.I Entefgy 1 CONDITION REPORT 1 C R - P N P - ~ O O ~ - O ~ ~ ~ ~ 1 Originator: Olson,Erjc W

Originator Group: Operations Mgmt

Supervisor Name: Dietrich,Peter T

Discovered Date: 04/19/2003 17:43

Originator Phone: 8744 Operability Required: Y

Reportability Required: N

Initiated Date: 04/19/2003 17:47

Condition Description: During 8.7.3, Secondary Containment Leakage Test, noted that the SBGT fan A flowrate may be slightly degraded. The fan was able to maintain the secondary containment pressure as required during the test with the inner reactor building door closed.

Immediate Action Description:

Suggested Action Description:

TRENDING (For Reference Purposes Only): Trend Tvpe Trend Code

CRT=EF PI=SI W = S T

ADMIN Entergy I Initiated Date: 4/19/2003 17:47 Owner Group :Eng Sys Mgmt

Current Contact: R. HUNNEFEiLD - OE Current Significance: C - CORRECTION

Closed by: Shatas,Albert A 9/30/2003 9 5 2

CR-PNP-2003-01413

Summary Description:

Remarks Description:

Closure Description: OE03.022 A11 CA's associated with this CR were reviewed by the responsible manager. Upon the manager's recommendation, this CR is being closed.

Per ENN-LI-102, Para. 5.8.2.3: Independent reviews are not required for non-significant condition reports. The documented closeout verification performed by the Responsible Management is adequate authorization for closure of the CR.

OPERABILITY

OperabilityVersion: I

Operability Code: EQUIPMENT INOPERABLE

Immediate Report Code: NOT REPORTABLE

Performed By: Pau1,Stanley W 04/20/2003 0628

Approved By: Haislet,Randy E 04/20/2003 07:06

Operability Description: SECONDARY CONTAINMENT IS OPERABLE. THE RB OUTER TRUCK LOCK DOOR IS INOPERABLE. LCO 1-03-0125 FOR RB OUTER TRUCK LOCK DOOR ISOLATION 1-03-1/56-0002-A IN PLACE ON THE INNER RB TRUCK LOCK DOOR TO MAINTAIN SECONDARY CONTAINMENT

Approval Comments:

Entergy I OPERABILITY I CR-PNP-2003-01413 OperabilityVersion: 2

Operability Code: OPERABLE - JUDGEMENT Immediate Report Code: NOT REPORTABLE

Performed By: Mantenfe1,Martin B

Approved By: Mantenfe1,Martin B

Operability Description: OE 03-021 with EE 03.027

Approval Comments: none

06/19/2003 15:44

06/19/2003 15:45

Attachments: Operability Description

Operability eval

Attachment Header Document Name:

CR-PNP-2003-01413 Version - 002 I I_-_Ix” __ ~ -~ -- r_ . _. -- Document Location

Attach Title:

]Operability eval - _ -

J

OPERABILITY AND IMMEDIATE REPORTABILITY DETERMINATION

NOTE

All sections of this Attachment are to be filled out. If the information is not required (N/R), it shall be indicated as such.

Condition Report # CR-PNP-2003-01413 Secondary SBGT “ A

Train Component ID # ContainmenVSBGT System # 50148 Problem Description: During 8.7.3, Secondary Containment Leakage Test, noted that the SBGT fan A flowrate may be slightly degraded. The fan was able to maintain the secondary containment pressure as required during the test with the inner reactor building door closed.

Reactor Mode: RUN Reactor Power: 100 Yo in. .. ..

Moderator Temperature (if shutdown): “F RPV Level: Reactor Pressure: 1035 psig Core Flow: 60m Ibm/hr Other Pertinent Information: SBGT “ B oDerable with inner TL door open. SBGT “A’ must be declared inop if inner door is opened per’EE 03.027

A. OPERABLEJUDGMENT EQUIPMENT INOPERABLE 6. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .

OPERABLE-JUDGMENT [m “N/R” if Equipment Inoperable] (1) System status prior to discovery of problem: X Operable 0 Inoperable

If inoperable, why? (2) Nature of Problem

Hardware nonconforming condition (equipment is not configured according to design documents) Hardware degraded condition (equipment is according to design but is

IxI degraded or failed) Other (explain)

CAUTION

If auestion (3). (4). or (5) is answered in the affirmative, then a 1 OCFR50.59 review may be , I . . , I required to support the Operability Determination.

(3) Are compensatory actions required to maintain operability? Yes x No (4) Will significant analysis be required to back up engineering

judgments in the operability evaluation? Yes x No (5) Does this issue/problem involve a deviation from the

transient or accident analyses in Chapter 14 of the FSAR? 0 Yes x No Basis for Operability 1

1.3.34.5 Rev. 4

1.3.34.5 Rev. 4

c Sheet 2 of 2 0 P E RAB I L ITY AN D I M M ED I AT E RE PO RTAB I L ITY D ET E RM I N AT1 0 N (Continued)

CAUTION

A 1 OCFR50.59 review, in accordance with ENN-LI-lOO/ENN-LI-lOl, shall be com leted prior to

Alteration (s). implementing compensatory measures that involve a Procedure change(s) and P or Temporary

(7) Compensatory Actions Taken: [m N/R if not required]

-+ cl.

D.

(8) Cognizant Engineer a. Name/Position: F MulcahY Manager: White b. Response Time and Date: 6/19/03 Written EE provided c. Written Engineering Evaluation (NE1 6.04) Due Date:

(Problem Identification date + 1/2 LCO Time) Done 6/19/03 1000

EQUIPMENT INOPERABLE [m "N/R" IF OPERABLEJUDGEMENT] LCO Entered: 0 No O Y e s LCO No. LCO Action Time Tech Spec Action Statement #: Date Entered: Time Entered:

(1) Procedure # (2) Tech Spec #

IMMEDIATE CORRECTIVE ACTIONS TAKEN: (3) WRT/MR # (4) Tagout #

A.

B.

0 Yes x No H 8-HR RPT

Daterrim e:

NRC Event #.:

("1\I/R" if not required)

Is immediate notification required? If yes, mark ap ropriate time requirement

Name of person report made to: 1 OCFR50.72 Requirement: Name of person making report: Station Notifications (see applicable Station Procedure)

4-HR RPT 1 24-HRRPT 1-HR RPT and complete t R is section.

Person/Agency Time Limit (circle action taken

0 Plant Ops Gen Mgr 24 hr, 4hr, lhr 0 NRC (via ENS) 24 hr, 4hr, lhr -

Reg & Ind Affairs Supt

I- Operations Manager NRC Resident Inspector

6.1 9. 03/ 1 530

Person ContactedlTime

Other (specify) England/ Applicable section of 1 OCFR50.72 (specify) 0

Performed by: Mantenfel Datenime: 0

1.3.34.5 Rev. 4

Control Room Log Entry completed by: Mantenfel Datenime: 35 Operability Evaluation (OE) Log updated by: Datenime:

1.3.34.5 Rev. 4

Enfefgy A S S I G N M E N T S

Version: 1

Significance Code: C - CORRECTION

Classification Code: NON-SIGNIFICANT

Owner Group: Eng Sys Mgmt

Performed By: McWilliams,Dorena C

Assignment Description: Responsible Manager: T. WHITE OE number referenced in operability tab should be 0E03-022

CR-PNP-2003-01413

04/20/2003 02:04

CORRECTIVE ACTION 1 CR-PNP-2003-01413 E n t m I CA Number: 1

__I I I--- Name Group 1 _ - I i Assigned By: CRG Mgmt

Assigned To: Eng Design Mgmt

Subassigned To :

White,Thomas F

Originated By: Landeche,David A

Performed By: White,Thomas F

Subperformed By: Approved By:

Closed By: White,Thomas F

4/20/2003 1 3 5 9 5 3

4/21/2003 10:48:08

4/21/2003 10:48:08 ~

Current Due Date: 06/20/2003 Initial Due Date: 06/20/2003

CA Type: CORRECTIVE ACTION

Plant Constraint: NONE

CA Description: As the Responsible Manager, validate the problem statement and determine corrective actions needed to resolve the adverse condition(s). Note: Category 'C' corrective actions may be closed to MR's without CRG approval provided the M R does not resolve a GL 91-18 deficiency. If a corrective action is closed out to a MR, the Responsible Manager is responsible to ensure the CR number is included in the MR references section. CA closure statements are expected to confirm this action has been completed.

Response: Work done under MR 03 1067 12 found that the set screws holding the linkage to the shaft of damper MON-109 were loose and the damper was not achieving a full open position. The set screws were tightened and the damper now strokes fully. This condition most likely limited the flow capability of the A train. An additional corrective action has been assigned to include provisions for locktiting or staking the set screws for future maintnenance on these dampers.

Subresponse :

Closure Comments:

CORRECTIVE ACTION I CR-PNP-2003-01413

Originated By: White,Thomas F Performed By: Mulcahy,Francis A

Subperformed By:

Approved By:

Closed By: White,Thomas F

4/21/2003 10:45:39

7/22/2003 15:01:40

7/24/2003 165956

Current Due Date: 07/25/2003 Initial Due Date: 07/25/2003

CA Type: CORRECTIVE ACTION

Plant Constraint: NONE

CA Description: Include provisions in a vendor manual or other document for locktiting or staking the linkage to shaft set screws on dampers MON-109/133 (and others of similar design).

Response: The procedure for adjusting the linkage for MO-N-109 and 113 is included in vendor manual V-110, "Honeywell Instrumentation And Actionator Motors". VMCR# 03.01 17 was issued on 7/22/03 to require staking or locktiting damper crank arm set screws when adjusting damper linkage.

Subresponse :

Closure Comments: Approved for closure.

' Entegy CA Number: 3

- - _ _ ~ In__ - I I I I ---_____ - - - I_I_____------ $ i Group I I Name

Assigned By: CA&A Staff

Assigned To: Eng Sys Mgmt Cook,William J

CORRECTIVE ACTION CR-PNP-2003-01413

Subassigned To : Eng Sys Mech Staff Mulcahy,Francis A

Originated By: McWilliams,Dorena C

Performed By: Cook,William J

8/6/2003 15:20:49

9/13/2003 12:06:04

Subperformed By: Mulcahy,Francis A 9/8/2003 14:05:07

Approved By:

Closed By: Cook,William J 9/13/2003 12:06:04

Current Due Date: 10/05/2003 Initial Due Date: 10/05/2003

CA Type: CORRECTIVE ACTION

Plant Constraint: NONE

CA Description: "As the Responsible Manager, validate the problem statement and determine corrective actions as needed to resolve the adverse condition(s). NOTE: Category 'C' corrective actions may be closed out to MR's without CRG approval provided the M R does not resolve a GL 91-18 deficiency. If a Corrective action is closed out to a MR, the responsible manager is responsible to ensure the CR number is included in the MR references section. CA closure statements are expected to confirm this action has been completed."

NOTE: THIS CONDITION REPORT DEALS WITH OPERABILITY EVALUATION 03.022.

Response: As the system engineer, take the lead on developing the plan to resolve this op eval. Tom McElhinney is the management sponsor and Steve Burke is support. Initial action plan development is approved and the actions assigned will be tracked by the MR process. CR can be closed.

IR photography will be used to determine if there is excessive leakage through the caulking between the concrete slabs at elevation 117 feet of the reactor building. This will be done with MRW3112422 scheduled to be performed om 9/24/03. If excessive leakage is found, plans will be made to repair caulking and regain some of the building DP margin lost over the past 10 years.

Subresponse :

A 3.M.1-34 Trouble Shooting Plan has been developed to troubleshoot VEX-210A flow condition. This plan includes an internal inspection of the BDD, outlet MO damper, fan assembly, filter compartments and inlet A 0 damper. Following the internal inspection, repairs will be made as necessary and the unit run to determine flow characteristics. This plan will be implemented under MR#03 109108 scheduled for 10/6/03.

Based on results of the troubleshooting and thermography, additional actions may be required to repair reactor building caulking and increase SBGT System flow.

Closure Comments: