ML20034F298

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Insp Repts 50-254/93-05 & 50-265/93-05 on 930209-11. Violations Noted.Major Areas Inspected:Matters Associated W/ HPCI Sys Being Inoperable Due to Check Valve Leakage within HPCI Sys
ML20034F298
Person / Time
Site: Quad Cities  Constellation icon.png
Issue date: 02/23/1993
From: Gardner R, Pegg W, Shembarger K
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20034F295 List:
References
50-254-93-05, 50-254-93-5, 50-265-93-05, 50-265-93-5, NUDOCS 9303030005
Download: ML20034F298 (4)


See also: IR 05000254/1993005

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U. S. NUCLEAR REGULATORY COMMISSION

REGION III

Reports No: 50-254/93005(DRS);50-265/93005(DRS)

Docket Nos: 50-254; 50-265

Licenses No:

DPR-29; DPR-30

Licensee: Commonwealth Edison Company

Opus West III

1400 Opus Place

Downers Grove, IL 60515

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Facility Name: Quad Cities Nuclear Plant

Inspection At: Quad Cities Nuclear Plant

Inspection Conducted:

February 9-11, 1993

Inspectors: NbMM4

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K. Shembarger

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W. Pegg

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Approved:

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R. Gardner, Chief,

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Plant Systems Section

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Insoection Summary

Insoection on February 9-11. 1993 (Recort No. 50-254/93005(DRS):

50-265/93005fDRS).

Areas Insoected:

Special inspection of matters associated with the Unit I and

Unit 2 HPCI systems being inoperable due to check valve leakage within the

HPCI systems.

Results: The inspectors determined that the HPCI systems were in a degraded

condition for several years as a result of the check valve leakage, which

could have prevented the systems from performing their function during a small

break LOCA event. Three violations were identified during the inspection

pertaining to inadequacies in 1) the inservice testing program, 2) test

control, and 3) a maintenance procedure. ' One weakness was identified-

regarding the lack of guidance in the emergency operating procedures to ensure

the HPCI pump discharge volume was maintained full during an event.

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DETAILS

1.0

Exit Meetina Attendees

Commonwealth Edison Company (CECO)

D. Bax, Station Manager

J. Burkhead, Quality Verification

D. Crannick, Maintenance Superintendent

H. Hentschel, Operations Manager

D. Kanakares, Regulatory Assurance, NRC Coordinator

J. Leider, Technical Services

A. Misek, Regulatory Assurance Supervisor

M. Nools, Quality Control Supervisor

C. Smith, Mechanical Maintenance

J. Wethington, Assistant Technical Staff Supervisor

U. S. Nuclear ReaulatorY Commission (NRC)

T. Taylor, Senior Resident Inspector

The NRC inspectors also contacted and interviewed other licensee personnel

during the inspection.

2.0

Inspection Results

2.1

Purpose of the Inspection

The purpose of the inspection was to review the matters associated with the

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HPCI system inoperability on February 5,1993, due to check valve leakage

within the HPCI systems.

2.2

Descriotion of Event

On February 5,1993, the licensee determined, after aligning 1) the HPCI

system suction to the torus and 2) the ECCS keep fill system to the HPCI

system, that the check valves located in the pump suction line were leaking.

This was identified as a result of the ECCS keep fill system's inability to

maintain adequate system pressure while aligned to-the HPCI system. The.

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licensee disassembled the check valves and identified that the hinge and disc

assembly for both valves were misaligned, allowing water to. flow from the HPCI

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system piping through the check valves to the torus. The licensee realigned

the hinge and disc assembly for each valve, performed a visual and pressure

check to ensure the valves seated adequately, and returned the HPCI systems to

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service.

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2.3

Sianificance of Event

Between at least January,1982 for Unit I and March,1990 for Unit 2, and

February,1993, the HPCI systems at the Quad Cities Nuclear Plant were in a

degraded condition as a result of misaligned hinge and disc assemblies in the

torus suction check valves. The valve leakage that occurred as a result of

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the hinge and disc assembly misalignment could have prevented the HPCI systems

from performing their intended function during a small break LOCA event.

Specifically, during a small break LOCA event, with HPCI saction aligned to

the torus and the HPCI pump cycling on and off as designed to maintain reactor

vessel level, multiple water hammer events could have affected the ability of

HPCI to perform its intended function.

2.4

Inspection Findinos

2.4.1

HPCI Check Valve Classification

The inspectors determined that the licensee had incorrectly classified the

HPCI system check valves (1-2301-39 and 2-2301-39) in the IST program (Section

XI of the ASME Code). Specifically, the licensee classified the valves as

category "C", with an open only safety function. The valves should have been

classified as category

"C", with an open and closed safety function, since the

check valves must close to prevent draining of the HPCI pump discharge piping

to the torus while the system is idle following a HPCI turbine trip.

Failure

to classify the valves correctly is considered a violation of 10 CFR 50.55a

(254/93005-01(DRS); 265/93005-Cl(DRS)).

2.4.2

HPCI Check Valve Testina

The inspectors determined that the licensee was not testing the HPCI system

check valves (1-2301-39 and 2-2301-39) as required by Subsection IWV (IWV-

3522) of Section XI of the ASME Code. Specifically, the Code requires, in

part, that valves that are normally open during plant operation, and whose

function is to prevent reversed flow, be tested. Since the valves are

normally open during HPCI system operation with suction from the torus, and

are required to close to prevent reversed flow with the system idle following

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a HPCI turbine trip, testing was required.

Failure to perform required

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testing is considered a violation of 10 CFR 50, Appendix B, Criterion XI

(254/93005-02(DRS); 265/93005-02(DRS)).

2.4.3

HPCI Check Valve Disassembly and Testina Procedure

The inspectors determined that the licensee's procedure to disassemble and

test the HPCI system torus suction check valves (QCMMS 2300-1, "HPCI Torus

'

Suction Check Valve () (2)-2301-39) Disassembly and Testing - Test Every Third

Refueling Outage, Rev. 0) did not provide guidance to ensure the valves were

seated properly.

Specifically, the acceptance criteria in the procedure was

limited to ensuring smooth operation of the valve from closed to open and back

to closed, and failed to include a method to ensure proper valve seating.

Failure to have procedures that include appropriate quantitative and

qualitative acceptance criteria is considered a violation of 10 CFR 50,-

Appendix B, Criterion V (254/93005-03(DRS); 265/93006-03(DRS)).

2.4.4

fmeroency Operatina Procedure Guidance Associated with Operation

of the HPCI System

The inspectors determined that guidance did not exist in the emergency

operating procedures (DGAs) to manually align the ECCS keep fill system.in the

event that 1) CCST level decreased below that required to maintain adequate

HPCI discharge volume (9.5 feet), or 2) HPCI suction automatically transferred

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from the CCST to the suppression pool. Although a control room alarm existed

to alert the operators of an automatic transfer in HPCI suction from the CCST

to the suppression pool, and the associated alarm response guidance directed

the operator to manually align the ECCS keep fi n system to the HPCI system,

the alignment may not have been performed in a timely manner or at all during

implementation of the emergency operating procedures.

(This is due to the

fact that control room annunciators are not safety related, and during a ; mall

break LOCA event,1) a large number of alarms would be annunciating in the

control room, making it difficult to identify a specific annunciating alarm,

and 2) emergency operating procedure implementation would take precedence over

responding to annunciatorr.)

Lack of guidance in the emergency operating

procedures (DGAs) to ensure the ECCS keep fill system is aligned when

required, to prevent water hammer events in the HPCI system, is considered a

weakness.

3.0

?;1t_ heetiw

The inspectors met with the licensee staff (denoted in Paragraph 1) at the

site on February 11, 1993, for an exit meeting to summarize the purpose,

scope, and findings of the inspection. A verbal summary of the inspection

findings was provided to the licensee at that time.

The inspectors discussed

the likely informational content of the inspection report with regard to

documents or processes reviewed by the inspectors during the inspection.

The

licensee did not identify any such documents or processes as proprietary.

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