05000315/LER-1997-005, :on 970313,discovered That Gaskets in Fire Protection Water Spray Sys Had Not Been Properly Fabricated Prior to Installation.Caused by Personnel Error.Removed Old Gasket Matl & Installed New Gaskets

:on 970313,discovered That Gaskets in Fire Protection Water Spray Sys Had Not Been Properly Fabricated Prior to Installation.Caused by Personnel Error.Removed Old Gasket Matl & Installed New Gaskets

ML17333B106
Person / Time
Site:	Cook
Issue date:	10/23/1997
From:	Boesch J INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17333B105	List: 05000315/LER-1997-005, :on 970313,discovered That Gaskets in Fire Protection Water Spray Sys Had Not Been Properly Fabricated Prior to Installation.Caused by Personnel Error.Removed Old Gasket Matl & Installed New Gaskets 05000315/LER-1997-005-01, Forwards LER 97-005-01 Which Corrects Area Name & LER Number Incorrectly Identified on Pages 2 & 3 of LER
References
LER-97-005, LER-97-5, NUDOCS 9710300123
Download: ML17333B106 (5)

LER-1997-005, on 970313,discovered That Gaskets in Fire Protection Water Spray Sys Had Not Been Properly Fabricated Prior to Installation.Caused by Personnel Error.Removed Old Gasket Matl & Installed New Gaskets

Event date:
Report date:
Reporting criterion:	10 CFR 50.73(a)(2) 10 CFR 50.73(a)(2)(ii) 10 CFR 50.73(a)(2)(iii) 10 CFR 50.73(a)(2)(v), Loss of Safety Function 10 CFR 50.73(a)(2)(viii)(A) 10 CFR 50.73(a)(2)(viii)(B) 10 CFR 50.73(a)(2)(x) 10 CFR 50.73(a)(2)(i)(B), Prohibited by Technical Specifications
3151997005R00 - NRC Website

text

iiitC FORH 366 (5-92)

LXCENSEE EVENT REPORT

{LER)

PPROVED BY OMB NO. 3150.0104 EXP IRES 5/31/95 ESTIMATED BURDEN PER

RESPONSE

TO COMPLY WITH THI INFORMATION COLLECTION REQUEST: 50.0 HRS.

FORWAR COMMENTS REGARDING BURDEN ESTIMATE TO TH INFORMATION AND RECORDS MANAGEHENT BRANCH (MNB 7714),

U.S.

NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWOR REDUCTION PROJECT (3150-0104),

OFFICE 0

HANAGEMENT AND BUDGET WASHINGTON DC 20503.

FACILITY NAME (1)

Donald C. Cook Nuclear Plant - Unit 1 DOCKET NUMBER (2) 50-315 Page 1 of 3 TITLE (4)

Reactor Coolant Pump Fire Protection Inoperable For Extended Period Without Compensatory Actions Due to Im ro erl Fabricated Gasket inS a Header Line MONTH DAY YEAR YEAR

'EQUENTIAI.

NUHBER REVISION NUMBER MONTH DAY FACILITY NAHE YEAR DOCKET HUMBER 03 13 97 97

005 01 10 23 FAC I LI I'Y NAME DOCKET NUHBER OPERATING MODE (9)

POWER LEVEL (10)

(jqg)$;tt>$$~)cPPg4$g@k".6~rP 20.2201(b) 20.2203(a)(2)(I) 20.2203(a)(2)(iii) 20.2203(a)(2)(iv) 20.2203(a)(2)(v) 20.2203(a)(3)( I) 20.2203(6)(4) 5D.36(c)(2) 50.73(a)(2)(l) 50.73(a)(2)(ii) 50.73(a)(2)(iii) 50.73(a)(2)(v) 50.73(a)(2)(viii)(A) 50.73(a)(2)(viii)(B) 50.73(a)(2)(x) 73.71(b)

OTHER (Specify in Abstract below

,and in Text,NAME Mr. John Boesch, Maintenance Superintendent tELEPHONE NUMBER (include Area Code) 616 465-5901, )g634

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS

CAUSE

SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS YES X

NO EXPEC'IED SUBMISSION DATE 15 ABSTRACT (Limit to 1400 spaces, i.e., approximately 15 single-spaced typewritten lines) (16)

On March 5, 1997, with Unit 1 in cold shutdown, it was discovered that gaskets in the Fire Protection water spray system for the ¹13 Reactor Coolant Pump (RCP) had not been properly fabricated prior to installation during the 1995 refueling outage.

The improper configuration of the gaskets rendered the Fire Protection system for the ¹13 RCP inoperable from the time of installation, without compensatory actions being taken. This event is reportable under 10CFR50.73(a)(2)(i)(B), as operation prohibited by Technical Specifications.

Although the Fire Protection requirements were removed from the Technical Specifications in March of 1996, at the time the gaskets were installed the Fire Protection Technical Specifications were still in effect.

The root cause of this event is personnel error. The personnel involved did not properly incorporate into their actions the information contained in the Job Order Activityregarding fabrication of the gaskets, and did not perform an adequate part serviceabiiity inspection.

To restore the system to operable status, the old gasket material was removed and new gaskets were installed.

Pre-fabricated gaskets willbe stocked to prevent this from occurring in the future.

This condition has been evaluated, and it has been concluded that the defense-in-depth fire protection for this area adequately protected the fire safety of the plant. Therefore, this event did not constitute a significant hazard to the health and safety of the public.

97i0300i23 97i023 PDR ADQCK 050003i5 8

PDRU.

'CLEAR REGULATORY COMMISSIOH PROVED BY OMB HO. 3150-0104 EXPIRES 5/31/95 LICENSEE EVENT CONTZNUATZON ESTIMATED BURDEH PER

RESPONSE

TO COMPLY WITH TKI INFORMATION COLLECTION REQUEST: 50.0 HRS.

FORWAR COMMENTS REGARDING BURDEN ESTIMATE TO TH INFORMATIOH AND RECORDS MANAGEMEHT BRANCH (MHB 7714),

U.S.

NUCLEAR REGULATORY COMMISSION, WASHINGTON, DC 20555-0001, AND TO THE PAPERWOR REDUCTIOH PROJECT (3150-0104),

OFFICE 0

MANAGEMENT AND BUDGET, WASHINGTON, DC 20503.

Cook Nuclear Plant - Unit 1 50-315 YEAR SEQUENTIAI.

97

005 REVISION 01 2OF3 TEXT (if cere space is required.

use addit>ooal NRC Fore 366A's) (IT)

Condition Prior to Event

Unit 1 was in Mode 5, Cold Shutdown.

The Reactor Coolant Pump (RCP) motor Fire Protection is a dry pipe, manually actuated system.

Normally the systemhas 35 to 40 psi supervisory air in the system, and the spay heads are closed.

When the fusible link in the spray head is melted, air pressure in the piping is reduced, sounding alarms in both the Control Room and the Containment AuxiliarySubpanel.

Operators then manually open the isolation valve to admit water to the header around the RCP motor.

On March 5, 1997, while installing the blank side of a spectacle flange for 1-ZFP-391-3, RCP ItI3 deluge valve, it was discovered that the rubber gaskets installed during the 1995 refueling outage had not been properly fabricated.

The gaskets were to have been fabricated out of a sheet of red rubber by the installer, with the center of the gasket cut out to provide a flow path for the water spray. The gasket material, when discovered, had been installed as a solid sheet of red rubber. The center area, which should have been cut away during installation, was found to be tom. The tom gaskets are attributed to the pressure of the supervisory air.

C use of Even The root cause of this event is personnel error. The personnel involved did not properly incorporate into their actions the information contained in the Job Order Activityregarding fabrication of the gaskets.

In addition the personnel did not perform an adequate part serviceability inspection.

This event is being reported in accordance with 10CFR50.73(a)(2)(i)(B),

" operation prohibited by Technical Specifications.

Although Fire Protection were removed from the Technical Specifications in March of 1996, at the time that the improperly fabricated gasket was installed, the Technical Specifications were still in effect.

The configuration of the gasket material would have impacted only the flow characteristics of the RCP fire protection system.

The system was capable of being actuated, but the tom gaskets would have restricted the flow, resulting in some reduced capability. The associated system components - detection, Control Room notification, deluge valve operation and the RCP oil collection system - would have operated.

Based on this, it has been concluded that the defense-in-depth fire protection for this area adequately protected the fire safety of the plant. Therefore, this event did not constitute a significant hazard to the health and safety of the public.

This condition was discovered on March 5, 1997.

During the investigation of this condition it became apparent that the gaskets had been in place since the previous refueling outage, in the fall of 1995.

Based on this information, and the fact that the Fire Protection Technical Specifications were in effect from the time of installation until March of 1996, the condition was determined to be reportable on March 13, 1997.

AU UCLEAR REGULATORY COMMISSION LICENSEE EVENT CONTINUATION PROVED BY OMB NO. 3150.0104 EXPIRES 5/31/95 ESTIMATED BURDEN PER

RESPONSE

TO COMPLY WITH THI IHFORMATIOH COLLECTION REQUEST: 50.0 HRS.

FORHAR COMMENTS REGARDIHG BURDEN ESTIMATE TO TH INFORMATION AND RECORDS MANAGEMENT BRANCH (MHB 7714),

U.S.

NUCLEAR REGULATORY COMMISSION, UASHINGTON, OC 20555-0001, AND TO THE PAPERWOR REDUCTIOH PROJECT (3150-0104),

OFFICE 0

MAHAGEMENT AHD BUDGET MASHIHGTON, DC 20503.

YEAR SEQUENTIAL REVISION Cook Nuclear Plant - Unit 1 50415 97

005 01 3OF3 TEXT (if more space is required.

use additional tRC Form 3664's)

(17)

Corrective Actions

The old gasket material was removed and properly configured gaskets were installed.

Properly configured gaskets will be purchased or pre-fabricated and set up in stock, thus eliminating the need for the installers to fabricate the gasket.

Information on this event will be presented to personnel in the groups which install these gaskets to illustrate the need to followwritten instructions and to reinforce the need to pay attention to details.

The gaskets for the other Unit 1 RCP Fire Protection headers were also checked.

AIIwere found to have been properly fabricated and installed.

Failed Com onent Identificatio None

Previous Similar Events

None