ML20149G852

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Discusses Special Insp Repts 50-327/97-05 & 50-328/97-05 on 970324-0522 & Forwards Notice of Violation
ML20149G852
Person / Time
Site: Sequoyah  
Issue date: 07/10/1997
From: Reyes L
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Kingsley O
TENNESSEE VALLEY AUTHORITY
Shared Package
ML20149G854 List:
References
50-327-97-05, 50-327-97-5, 50-328-97-05, 50-328-97-5, EA-97-232, NUDOCS 9707240098
Download: ML20149G852 (5)


See also: IR 05000327/1997005

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July 10,1997

EA 97 232.

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Tennessee Valley Authority

ATTN: Mr. Oliver D. Kingsley, Jr.

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President, TVA Nuclear and

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Chief Nuclear Officer

6A Lookout Place

1101 Market Street

Chattanooga, TN 37402 2801

SUBJECT:

NOTICE OF VIOLATION

(NRC SPECIAL INSPECTION REPORT NOS. 50 327/97 05 AND 50 328/97 05)

Dear Mr. Kingsley:

This refers to the special inspection conducted on March 24 through

May 22, 1997, at the Sequoyah facility. The purpose of the inspection was.to

review asmets of the Unit 1 reactor coolant system (RCS) inadvertent drain

down whic1 occurred on March 24, 1997. The results of the inspection were

sent to'you by letter dated May 27, 1997. An open, predecisional enforcement

conference was conducted in the Region II office on June 27, 1997, with you

and members of your staff, to discuss the apparent violations' the root

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causes, and corrective actions to preclude recurrence. A list of' conference

attendees-and copies of the Nuclear Regulatory Commission's (NRC) and

Tennessee Valley Authority's (TVA) presentation materials are enclosed.

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Based on the information developed during the insmction and the information

that was provided during the conference, the.NRC 1as determined that

violations of NRC requirements occurred. The violations are cited in the

enclosed Notice of Violation (Notice), and the circumstances surrounding them

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are described in detail in the subject inspection report.

The RCS. drain down event occurred during an evolution to reduce pressurizer

level to 25%, following plant ' shutdown. You stated that the evolution

included a rapid RCS depressurization which caused voids in the reference leg

for the cold calibrated pressurizer level instrument and erroneous indication

of pressurizer level in the control room. Operators relied on the erroneous

. indication and inadvertently drained the pressurizer and subsequently the RCS

to a. level just below the top of the reactor vessel head.

Two violations were identified as a result of the event. Violation A involved

two examples of the failure to identify and take adequate corrective actions

for a significant condition adverse to quality.

In the first example of

Violation A TVA failed to identify and correct deficiencies in the control of

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RCS.. inventory during a reduction of pressurizer level. The root cause of this

example of the violation was the failure of TVA management to provide the

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proper combination of operator training and procedural guidance necessary to

identify the discrepancy in the pressurizer level indication. As a result,

although the operators appeared to be attentive to their duties and were

monitoring the hot calibrated and cold calibrated pressurizer level

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instruments, they failed to identify a malfunction of the cold calibrated

pressurizer level instrument.

It is also of particular significance that

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although the operators questioned the conflicting indications including

receiving and acknowledging alarms in the control room indicating letdown

isolation and low pressurizer level, they failed to stop the evolution

promptly and determine if further actions were necessary to effectively

analyze the conflicting level indications. The operators continued the

pressurizer drain down until a reactor operator, assuming shift duties after a

shift change, noted the discrepancy between pressurizer level and a reactor

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vessel level indication and initiated corrective actions. A weakness was also

noted in implementation of corrective actions for a loss of RCS inventory

control in 1993. TVA had determined that procedural controls for RCS

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inventory control should be enhanced, based on a previous event review for a

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1993 Sequoyah Unit 1 inadvertent RCS drain down. These controls included

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measures to ensure (1) positive inventory control, (2) use of a pressurizer

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level correction curve which showed the relationship between the hot and cold

calibrated instruments, and (3) use of multiple independent channels to

confirm the accuracy of instruments relied on during the drain down.

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However, the corrective action for the 1993 event focused on

3recluding

inventory control events only at low pressurizer levels and t1e procedure for

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operatinn in normal pressurizer level bands was not revised.

In the second example of Violation A, TVA failed to identify that two previous

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backfills'of the pressurizer level instrument reference legs that occurred

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after rapid RCS depressurization evolutions were evidence of the pressurizer

level instrument's susceptibility to voiding during rapid RCS

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depressurization. As a result, corrective actions were not taken to ensure

that adequate indication of RCS inventory was available during reductions in

RCS inventory.

Violation B involved failures to log correctly and accurately the plant's

status as required by plant operating procedures.

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The NRC is concerned that, when faced with the discrepant indications, the

operators failed to take immediate corrective actions to determine actual RCS

inventory. The operators also failed to take precautionary steps, such as

consulting the pressurizer level correction curve which was available in the

control room, or implementing positive inventory controls prior to commencing

the RCS drain down evolution.

In addition, the NRC is concerned that previous

opportunities to identify the level instrument failure mode were lost when you

failed to evaluate the circumstances surrounding two previous cold calibrated

reference leg backfills due to voiding in the pressurizer level reference leg.

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TVA

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The March 1997 Unit 1 RCS drain down event is also of particular concern to

the NRC because of the similarity of this event to the 1993 Unit 1 RCS drain

down. Although, the actual safety consequences of both events were low, the

recurrence of this event, as a result of operator errors and failure to

provide adequate procedural or training guidance, represents a significant

regulatory concern.

In light of the potential consequences of the loss of

reactor coolant inventory, licensees should take aggressive action to ensure

that appropriate procedures and training are provided to ensure that RCS

inventory is effectively controlled, particularly during evolutions involving

planned reductions in RCS inventory.

Additionally, corrective action

effectiveness has been an ongoing concern at Sequoyah. Therefore, the

violations have been categorized in the aggregate in accordance with the

" General Statement of Policy and Procedures for NRC Enforcement Actions"

(Enforcement Policy). NUREG 1600, as a Severity Level III problem.

In accordance with the Enforcement Policy, a base civil penalty in the amount

of $55,000 is considered for a Severity Level III problem occurring after

November 12, 1996.

Because your facility has

enforcement actions within the last two years, peen the subject of escalated

the NRC considered whether

credit was warranted for Identification and Corrective Action in accordance

with the civil penalty assessment process described in Section VI.B.2 of the

Enforcement Policy.

NRC determined that credit was warranted for

Identification in that the violations were identified by your staff. At the

conference, your staff stated that corrective actions taken or initiated

included the following:

(1) reinforce management expectations of Operations

personnel: (2) revision of the general operating procedure to control backfill

of the cold calibration level channel reference leg, ensure use of multiple

level indications during drain down and ensure positive inventory controls:

(3) enhanced training and evaluation of crew performance: (4) self-assessment

of Operations including an independent assessment conducted by peers from

other operating plants. Based on the above, the NRC determined that the

corrective actions appeared to be comprehensive and that credit was warranted

for the factor of Corrective Action.

Therefore, to encourage prompt identification and comprehensive corrective

actions for violations, I have been authorized, after consultation with the

Director, Office of Enforcement, not to propose a civil penalty in this case.

However, significant or further repetitive violations in the future could

result in a civil penalty.

'Two Severity Level III problems and proposed civil penalties of $50,000 each

were issued on December 24,1996. (EA 96 414) for inadequate corrective actions

related to maintenance of reactor trip breakers and other equipment. A Severity

Level III violatien and proposed civil penalty of $50,000 was issued on November 19,

1996, (EA 95-269) related to fire protection program deficiencies. A Severity

Level II violation and proposed civil penalty of $80,000 were issued on February 20,

1996, (EA 95 252) related to employee discrimination in Department of Labor Case

Nos. 92 ERA 19 and 92 ERA 34.

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TVA

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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, you should document the specific actions taken and any additional

actions you plan to prevent recurrence of the violation. 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.

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.

Sincerely.

Original signed by

Bruce S. Mallett for

Luis A. Reyes,

Regional Administrator

Docket Nos. 50-327, 50 328

License Nos DPR 77, DPR 79

Enclosures:

1. Notice of Violation

2. NRC Presentation Materials

3. TVA Presentation Materials

4. List of Attendees

cc w/encls:

0. J. Zeringue, Senior Vice

President

Nuclear Operations

Tennessee Valley Authority

6A Lookout Place

1101 Market Street

Chattanooga, TN 37402-2801

Jack A. Bailey, Vice President

Engineering & Technical Services

Tennessee Valley Authority

6A Lookout Place

1101 Market Street

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Chattanooga, TN 37402 2801

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cc w/encls: (See page 5)

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TVA.

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cc w/encls cont'd:

M. Bajestani

Site Vice President

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Sequoyah Nuclear Plant

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Tennessee Valley Authority

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P. O. Box 2000

Soddy Daisy, TN 37379

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General Counsel

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Tennessee Valley Authority

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400 West Summit Hill Drive

Knoxville, TN 37907.

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Raul R. Baron, General Manager

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Nuclear Assurance and Licensing

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' Tennessee Valley Authority

4J Blue Ridge

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1101 Market Street

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Chattanooga, TN

37402 2801

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Pedro Salas, Manager

Licensing and Industry Affairs

Tennessee Valley Authority

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4J Blue Ridge'

1101 Market Street

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Chattanooga, TN 37402 2801

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Ralph H. Shell, Manager

Licensing and Industry Affairs

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Sequoyah Nuclear Plant

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P. O. Box 2000

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Soddy Daisy TN 37379

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J. T. Herron, Plant Manager

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Sequoyah Nuclear Plant

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Tennessee Valley Authority

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P._0. Box 2000

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Soddy Daisy, TN 37379

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Michael. H. Mobley, Director

Division of Radiological Health

3rd Floor, L and C Annex

401 Church Street

Nashville, TN 37243-1532

County Executive

Hamilton County Courthouse

Chattanooga, TN 37402