ML20203E005

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Forwards Insp Rept 50-298/97-201 on 971027-1107,1117-21 & 1201-04.No Violations Noted
ML20203E005
Person / Time
Site: Cooper Entergy icon.png
Issue date: 02/05/1998
From: Richards S
NRC (Affiliation Not Assigned)
To: Horn G
NEBRASKA PUBLIC POWER DISTRICT
Shared Package
ML20203E011 List:
References
50-298-97-201, NUDOCS 9802260231
Download: ML20203E005 (6)


See also: IR 05000298/1997201

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NUCLEAR REGULATORY COMMISSION

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February 5,1998

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Mr. G. R. Hom

Sr. Vice President of Energy Supply

Nebraska Public Power District

141415th Street

Columbus, NE 68601

SUBJECT:

COOPER NUCLEAR STATION - DESIGN INSPECTION

(NRC INSPECTION REPORT NO. 50-298/97-201)

Dear Mr. Hom:

'

A design inspection at the Cooper Nuclear Station (CNS) was performed by the Special

Inspection Section of the Office of Nuclear Reactor Regulation (NRR) during the period

October 6,1997, through December 4,1997, including on-site inspections during October 27-

November 7,1997, November 17-21,1997, and December 1-4,1997. The team selected for

- inspection the residual heat removal (RHR) system and the reactor equipment cooling (REC)

system. The purpose of the inspection was to evaluate the capability of the systems to perform

safety functions required by their design bases, tie adherence to the design and licensing bases,

and the consistency of the as-built configuration with the updated safety analysis report (USAR).

The results of this inspection are presented in the enclosed report. The team selected and

reviewed relevant portions of the USAR, technical specifications (TS), calculations, design

criteria documents, drawings, modification packages, surveillance procedures, and other plant

documents.

The team identified that the design change to the REC system for the installation of the filter

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demineralizer in 1991, the associated safety analysis, and the operating procedure did not

address the importance of maintaining water inventory in the closed REC system. The REC

system would not have been able to support its long-term cooling functions in the event of a

design basis accident, because the minimum available volume of water in the surge tank would

have been depleted within a day through the sampling valves that were left open apparently

since the modification was installed in 1991. Your staff isolated the sampling valves, notified the

NRC of the condition, and issued LER 97-014 on December 12,1997, which identified the cause

as a failure to understand the design basis functions of the system.

. Although many calculations reviewed by the team were satisfactory, the team noted that

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nonconservative assumptions and design inputs were used in the calculations for estimating the

RHR pump room temperature and for verifying the capability of the service water (SW) system to

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provide adequate back up cooling for safety-related equipment in the REC system. A night order

was issued to secure one of the RHR pumps if the fan coil unit in that room becomes

inoperable, and SW back-up cooling calculation was revised.

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Mr. G. R. Horn

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February 5,1998

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The 10 CFR 50.59 safety evaluation that was performed for the USAR revision to increase the

RHRSW booster pump room temperature limit to 131'F did not address the consequences of

operator actions required during post accident conditions to prevent exceeding this tempmature

limit.

The effects of failure of air pressure regulators in the instrument air system on air operated

valves had not been evaluated. At the exit meeting , we urged you to excedite this investigation

and promptly perform operability evaluations as required.

Previous NRC inspections had identified weaknesses in factoring instrument uncertainties into

test acceptance criteria and operating procedures. The team noted that the procedure for

moriitoring SW temperature and the surveillance test procedure for RHR pumps did not consider

applicable instrument uncertainties.

The team also identified other issues, such as: weaknesses in performance monitoring of RHR

and REC heat exchangers; an inadequate reportability review of a deficiency in the design of

power sources to RHR heat exchanger vent valves; not including in operating procedures vendor

recommended limitations on RHR pump operation at low flows; and not considering the potential

for pumping post-accident leakage from ECCS to the radwaste system. In addition, the team has

referred four issues identified in the report to the NRR staff for evaluation.

The team noted several discrepancies in the USAR, TS, and system design criteria documents,

The design criteria document (DCD-13) for the RHR system contained severalincorrect

statements that were inconsistent with the current system design.

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Some of the deficiencies discussed above challenged the capability of the systems to perform

their full des:gn bases functions. The contributory causes for these deficiencies appear to be a

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lack of understanding of the design bases of the systems, use of nonconservative assumptions

and design inputs in calculations, and not maintaining control over the configuration of the design

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bases reflected in various plant documents. Where appropriate, your staff took immediate

corrective or compensatory actions to ensure system operability. For other issues, you have

initiated problem identification reports to address required corrective actions. Taking into

consideration your immediate actions, the team concluded at the end of the inspection, that both

systems were capable of pe, forming their safety functions.

As with all NRC inspections, we expect that you will evaluate the applicability of the results of this

inspection and the specific findings to other systems and components throughout the plant.

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- DISTRIBUTION FOR COOPER NUCLEAR STATION - DESIGN INSPECTION REPORT:

. DATED: Februarv 5.1998 -

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Mr G. R. Hom -

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February 5,1998

Any enforcement action resulting from this inspection will be handled by the NRC Region IV

office via separate correspondence. Should you have any questions concoming the attached

inspection report, please contact the project manager, Mr. J. R. Has et (301) 415-1336, or the -

l inspection team leader, Mr. S. K. Malur at (301) 415 2963.

. . Sincerely, =

Original sigral by

Darald P. tbrkin FOR

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Sti art A. Richards, Chief _

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E <ents Assessment, Generic Communication,

snd Specialinspection Branch

Division of Reactor Pr9 gram Management

Office of Nuclear Reactor Regulation

Docket No.: 50-298

Enclosure : NRC Inspection Report No.: 50-298/97 201

cc: see next page

DOCUMENT NAME: G:\\skm\\ coverlet.1'

- See previous concurrence

To rec'ive a copy of this document, indicate in the box C= Copy w/o attachment / enclosure E= Copy with attachment / enclosure N = No copy .

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Mr. G. R. Horn

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Any enforcement action resulting from this inspection will be handled by the NRC Region IV

office via separate corre',pondence. Should you have any questions concerning the attached

- inspection report, please contact the project manager, Mr. J. R. Hall at (301) 415-1336, or the

inspection team leader, Mr. S. K. Malur at (301) 415-2963.

Sincerely,

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Stuart A. Richards, Chief

Evants Assessment, Generic Communication,

and Specialinspection Branch

Division of Reactor Program Management

Office of Nuclear Rer.ctor Regulation

Docket No.: 50-298

Enclosure : NRC Inspection Report No.: 50-298/97-201

cc: see next paoa

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Nebraska Public Power Company

Cooper Nuclear Station

cc:

Mr. John R. McPhail, General Counsel

Lincoln Electric System

Nebraska Public Power Di:trict

ATTN: Mr. Ron Stoddard

P. O. Box 499

11th & O Streets

Columbus, NE 68602-0499

Lincoln, NE 68508

Nebraska Public Power District

MidAmerican Energy

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ATTN: Mr. J. H. Swailes

ATTN: Dr. William D. Leech, Manager Nuclear

Vice Presider.t of Ne. lear Energy

907 Walnut Street

P. O. Box 98

P. O. Box 657

Brownville, NE 68321

Des Moines, IA 50303-0657

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Randolph Wood, Director

Nebraska Department of Environmental

Nebraska Public Power District

Control

ATTN: Mr. B. L. Houston, Nuclear

P. O. Box 98922

Licensing & Safety Manager

Lincoln, NE 68509-8922

P. O. Box 98

Brownville, NE 68321

Mr, Larry Bohlken, Chairman

Nemaha County Board of Commissioners

Mr. G. R. Hom

5

Nemaha County Courthouse

Sr. Vice President of Energy Supply

1824 N Street

Nebraska Public Power District

Aubum, NE 68305

141415th Street

Columbus, NE6P'ni

Senior Resident inspector

U.S. Nuclear Regulatory Commission

P. O. Box 218

Brownville, NE 68321

Regional Administrator, Region IV

- U.S. Nuclear Regulatory Commission

611 Ryan Plaza Drive, Suite 1000

Arlington, TX 76011

Ms. Cheryl Rogers, LLRW Program Manager

Division of Radiological Health

Nebraska Department of Health

301 Centennial Mall, South

P. O. Box 95007

Lincoln, NE 68509-5007

Mr. Ronald A. Kucera, Department Director

of Intergovemmental Cooperation

Department of Natural Resources

P.O. Box 176

Jefferson City, MO 65102

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