ML070780624

CR-PNP-2003-01413, Secondary Containment Leakrate Testing Was Aborted

ML070780624
Person / Time
Site:	Pilgrim
Issue date:	04/19/2003
From:	Entergy Nuclear Generation Co
To:	Office of Nuclear Reactor Regulation
References
CR-PNP-2003-01413
Download: ML070780624 (13)

Text

.I Entefgy 1 CONDITION REPORT 1 C R - P N P - ~ O O ~ - O 1~ ~ ~

Originator: Olson,Erjc W Originator Phone: 8744 Originator Group: Operations Mgmt Operability Required: Y Reportability Required: N Supervisor Name: Dietrich,Peter T Discovered Date: 04/19/2003 17:43 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=ST

Entergy I ADMIN CR-PNP-2003-01413 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 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-AIN 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 06/19/2003 15:44 Approved By: Mantenfe1,Martin B 06/19/2003 15:45 Operability

Description:

OE 03-021 with EE 03.027 Approval Comments:

none Attachments:

Operability Description Operability eval

Attachment Header Document Name:

CR-PNP-2003-01413Version - 002 I_-_Ix __ ~ -~ -- r_ . _. --I 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 Component ID # ContainmenVSBGT System # 50148 Train 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 perEE 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)., I . . or (5)is answered in the affirmative, then a 10CFR50.59 review may be (4).

, 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 0PERABILITY AN D I MMEDI AT E REPORTABILITY DETERMINAT10N (Continued) c Sheet 2 of 2 CAUTION A 10CFR50.59 review, in accordance with ENN-LI-lOO/ENN-LI-lOl, shall be com leted prior to implementing compensatory measures that involve a Procedure change(s) and or Temporary Alteration(s).

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

(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 (NE16.04) Due Date: Done 6/19/03 1000 (Problem Identification date + 1/2 LCO Time)

-+

cl. EQUIPMENT INOPERABLE LCO Entered: 0 No O Y e s

[m "N/R" IF OPERABLEJUDGEMENT]

LCO No. LCO Action Time Tech Spec Action Statement #:

Date Entered: Time Entered:

D. IMMEDIATE CORRECTIVE ACTIONS TAKEN:

(1) Procedure # (3) WRT/MR #

(2) Tech Spec # (4) Tagout #

A. Is immediate notification required? 0 Yes x No If yes, mark ap ropriate time requirement R

and complete t is section.

Name of person report made to:

H 1-HR RPT 8-HR RPT Daterrime:

1 4-HR RPT 24-HRRPT 10CFR50.72 Requirement:

Name of person making report: NRC Event #.:

B. Station Notifications (see applicable Station Procedure)

Person/Agency Time Limit (circle action taken Person ContactedlTime ("1\I/R" if not required) 0 Plant Ops Gen Mgr 24 hr, 4hr, l h r 0 NRC (via ENS) 24 hr, 4hr, l h r -

Reg & Ind Affairs Supt Operations Manager NRC Resident Inspector I -

6.19.

03/1 530 Other (specify) England/

0 Applicable section of 10CFR50.72 (specify)

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 ASSIGNMENTS CR-PNP-2003-01413 Version: 1 SignificanceCode: C - CORRECTION ClassificationCode: NON-SIGNIFICANT Owner Group: Eng Sys Mgmt Performed By: McWilliams,Dorena C 04/20/2003 02:04 Assignment

Description:

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

E n t m I CORRECTIVE ACTION 1 CR-PNP-2003-01413 CA Number: 1 I I- - 1 I i __I Group Name Assigned By: CRG Mgmt Assigned To: Eng Design Mgmt White,Thomas F Subassigned To :

Originated By: Landeche,David A 4/20/2003 13 5 9 5 3 Performed By: White,Thomas F 4/21/2003 10:48:08 Subperformed By:

Approved By:

Closed By: White,Thomas F 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 106712 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 4/21/2003 10:45:39 Performed By: Mulcahy,Francis A 7/22/2003 15:01:40 Subperformed By:

Approved By:

Closed By: White,Thomas F 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 CORRECTIVE ACTION CR-PNP-2003-01413 CA Number: 3 II

~ In__ I I I I I_I_____

i

$ Group Name Assigned By: CA&A Staff Assigned To: Eng Sys Mgmt Cook,William J Subassigned To : Eng Sys Mech Staff Mulcahy,Francis A Originated By: McWilliams,Dorena C 8/6/2003 15:20:49 Performed By: Cook,William J 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.

Subresponse :

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.

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#03109108 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: