page 58 of 58 Rev. 20

Initial Conditions: Operational Condition 5, core alterations in progress.

  • The Reactor Mode Switch is Operable and locked in Refuel position.
  • The CRDM for 14-23 has been replaced after rebuild.
  • The Dominion Engineering Inc. (DEI) FSP tool with grid guide is attached to the Frame Mounted Aux Hoist.

Turnover: You are the Refueling SRO.

  • All fuel is in the vessel except the 4 bundles of the 14-23 cell. Q
  • Control Rod Blade 14-23 needs to be removed and replaced. f
  • The Control Rod Blade 14-23 is fully withdrawn with the CRDM uncoupled from under-vessel.
  • You are at Step 5.3 of HC.RE-FR.ZZ-0002.

H 0o

CORE MAP 0 Deg 39 4143 45 47 49 51 53 5557 59 N

01 03 05 07 09 11 13 15 17 19 21 2325272 313335 3739 41 43 4547 49 51 53555759 LPRM

{ IRM 1 SRM

Annendix D Scenario Outline Form ES-D-1 I._-- S, a Facility: Hope Creek Scenario No.: 2 Op Test No.: 1 Examiners:_ Candidates: LSRO

_LSRO LSRO LSRO Obwectives: To evaluate the applicants' ability to recognize and address problems with control rod support. Recognize HC.OP-AB.CONT-0005 IRRADIATED FUEL DAMAGE entry and take required actions.

Initial Conditions: Core Alterations are in progress. A fuel bundle is in the Fuel Prep Machine, being re-assembled. A move sheet and core map is provided.

Turnover: You are the Refueling SRO. Double blade guide 29-26/31-28 is about to be removed from the core.

Event Malf. Event Event Evaluator No. No. Type Description Guide 1 N/A N Double blade guide removed IAW Double Blade Guide is grappled to HC.OP-SO.KE-0001 be removed from the core location according to procedure.

2 1 N Provide adequate support for Determines inadequate support Control Rod 30-27. and initiates corrective action.

3 N/A C A fuel bundle fails in a location Notify Control Room.

causing high radiation conditions on the Refueling Floor and in the Implement actions of HC.OP-Drywell. AB.CONT-0005 IRRADIATED FUEL DAMAGE.

Suspends all refueling operations.

Recognizes radiological effects on the Drywell.

4 N/A M Refuel Floor Exhaust Hi-Hi Evacuate the refuel floor.

I Radiation alarms Recognizes FRVS auto start and Reactor Building Ventilation isolation setpoints.

5 N/A M Classify the event. Classifies the event as an ALERT lAW ECG 6.4.2.a

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

Scenario No.No. 2 Event No.: 11 Op-Test No. HC LSRO HG LSRQ Scenario 2 Event No.:

Initial Conditions: Core Alterations are in progress. A fuel bundle is in the Fuel Prep Machine, being re-assembled.

Turnover: You are the Refueling SRO. Double blade guide 29-26/31-28 is about to be removed from the core. A move sheet and core map is provided.

Event

Description:

Double Blade Guide (DBG) 29-26/31-28 removed IAW HC.OP-SO. KE-0001.

Examiner Cue: The Main Fuel Grapple is unloaded and positioned above Double Blade Guide (DBG) 29-26/31-28 in the Full Up position.

Time Position Applicant's Actions or Behavior Ref: HC.OP-SO.KE-0001 5.5 LSRO 5.5.1 Ensure that all prerequisites have been satisfied IAW Section 2.5 of this procedure.

Cue: All prerequisites have been satisfied.

LSRO 5.5.2 Use the Refuel Platform and Trolley Position Controls to maneuver the Fuel Grapple to the coordinates listed on the Fuel Movement Sheet(s). Digital position Indication System should be used for single blade guides.

Cue: The Fuel Grapple is positioned above Double Blade Guide (DBG) 29-26/31-28 in the Full Up position.

LSRO 5.5.3 Ensure the fuel grapple is at the correct Core or Fuel Pool Coordinates.

LSRO Operator checks map and move sheet. Confirms location is correct.

LSRO

  • 5.5.4 LOWER the Fuel Grapple to approximately one foot above the blade guide to be removed by using the Fuel l _ Grapple Hoist control in the LOWER position Cue: Fuel hoist has been lowered to approximately one foot above the blade guide.

LSRO

  • 5.5.5 ROTATE the Fuel Grapple so that the grapple hooks are in line with the blade guide handle.

Cue: Grapple hooks are aligned.

Last printed 03/31/2003 9:13 AM Page 1 of 5

LSRO

  • 5.5.6 PLACE the GRAPPLE ENGAGE/RELEASE Switch to the RELEASE to ensure the Fuel Grapple hooks are open, OBSERVE the grapple ENGAGE light off.

Cue: The controls stated are in the positions stated. The I _ Grapple ENGAGE light is off.

LSRO

  • 5.5.7 Slowly LOWER the Fuel Grapple UNTIL the Fuel Grapple is resting on the blade guide handle. Grapple may be gently twisted to seat on handle Cue: The grapple lowers until seated.

5.5.7.A OBSERVE the Fuel Grapple Hoist downward motion automatically stops.

Cue: The Fuel Grapple Hoist downward motion automatically l_ stops.

LSRO 5.5.7.B OBSERVE the SLACK CABLE light on.

Cue: The SLACK CABLE light is on.

LSRO ENSURE Fuel Grapple is at required depth by observing HOIST GRAPPLE ELEVATION Digital Readout.

Cue: The digital readout reads approximately 548". (NOTE:

This is the value of the top of a fully seated fuel bundle plus 6 inches. These numbers are NOT required from memory and are not written in any procedure.)

LSRO

  • 5.5.8 PLACE the GRAPPLE ENGAGE/RELEASE Switch in the ENGAGE position to grapple the blade guide AND OBSERVE the GRAPPLE ENGAGE light on.

Cue: The grapple ENGAGE Light is on.

LSRO CAUTION 5.5.9 DO NOT remove a blade guide from its Reactor Core location if the respective control rod will be left unsupported.

When asked, Cue: Fuel Bundle 29-28 is in the core.

When asked, Cue: Fuel Bundle location 31-26 is empty.

LSRO

Last printed 03/31/2003 9:13 AM Page 2 of 5

Op-Test No. LSRO Scenario No. 2 Event No.: 2 Event

Description:

Provide adequate support for Control Rod 30-27.

Examiner Cue:

You have returned to the fuel pool. The fuel bundle for location 31-26 is now grappled Time [ Position l Applicant's Actions or Behavior LSRO Operator discusses options of putting either a fuel bundle or single blade guide in location 31-26 and

  • requests a revised Move Sheet.

Cue: The fuel movement sheet for fuel assembly 31-26 was inadvertently signed off Provide new move sheet #2 for bundle location 31-26.

Cue: You have returned to the fuel pool. The fuel bundle for location 31-26 is now grappled and full up on the Fuel Hoist in the Fuel Pool.

LSRO Operator determines beginning step to be 5.3.13 of HC.OP-SO. KE-0001.

LSRO

  • 5.3.13 USE the Trolley position control to position the Fuel Grapple in direct alignment with the center of the fuel transfer path to the Reactor Well.

Cue: The fuel grapple is aligned as stated.

LSRO

  • 5.3.14 USE the Refuel Platform Position Control in the REVERSE position to maneuver the Refuel Platform to the Reactor Cavity area.

Cue: The Refuel Platform is moving towards the Reactor Cavity.

Last printed 03131/2003 9:13 AM Page 3 of 5

lOp-Test No. LSRO Scenario No. 2 Event No.: 3 Event

Description:

A fuel bundle fails in a location causing high radiation conditions on the Refueling Floor and in the Drywell.

Examiner Cue: The once burned fuel bundle on the fuel grapple free falls and lands horizontally on the end of the Cattle Chute above the RPV flange. The bundle is broken into several pieces.

Time Position Applicant's Actions or Behavior LSRO

  • Notifies the Control Room.

LSRO Implement actions of HC.OP-AB.CONT-0005 IRRADIATED FUEL DAMAGE.

LSRO

  • Suspends all refueling operations.

CUE: The Spent Fuel Pool Area Radiation Monitor alarms.

LSRO Notify Radiation Protection of the condition.

Cue: What areas of the plant will be directly affected by the radiation from the bundle?

LSRO Operator discusses increased radiation concerns inside the Drywell area.

Op-Test No. LSRO Scenario No. 2 Event No.: 4 Event

Description:

Refuel Floor Exhaust Hi-Hi Radiation alarms.

Examiner Cue:

The Control Room informs you that Refuel Floor Exhaust Hi-Hi Radiation alarms.

Time Position Applicant's Actions or Behavior LSRO

  • Direct the crew to evacuate the refuel floor.

LSRO Recognizes FRVS auto start and Reactor Building Ventilation isolation setpoints.

Last printed 03/31/2003 9:13 AM Page 4 of 5

Op-Test No. LSRO Scenario No. 2 Event No.: 5 Event

Description:

Classify the event.

Examiner Cue:

Classify the event including E.A.L number based on the information given.

Time Position Applicant's Actions or Behavior LSRO Reviews Event Classification Guide (ECG) and Technical Basis.

LSRO

  • Classifies the event as an ALERT lAW EAL # 6.4.2.a CUE: You have reached the termination point for the scenario.

Last printed 03/31/2003 9:13 AM Page 5 of 5

(

HC.RE-FR.ZZ-0001 (Q)

ATTACHMENT I FUEL MOVEMENT SHEET REFUEL NO. N/A SHEET NO. 1 CONTINUED ON SHEET N/A i

0 It Step ID. FROM Time TO Time Operator Verified By Number Number Location Orien- Date Location Orien- Date InitialsInitials tation tation l 01 YJP424 SFP NE Todays Date CORE NE 31-26 AE-43 5 minutes ago H

02 DBG CORE 29-26/31-28 SFP RACK

  1. 21, or 22 0 n

I

_ 1 I__ I-+I Iat

_ I i i-Gusa Idwwe'

~~o X"~_AaAai9 1 Prepared By Date Independently Verified By Date Page 18 of 23 Rev. 20 Ilopec Creek

HC.RE-FR.ZZ-00u (Q)

ATTACHMENT 1 FUEL MOVEMENT SHEET REFUEL NO. N/A SHEET NO. 1 CONTINUED ON SHEET N/A 0

Step I.D. FROM Time TO Time Operator Verified By Number Number Location Orien- Date Location Orien- Date Initials Initials tation _ tation 01 DBG CORE SFP RACK 29-26/31-28 #21, or 22 I +/-

I 0

I I I

44 1I

+4 4 4 4

4 I I I

I 4t gooda'a , oza'a 3?Jhza{/ Am 3a/uzx o9/~Dayte a1 Prepared By Date Independently Verified By Date Hop~e Creek Page 18 of 23 Rtev. 20

L866 888l 617 159 1 25301

CORE MAP 0 Deg 01 03 05 07 09 11 13 15 17 19 21 23 25 27 29 31 33 35 37 39 41 43 45 60 47 49 51 53 5557 59 60 58 3B31E3 lll 56 58 56 54 52 .5Z 54 50 50 48 g W 1 B g1 S 1 1 g g 48 46 ihuW 5046

.44 mom 42 SI-MMuTlEm 44

~S~u~

40 BqE I 42 38 MogSEuguususemS 40 36 E12SESNS ~ T 38 joofl r 36 34 g0~

N w 34 IM Her I 32 30 1 I m 28 § s EWIisE 30 26 ml~

28 24 E~flm11 flE~SD1 l 26 1L11~~SgS 24 22 Sog~B~wg 22~gflg 20 0MM METIll §@3SgS Sl-B 2 16 MMISMO 16 14 b- I0 b-0 14 12 oom toElEB1E ml~BlT 12 08OBall la glig l l l 08 06 06 04 MILE ME 02 MOMSIg 04 JIg11 02 01 03 05 07 09 U 13 15 17 19 2123 25 27 3133 35 37 39 41 43 45 47 49 51 53 55 57 59 O LPRM NIRM S8RM

Initial Conditions: Core Alterations are in progress. A fuel bundle is in the Fuel Prep Machine, being re-assembled.

Turnover: You are the Refueling SRO. Double blade guide 29-26/31-28 is about to be removed from the core. A move sheet and core map is provided.

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