ML20062H304

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Forwards Safety Insp Repts 50-461/90-05 & 50-461/90-12 on 900314-0514 & 0518-31 & Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $112,500
ML20062H304
Person / Time
Site: Clinton 
Issue date: 11/26/1990
From: Davis A
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Jamila Perry
ILLINOIS POWER CO.
Shared Package
ML20062H305 List:
References
EA-90-108, NUDOCS 9012040246
Download: ML20062H304 (6)


See also: IR 05000461/1990005

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November 26, 1990

Docket No. 50-461

License No. NPF-62

EA 90-108

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Illinois Power Company

ATTN:

J. S. Perry

Vice President

Clinton Power Station

Mall Code V-275

Post Office Box 678

Clinton, Illinois 61727

Gentlemen:

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SUBJECT:

NOTICE OF VIOLATION AND PROPOSED IMPOSITION OF CIVIL PENALTY - $112,500

(NRC INSPECTION REPORTS 50-461/90005(DRS) AND 50-461/90012(DRP))

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This refers to the special safety team inspections at the Clinton Power Station,

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conducted on March 14 - May 14, 1990, and on May 18 - May 31, 1990, of activities

authorized by NRC License No. NPF-62.

During these inspections, violations of

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NPC requirements were identified, and on June 5,1990, an enforcement conference

was held at the Clinton Power Station between you, and other members of.your

staff, and Dr. C. J. Pape'riello, and other members of the NRC staff.

Copies

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of the inspection. reports were mailed to you on May 31 and June 5, 1990, and

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the enforcement conference report was mailed to you on June 11, 1990. A final

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management meeting, to ensure that all technical issues had been resolved, was

held on November 6, 1990.

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The~ violations, which are described in the enclosed Notice of Violation and

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' Proposed Imposition of Civil- Penalties (Notice), involve three separate issues.

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Violation I concerns your failure to promptly identify and initiate appropriate

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corrective action for a potentially gignificant condition adverse to quality.

During performance testing of the shutdown servire water (SX) pump room heat

exchanger on January 24, 1990, Plant Technical Staff engineers found flow rates

significantly lower than expected. Though the flow data was forwarded to the

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' Nuclear Station Engineering Department (NSED) for trending purposes, the test

engineers failed to either initiate a Condition Report or inform the shift

supervisor.

Consequently, no action was taken to investigate the suspected

malfunction until the Supervisor of Plant festing reviewed the test data on

February.15, 1990.

As a result, your corrective action was not prompt, and

unduly extended operation with the SX system degraded. This violation

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demonstrates inadequate management attention to ensuring prompt, thorough

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evaluations of unexpected equipment indications.

CERTIFIED MAIL

RETURN RECEIPT REQUESTED

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lilinois Power Company

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November 26, 1990

Your subsequent investigation found that the shutdown service water and control

room heating, ventilation, and air conditioning (HVAC) chilled water flow rates

were less than the design value for numerous components.

This condition had

existed since plant startup in 1987 due to initial design inadequacies (Violation

11.A), that were compounded by inadequate pre-operational testing (Violation 11.B).

While these deficiencies occurred several years ago, they resulted in your having

to do extensive engineering calculations, modifications, and flow balancing in

order to restore the systems to their design configurations.

Violation 111 concerns the May 14, 1990 startup with diesel generators (DG) 1A

and IB inoperable due to the unavailability of shutdowr. service water.

The DG

heat exchanger SX outlet valvr were incorrectly positioned by operators during

system restoration work following maintenance.

Had the diesels been called upon

in a loss of offsite power event, they would have tripped within approximately

ten minutes of starting, but would not have been physically damaged, and could

have been restarted.

Had they been called upon during a loss of coolant accident,

coincident with a loss of offsite power, the diesels would have physically failed

within approximately thirty minutes of starting, unless the operators responded

to the diesel trouble alarm, correctly diagnosed the problem, and locally opened

the valves.

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The root cause of Violation 111 appears to be that the management and administrative

controls you had established to ensure proper valve position were not clearly or

consistently communicated to your operators.

To ensure repeatability of the SX

system flow balance to the DG heat exchangers, a new methodology for throttling

the SX outlet valves had been developed with the valve position specified on a

control tag. The first problem that developed was that the tags were not

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updated after initial placement to reflect the final valve throttle positions

once the system balance was completed.

Secondly, information on how the SX

valves were to be throttled was not communicated to all members of the operations

staff.

Both the operator who manipulated the valves and the assistant shift

supervisor with whom he conferred as to the correct valve positioning method,

did not know about the new methodology.

This is particularly disturbing because

the NRC Resident Inspectors had extensive discussions with plant management

concerning the need to ensure that all responsible personnel were informed

of these changes because of the need to establish a precise and repeatable valve

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position, to ensure accurate flow rates were established.

Consequently, you went from cold shutdown (Operational Condition 4) to startup

(Operational Condition 2), and remained there for over a day before discovering

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the closed valves when DG 1A tripped during a routine surveillance test. We

were, however, encouraged by the fact that, in this instance, you took prompt

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and extensive corrective actions.

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To emphasize the need for additional management attention to problem identifi-

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cation and resolution, and prompter, more effective corrective actions, I have

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been authorized af ter consultation with the Director, Office of Enforcement,

and the Deputy Executive Director for Nuclear Reactor Regulation, Regional

Operations, and Research to issue the enclosed Notice of Violation and Proposed

Imposition of Civil Penalties in the amount of $112,500 1 m the Violations set

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Illinois Power Company

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November 26, 1990

forth in the Notice.

The violations have each been classified at Severity

Im/ol 111 in accordance with the " General Statement of Policy and Procedure for

Enforcement Actions," 10 CFR Part 2, Appendix C (1990) (Enforcement Policy).

The base value of a civil penalty for a Severity Level III violation or problem

is $50,000.

The escalation and mitigation factors in the Enforcement Policy

were considered for e :h violation as described below.

Violation I is cunsidered a significant failure to identify and correct a degraded

condition, and is therefore categorized at Severity Level III. The base civil

penalty was escalated by 50% for NRC identification of your corrective action

system failures. However, once the system performance problem and corrective

action deficiencies were identified, you took extensive corrective actions that

included an in-depth evaluation of the SX system design problems as well as

providing wide training to station personnel regarding their responsibility

for prompt reporting of deficient conditions.

Consequently, a 50% mitigation

is applied for these actions.

No other adjustments were considered appropriate

and a $50,000 civil penalty is assessed for this violation.

The failure to ensure that the shutdown service water and control room HVAC

chilled water systems performance (1) met their Final Safety Analysis Report

(FSAR) design bases (Violation II.A) and (2) that SX system was adequately tested

(Violation II.B), has been categorized in the aggregate as a Severity Level III

problem under Supplements I and 11 of the Enforcement Policy. These violations

resulted in system performance being significantly degraded below the design

basis described in the FSAR since initial plant startup and extensive analysis

was necessary to provide assurance that the systems would serve their intended

function.

This is of significant concern because the plant was licensed, in

part, on the basis of the statements made in the FSAR. A civil penalty is

normally proposed for Severity Level 111 problems.

However, because you identi-

fied and reported the violations, initiated comprehensive corrective action that

included significant system testing and modification, and the violation would

not reasonably be expected to have been identified by routine surveillance testing

or quality assurance audit program and is not indicative of a current performance

concern, we have decided to exercise discretion under Section V.G.3 of the

Enforcement Policy and not propose a civil penalty for these violations.

Violation 111 is considered a significant operational violation and therefore

has been categorized at Severity Level Ill.

Though you identified this violation,

it was only mitigated by 25% because the DG failure that led to the discovery

of the mispositioned SX valves is considered self-identifying. A 50% mitigation

factor was applied for your corrective actions which included significant efforts

to communicate management expectations regarding operator performance, responsi-

bilities and authorities. A 100% escalation factor was applied for prior notice

because specific NRC concerns regarding the need to communicate the new method

of setting the SX throttle valves was discussed with senior plant management

prior to the event.

No further adjustment to the base civil penalty was con-

sidered appropriate and a $62,500 civil penalty is assessed for this vic!ation.

You are required to respond to this letter and should follow the instructions

specified.in the enclosed Notice when preparing your response.

In your response,

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l111nois Power Company

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November 26, 1990

you should document the specific actions token and any additional actions you

plan to prevent recurrence.

Particular emphasis should be placed on your actions

to assure that potential design and testing deficiencies similar to those in

Violations ll.A and B, are not present. After reviewing your response to this

Notice, including your proposed corrective actions and the results of future

inspections, the NRC will determine whether further NRC enforcement action is

necessary to ensure compliance with NRC regulatory requirements.

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In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of

this letter and its enclosure will be placed in the NRC Public Document Room.

The responses directed by this letter and the enclosed Notice are not subject

to the clearance procedures of the Office of Management and Budget as required

by the Paperwork Reduction Act of 1980, P. L.96-511.

Sincerely,

Ll%ta r

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A. Bert Davis

Regional Administrator

Enclosures:

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1.

Notice of Violation and Proposed

imposition of Civil Penalties

2.

Inspection Reports No. 50-461/90005(DRS)

and No. 50-461/90012(DRP)

See Attached Distribution

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(Received via FAX)

WTroskoski

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JSniezek

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11/15/90

11/18/90

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lilinois Power Company

-5-

November 26, 1990

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Distribution.

cc w/ enclosure:

J. Cook, Manager, Clinton Power Station

F. Spangenberg, Ill, Manager,

' Licensing and Safety

DCD/DCB (RIDS)

OC/LFDCB

Resident inspector, Rlli

J. Hickman, NRR, PM

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McCaffrey, Chief, Public

Utilities Division

.H. Taylor, Quality Assurance

Division, Sargent & Lundy

Engineers

Patricia O'Brien, Governor's

Office of. Consumer Services

S, Zabel, Esquire, Schiff, Hardin,

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& Waite

L. Larson, Project Manager,

General Electric Company

Chairman, DeWitt County Board

Illinois Department of

Nuclear Safety

Robert _ Newmann, Office of Public

Counsel, State of Illinois Center

Perry SRI

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lilinois Power Company

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November 26, 1990

DISTRIBUTION:

PDR

LPDR

SECY

CA -

J.Sniczek, DEDR

J.Lieberman, OE

J.Goldberg, 0GC

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T.Murley, NRR

J.Partlow, HRR

Enforcement Coordinators

R1, Ril,-RIV, RV

F.Ingram, GPA/PA

B. Hayes, 01

D. Williams OlG

E. Jordan, AE0D

. W.Troskoski OE

Day File

EA File

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PA0:R111

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