ML20212J876

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Forwards RAI Re Util 990412 Request to Revise Duane Arnold Energy Ctr TS SR 3.6.1.3.7 to Allow Representative Sample of Reactor Instrumentation Line EFCV to Be Tested Every 24 Months,Instead of Testing Each EFCV Every 24 Months
ML20212J876
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 09/30/1999
From: Mozafari B
NRC (Affiliation Not Assigned)
To: Protsch E
IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
References
TAC-MA05421, NUDOCS 9910060018
Download: ML20212J876 (5)


Text

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September 30, 1999 Mr. Eliot Protsch President IES Utilities Inc.

200 First Street, SE P.O. Box 351 Cedar Rapids, IA 52406-0351

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON TECHNICAL SPECIFICATION CHANGE REQUEST REGARDING EXCESS FLOW CHECK VALVE SURVEILLANCE REQUIREMENTS AT DUANE ARNOLD ENERGY CENTER (TAC NO. MA05421)

Dear Mr. Protsch:

In a letter dated April 12,1999, IES Utilities Inc. submitted a request to revise Duane Arnold Energy Center (OAEC) Technical Specification (TS) Surveillance Requirement (SR) 3.6.1.3.7 to allow a representative sample of reactor instrumentation line excess flow control valves (EFCV) to be tested every 24 months, instead of testing each EFCV every 24 months.

>The NRC staff has reviewed your submittal regarding the EFCV surveillance requirement for DAEC, and has determined that additional information is necessary to complete our review.

Your timely response to the enclosed request for additional information (RAI) will assist us in meeting your set.edule. This RAI and the schedule have been discussed with Kenneth Putnam of your staff. If you have any questions regarding this issue, please contact me at your earliest convenience at 301-415-2020.

Sincerely, Originalsignedby:

Brenda L. Mozafari, Project Manager, Section 1 Project Directorate lll Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-331 DISTRIBUTION:

Docket File PUBLIC JHannon PD31r/f

Enclosure:

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Mr. Eliot Protsch President IES Utilities Inc.

200 First Street, SE l

P.O. Box 351 l

l Cedar Rapids, IA' 52406-0351

SUBJECT:

L REQUEST FOR ADDITIONAL INFORMATION ON TECHNICAL SPECIFICATION l

CHANGE REQUEST REGARDING EXCESS FLOW CHECK VALVE SURVEILLANCE REQUIREMENTS AT DUANE ARNOLD ENERGY CENTER (TAC NO. MA05421)

Dear Mr. Protsch:

- In a letter dated April 12,1999, IES Utilities Inc. submitted a request to revise Duane Amold Energy Center (DAEC) Technical Specification (TS) Surveillance Requirement (SR) 3.6.1.3.7 to l

allow a representative sample of reactor instrumentation line excess flow control valves (EFCV) to be tected every 24 months, instead of testing each EFCV every 24 months.

The NRC staff has reviewed your submittal regarding the EFCV surveillance requirement for DAEC, and has determined that additional information is necessary to complete our review.

Your timely response to the enclosed request for additional information' (RAI) will assist us in l

meeting your schedule. This RAI and the schedule have been discussed with Kenneth Putnam 3

of your staff. If you have any questions regarding this issue, please contact me at your earliest convenience at 301-415-2020.

Sincerely, Onginalsignedby:

Brenda L. Mozafari, Project Manager, Section 1 Project Directorate ill Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-331 DISTRIBUTION:

. Docket File PUBLIC JHannon PD31r/f

Enclosure:

As stated GGrant, Rlli SBlack JPulsipher i

GHubbard (SPLB)

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September 30, 1999 i

Mr. Eliot Protsch President IES Utilities Inc.

200 First Street, SE P.O. Box 351 Cedar Rapids, IA 52406-0351

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION ON TECHNICAL SPECIFICATION CHANGE REQUEST REGARDING EXCESS FLOW CHECK VALVE l

SURVEILLANCE REQUIREMENTS AT DUANE ARNOLD ENERGY CENTER f

(TAC NO. MA05421) j

Dear Mr. Protsch:

In a letter dated April 12,1999, IES Utilities Inc. submitted a request to revise Duane Amold Energy Center (DAEC) Technical Specification (TS) Surveillance Requirement (SR) 3.6.1.3.7 to

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allow a representative sample of reactor instrumentation line excess flow control valves (EFCV) to be tested every 24 months,instead of testing each EFCV every 24 months.

The NRC staff has reviewed your submittal regarding the EFCV surveillance requirement for DAEC, and has determined that additionalinformation is necessary to complete our review.

Your timely response to the enclosed request for additional information (RAl) will assist us in meeting your schedule. This RAI and the schedule have been discussed with Kenneth Putnam of your staff. If you have any questions regarding this issue, please contact me at your earliest convenience at 301-415-2020.

i Sincerel Brenda L. Mozafari, Project M nager, Section 1 "roject Directorate 111 Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-331

Enclosure:

As stated l

l cc w/ enc!: See next page

.. o i,4 REQUEST FOR ADDITIONAL INFORMATION REGARDING EXCESS FLOW CHECK VALVE SURVEILLANCE REQUIREMENTS FOR THE DUANE ARNOLD ENERGY CENTER DOCKET NO. 50-331 l

1.

Explain the discrepancy between page 11, Section 4.2, top paragraph that states "...a total of nine failures over 10,000 valve years of operation" and Table 4.1 on page 14 that Indicates 11 failures.

2.

Refer to page 12, Section'4.3, top paragraph. The single instrumentation line break frequency of 5.34E-6/ year assumed was based on WASH-1400 data. Explain why a more updated value was not used. Individual Plant Examination data indicate that such frequency could be higher.

EFCV unavailability used the lambda T over two formula. Provide the basis for j

assuming a constant failure rate for 10 years. Explain how the nature of " stickiness" might change over such a long period (10 years) with potentially new failure mechanisms becoming dorninant.

Describe the impact / change on the release frequency estimate if (1) a more updated instrumentation line break frequency and (2) a constant failure rate is not assumed.

3.

Verify if there are valves in the plant that are similar to EFCVs whose failure data may be available. If such data exist, provide the data as well as the impact of applying such i

data on the release frequency estimate.

In addition, ensure that you have considered in your analysis any information available on degradation mechanism (s) and root cause(s) of the failed EFCVs (or similar valves) observed at other plants. Similarly, provide assurance that this type of information (including failure rates) will be shared among the plants for future data as they become updated and available.

Provide performance criteria for EFCVs. Describe how a cause determination will be performed and determine what specific corrective action would be taken if EFCVs do not meet their performance criteria.

Enclosure

W',

,4 Mr. Eliot Protsch Duane Arnold Energy Center IES Utilities Inc.

cc:

Jack Newman, Esquire Al Gutterman, Esquire Morgan, Lewis, & Bockius 1800 M Street, NW.

Washington, DC _20036-5869 Chairman, Linn County Board of Supervisors Cedar Rapids,IA 52406 IES Utilities Inc.

ATTN: Gary Van Middlesworth Plant Superintendent, Nuclear 3277 DAEC Road Palo,IA 52324 John F. Franz, Jr.

Vice President, Nuclear Duane Arnold Energy Center 3277 DAEC Road Palo,IA 52324 Ken Peveler Manager of Regulatory Performance Duane Arnold Energy Center 3277 DAEC Road Palo,IA 52324 U.S. Nuclear Regulatory Commission Resident inspector's Office Rural Route #1 Palo,IA 52324 Regional Administrator, Rlli U.S. Nuclear Regulatory Commission 801 Warrenville Road Lisle, IL 60532-4531 Daniel McGhee Utilities Division Iowa Department of Commerce Lucas Office Building,5th floor Des Moines, IA _50319