ML20137V702

From kanterella
Jump to navigation Jump to search
Forwards Insp Rept 50-302/97-04 on 970127-0321.No Violations Noted
ML20137V702
Person / Time
Site: Crystal River Duke Energy icon.png
Issue date: 04/11/1997
From: Jaudon J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To: Richard Anderson
FLORIDA POWER CORP.
Shared Package
ML20137V706 List:
References
EA-97-094, EA-97-94, NUDOCS 9704170378
Download: ML20137V702 (4)


See also: IR 05000302/1997004

Text

-

~

.

,,

.

..

- - - -

~ .

.

-

..

-

.-

.. --

b

1,

. . ,

,

APRIL 11, 1997

.

t

W

4

EA 97-024-

'

- Florida Power Corporation

-

Crystal River Energy Complex

I

Mr. Roy A. Anderson (SA2C)

Sr. VP, Nuclear Operations

,

.

ATTN: Mgr.. Nuclear Licensing

i

15760 West Power Line Street

t

Crystal River. FL 34428-6708

SUBJECT:

NRC SPECIAL INSPECTION REPORT NO. 50-302/97-04

Dear Mr. Anderson:

,

1

!

This refers to the inspection conducted on January 27 through March 21. 1997.

!

at the Crystal River facility. The purpose of the inspection was to follow up

on failures to report outside design basis and other conditions to the NRC as

required. The enclosed report presents the results of this inspection.

.

Based on the results of this inspection, three apparent Violations were

identified and are being considered for escalated enforcement action in

accordance with the " General Statement of Policy and Procedure for NRC

"

Enforcement Actions" (Enforcement Policy), NUREG-1600.

One apparent Violation

involves two examples:

(1) failure to report to the NRC the outside design

basis condition, involving insufficient emergency feedwater pump net positive

.

!

suction head, that was identified in April 1996: and (2) failure to report to

.

the NRC in a timely manner the outside design basis condition, involving a

non-safety-related transfer switch installed in safety-related emergency

,

i

safeguards status indicating light circuitry, that was identified in December

1995. This apparent Violation is of- concern because example (1) involved a

condition that resulted in escalated enforcement in 1997 and your failure to

'

report the condition contributed to a lack of timely NRC awareness and review

'

of the condition. As a result, the NRC missed an opportunity to ensure that

appropriate corrective actions were taken to address an outside design basis

4

condition. This apparent Violation is also of concern because it is a repeat

J

of previous Violations 50-302/94-27-02, 50-302/94-27-03, and 50-302/96-06-06.

which involved failures to report outside design basis conditions to the NRC

"

4

'

as re uired by 10 CFR 50.72 and 50.73.

Another concern. related to example

l

(2) o this ap)arent Violation, was because it had an incorrect date for the

discovery of t1e nonconforming condition and the LER failed to address or

4

'

include corrective action for the untimely engineering review of the

.

nonconforming condition. The other apparent Violations ~ involved recent

//

'

problems with reporting conditions to the NRC: including failure to make an

/,

'

emergency phone report within the time requirements of 10 CFR 73.71 and

failure to hand carry a suspected reportable issue to the Shift Manager for a

reportability review, as required by the licensee's procedures.

i

.

9704170378 970411

I

i

y

PDR

ADOCK 05000302

$l%%$$,EE,E,II

G

pop

i

!

50/

_

_

-

.

__

j

2

<

-

1

.

,

, >

i

f

)

FPC

2

l

The circumstances surrounding these apparent Violations, the significance of

i

the issues, and the need for lasting and effective corrective action were

discussed with members of your staff at the inspection exit meetings on

i

January 31, February 27, and March 21, 1997.

As a result, it may not be

j

necessary to conduct a predecisional enforcement conference in order to enable

i

the NRC to make an enforcement decision. .However, a Notice of Violation is

i

not presently being issued for these inspection findings.

Before the NRC

i

makes its enforcement decision, we are providing you an opportunity to either

!

(1) respond to the apparent violations addressed in this inspection report

j

within 30 days of the date of this letter or (2) request a predecisional

enforcement conference.

Please contact Mr. Harold Christensen at

e

1

(404) 331-4700 within seven days of the date of this letter to notify the NRC

of your intended response.

j

i

Your response should be clearly marked as a " Response to Apparent Violations

in Inspection Report No. 50-302/97-04 and should include for each apparent

Violation:

(1) the reason for the apparent Violation, or, if contested, the

basis for disputing the apparent Violation. (2) the corrective steps that have

4

been taken and the results achieved, (3) the corrective steps that will be

taken to avoid further violations, and (4) the date when full compliance will

be achieved.

Your response should be submitted under oath or affirmation and

may reference or include previously docketed correspondence, if the

correspondence adequately addresses the required response.

If an adequate

response is not received within the time specified or an extension of time has

not been granted by the NRC. the'NRC will either proceed with its enforcement

decision or schedule a predecisional enforcement conference.

In addition, please be advised that the number and characterization of

apparent-Violations described in the enclosed inspection-report may change as

a. result of further NRC review.

You will be advised by separate

' correspondence of the results of our deliberations on this matter.

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

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

j

Sincerely,

ORIGINAL SIGNED BY

i

JOHNS JAUDON

Johns P. Jaudon. Director

Division of Reactor Safety

Docket No.

50-302

. License No. DPR-72

Enclosure:

Inspection Report 50-302/97-04

cc w/ encl: See page 3'

_

.

..

FPC

3

cc w/ encl:

John P. Cowan Vice President

Nuclear Production (SA2C)

F~1orida Power Corporation

Crystal River Energy Complex

15760 West Power Line Street

Crystal River, FL 34428-6708

B. J. Hickle Director

Nuclear Plant Operations (NA2C)

Florida Power Corporation

Crystal River Energy Complex

15760 West Power Line Street

Crystal River, FL 34428-6708

David F. Kunsemiller, Director (SA2A)

Nuclear Operations Site Support

Florida Power Corporation

Crystal River Energy Complex

15760 West Power Line Street

Crystal River, FL 34428-6708

R. Alexander.Glenn

Corporate Counsel

Florida Power Corporation

MAC - ASA

P. O. Box 14042

St. Petersburg, FL 33733-4042

Attorney General

Department of Legal Affairs

The Capitol

Tallahassee, FL 32304

Bill Passetti

Office of Radiation Control

De)artment of Health and

Rehabilitative Services

1317 Winewood Boulevard

Tallahassee, FL 32399-0700

Joe Myers. Director

Division of Emergency Preparedness

Department of Community Affairs

2740 Centerview Drive

Tallahassee, FL 32399-2100

cc w/ encl cont'd:

See page 4

_.=.

. .

.

.

1

,

FPC

4

,

cc w/ encl cont'd:

Chairman

.

Board of County Commissioners

'

Citrus County

110 N. Apopka Avenue

Inverness. FL 34450-4245

Robert B. Borsum

Framatome Technologies

1700 Rockville Pike. Suite 525

,

Rockville, MD 20852-1631

l

Distribution w/ encl:

J. Lieberman. OE

'

D. Nelson OE

B. Summers. OE

'

K. Landis, RII

L. Raghavat

NRR

B. R. Crowl . RII

G. Hopper. R;I

!

PUBLIC

NRC Resident Inspector

U.S. Nuclear Regulatory Commission

6745 N. Tallahassee Road

Crystal River. FL 34428

Orricr

pit

ptr

ptr

O

pit

pit

A

ptL /

'

SIGNATURE

,-

1

NAME

RSchin

PF Ion

gah1h1

CChr stensen

Klang15,[

,,

DATE

04 / 7

/ 97

04 / "I / 97

b 04_/ f / 97

04 / ) / 97

04

/ 97

04 /

/ 97

COPY?

@

NO

YES

[NO)

[ EM ' NO

(YE$)

NO

tES/

NO

[ DES)

NO

i

,

_

=

nFFICE

Pff

$1GNATURE

NAME

CEvans

y

DATE

04 / O S/ 97

04 /

/ 97

04 /

/ 97

04 /

/ 97

04 /

/ 97

04 /

/ 97

COPY 7

YES

NO

YES

NO

YES

NO

YES

NO

YES

NO

YES

NO

OFFILIAL RELORD COPY

UULUMthl NAMt: 6:CR9/04.rpC