ML20197B832

Forwards Design Insp Rept 50-313/97-201 on 970210-0314.Team Identified Issue Re Excessive EFW Flowrates to Single SG & Issues Associated W/Operability Evaluation Performed for Borated Water Storage Tank Flange Removal

ML20197B832
Person / Time
Site:	Arkansas Nuclear
Issue date:	07/24/1997
From:	Richards S NRC (Affiliation Not Assigned)
To:	Hutchinson C ENTERGY OPERATIONS, INC.
Shared Package
ML20197B838	List: IR 05000313/1997201 ML20197B832
References
50-313-97-201, NUDOCS 9803120192
Download: ML20197B832 (3)

See also: IR 05000313/1997201

Text

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[a  % UNITED STATES

g- ) NUCLEAR REGULATORY COMMISSION

g ~t WASHINGTON, D.C. 2055Mo01

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0,,,,, /- July 24, 1997

- Mr. C. Randy Hutchinson

Vice President, Operations ANO

Entergy Operat:ons, Inc.

1448 S.R. 333

Russellville. AR 72801

SUBJEC.T: ARKANSAS NUCLEAR ONE, UNIT 1, DESIGN INSPECTION

NRC INSPECTION REPORT NO. 50 313/97-201

Dear Mr. Hutchinson:

During the period from February 10,1997 through March 14,1997, the U.S. Nuclear

Regulatory Commission's (NRC) Office of Nuclear Reactor Regulation (NRR) performed a

design inspection of the Arkansas Nuclear One, Unit 1, Emergency Feedwater System (EFW)

and the Decay Heat (DH)/ Low Pressure injection System (LPI). The purpose of the

inspection was to evaluate the capability of the systems to perform safety functions

required by their design basis, adherence to the design and licensing basis, ano consistency

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of the as-built configurction with the Final Safety Analysis Report (FSAR).

[ The results of this inspection are contained in the attached inspection report. Overall, the

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team found the design of the two selected systems to be good, with adequate design

margins. Your_ staff's understanding of the design basis was good, ss was their inspection

preparation and ability to address team identified concerns. The implementanon of the

design was found to be adequate with some concerns noted.

The team identified an issue regarding excessive EFW flowrates to a single steam generator.

To reduce steam generator tube vibration crossflow velocity, Framatome Technologies, Inc.

(FTI),in a 1991 report to ANO 1, recommended a maximum flow of 1500 gpm assuming

both pumps are available and one steam generator is isolated. However, ANO-1 plant

,

operating procedures have no provisions to monitor and preclude exceeding thic limit. In.

May 1996, ANO-1 experienced a transient in wiich peak EFW flowrates of 1716 gpm were

identified for a brief time. An analysis performed by FTl, together with the results of your

staff's steam generator tube inspection performed during the last outage, suggest that there

is no immediate operability concern. The NRR staff will review and evaluate the plant

specific and potentially generic aspects of this issue.

The team identified issues associated with an operability evaluation performed for the

borated water storage tank flange removal which did not acconunt for the instsilation of a

foreign material exclusion cover and did not adequately address radioactive releases from

the tank.

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Other findings included an niadequate evaluation fcr non "O" steam traps which, if failed,  !

could significantly alter the EFW pump room environment; not periodically testing certain

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molded case circuit breakers; not establishing a basis for determining design requirements

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for the installation of instrument tubing and sensing lines that were found to be

' inadequately supported; inr.dequate control of some field routed conduits; a vortexing

calculation which did not account for instrument error, and discrepancies in the FSAR.

You have initiated appropriate measures to aodress the immediate concerns identified by

team. For the other issues, you have initiated appropriate reviews and corrective actions,

such as revision of design documents, changes to procedures, and further evaluations of the

identified issues. Notwithstanding the weaknesses described above, the team concluded

that the reviewed systems generally adhered to the design and licensing bases.

Pleas.e provide a senedule, within 60 days of the date of this letter, for completion of your

corrective actions for the iterns listed in Appendix A to the enclosed report, so that we can

plan for re inspection of_thsse items. As with all NRC inspections, we expect that you will

evale- e theand

other systems resuhs of this inspection, and where applicable, apply the specific findings to

components.

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in accordance with 10 CFR 2.790 of the Commission's regulations, a copy of this letter an

inspection report will be placed in the NRC Public Document Room. Any on enforcement a

resulting from this inspection will be issued by the NRC Region IV office via separate

please contact the inspection team leader, Mr. Robert L. Pettis, Jr .

Sincerely,

r_

L Stuart A. Richards, Chief

Specialinspection Branch

Division of inspection and Support Programs

Office of Nuclear Reactor Regulation

Enclosure: Inspection Report No. 50 313/97-201

cc: See next page

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,

Mr. C. Randy Hatchinson

Entergv Operations. Inc.

Arkansas Nuclear One. Unit 1

cc:

Executive Vice President &

- Chief Operating Officer Vice President, Operations

Entergy Operations, Inc. Entergy Operations, Inc.

P. O. Box 31995 P. O. Box 31995

Jackson, MS 39286 1995 Jackson, MS 39286-1995

Director. Division of Radiation Wise, Carter. Child & Caraway

P. O. Box 651

Control and Emergency Management

- Arkansas Department of Heal th Jackson, MS 39205

4815 West Markham Street, Slot 30

Little Rock, AR 72205 3867

!

Winston & Strawn

1400 L Street, N.W.

Washington, DC 20005 3502

Manager, Rockville Nuclear Licensing

Framatome Technologies

1700 Rockville Pike, Suite 525

Rockville, MD 20852

k-

Senior Resident hispector

U.S. Nuclear Regulatory Commission

P. O. Box 310

London, AR 72847

- Regional Administrator, Region IV

U.S. Nuclear Regulatory Commission

611 Ryan Plaza Drive, Suite 400

Arlington, TX 76011-8064

. County Judge of Pope County

Pope County Courthouse

Russellville, AR 72801

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