ML20058A081

Forwards Questions Re 900808 License Amend Request to Increase Reactor Power to 100% for Response

ML20058A081
Person / Time
Site:	Arkansas Nuclear
Issue date:	10/15/1990
From:	Alexion T Office of Nuclear Reactor Regulation
To:	Carns N ENTERGY OPERATIONS, INC.
References
TAC-74894, NUDOCS 9010250250
Download: ML20058A081 (6)

Text

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October 15, 1990 Docket No. 50-313 Mr. Neil S. Carns Vice President, Operations AN0 Entergy Operations, Inc.

Route 3 Box 137G Russellville, Arkansas 72801

SUBJECT:

LICENSE AK NDMENT REQUEST T0 INCREASE REACTOR POWER TO 100%

(TAC NO. 74894)

By letter dated August 8, 1990 Entergy Operations requested the subject license amendment for Arkansas Nuclear One, Unit 1 (ANO-1). The NRC staff is currently reviewing your application and has determined that additional information is required to complete our review. questions are from our Reactor Systems Branch, Enclosure 2 questions are from our Structural and Geosciences Branch, and inclosure 3 questions are from our Human Factors i

Assessment Branch.

L As discussed with Dale James, our staff is available to discuss these l

questions should further clarification be necessary. A prompt response to these questions is requested so that our staff can meet your requested l

completion date of December 1, 1990.

Sincerely, ORGINIAL SIGNED BY:

Thomas W. Alexion, Project Manager Project Directorate IV.1 Division of Reactor Projects - 111, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosures:

As stated

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s October 15, 1990 Docket No. 50-313 Mr. Neil S. Carns Vice President, Operations ANO Entergy Operations, Inc.

Route 3 Box 137G Russellville, Arkansas 72801

SUBJECT:

LICENSE AMENDMENT REQUEST T0 INCREASE REACTOR POWER TO 1001 (TAC N0. 74894)

By letter dated August 8, 1990, Entergy Operations requested the subject license amendment for Arkansas Nuclear One, Unit 1 (ANO-1). The NRC staff is currently reviewing your application and has determined that additional information is required to complete our review. Enclosure 1 questions are from our Reactor Systems Branch, Enclosure 2 questions are from our Structural and Geosciences Branch, and Enclosure 3 questions are from our Human Factors Assessment Branch.

n As discussed with Dale James, our staff is available to discuss these questions should further clarification be necessary. A prompt response to these questions is requested so that our staff can meet your requested completion date of December 1, 1990.

Sincerely, W p y y 's [*

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Thomas W. Alexion,. Project.anager Project Directorate IV-1 Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosures:

' As stated cc w/ enclosures:

.See next page l

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Entergy Operations, Inc.

Arkansas Nuclear One, Unit I cc:

- Mr. Early Ewing, General Manager Mr. Donald C. Hintz Technical Support and Assessment Executive Vice President Arkansas Nuclear One and Chief Operating Officer Route 3 Box 137G Entergy Operations, Inc.

Russellville, Arkansas 72801 P. O. Box 31995 i

Jackson, Mississippi 39286 Mr. Jerry Yelverton Mr. Geralo Huench Director Nuclear Operations Vice President Operations Support Arkansas Nuclear One Entergy Operations, Inc.

l Route 3. Box 137G P. O. Box 31995 Russellville, Arkansas 72801 Jackson, Mississippi 39286 l

Mr. Nicholas S. Reynolds Mr. Robert B. McGehet isquire Bishop Cook, Purcell

• Reynolds Wise, Carter, Child & s raway 1400 L Street, N.W.

P. O. Box 651 Washington, D.C.

20005-3502 Jackson, Mississippi 39205 J

Mr. Robert B. Borsum Mr. Tom W. Nickels Babcock & Wilcox Arkansas Nuclear One Nuclear Power Generation Divisir Route 3, Box 137G 1700 Rockville Pike, Suite 525 Russellville, Arkansas 72801 Rockville, Maryland 20852 Senior Resident Inspector Admiral Kinnaird R. McKee, USN (Ret)

U.S. Nuclear Regulatory Commission Post Office Box 41 1 Nuclear Plant Road Oxford, Maryland 21654 Russellville, Arkansas 72801 Regional Administrator, Region IV U.S. Nuclear Pegulatory Commission Office of Executi'fe Director for Operations 611 Ryan Plaza ijrive, Suite 1000 Arlington, Tex;s 76011

' Honorable Joe W. Ph'111ps County -Judge ',f Pope County Pope County f ourthouse Russeil'!!!!e, Arkansas 72801 Ms. Greta Dicus, Director Division of Environmental Health Protectic Arkansas Department of Health 4815 West Markam Street Little: Rock, Arkansas 72201

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1 ENCLOSURE 1 QUESTIONS FROM REACTOR SYSTEMS BRANCH

't 1.

Is cavitation possible in the flow controlling orifices? Could

'i such cavitation alter the expected flows during HPl?

2.

Have the valves for the flow control and flow balancing been tested for stability (of setting) during long-term operation?

3.

Can a break occur downstream from the flow restricting (regulating) orifices?

I 4

Will the instrumentation allow the operator to determine, under all circumstances, the maximum flow side so the operator can take the proper corrective action?

q S.

Has Refe,ence 1 in 86-1179795-01 been reviewed by the NRC?

e.

Table 9 (86-1179795-01) does not show pressure vessel water level.

Does any core uncovering take place?

i 7.

It is assumed that the proposed system modifications will meet some performance reouirements.

Will the planned test verify all of the assumed performance requirements?

There is no listing of Quantified recuirements to be verified by the tests.

l 8.

Document 86-1179795-01 is based on the results of References 1-5, however. th? assumptions, the methodology, the data-or generally the acceptability of these calculations is not discussed.

i 9.

On page 12 (86-1179795-01) the limiting break size is j

identified as 0.02 to 0.1 square feet.

On page 6 (89R-1006-

]

02) a-break size of 0.06 to 0.1 souare feet is identifieo.

Is j

there any significant difference in the two?

1

10. On page 7 (89R-1006-02) an extrapolation is mentioned based on References S and 6.

Are such extrapolations valid?

Have References S and 6 been reviewed by the NRC?

What are the methods, assumptions and data in these analyses?

11.

In 89R-1006-02.1there is a large number of ANO studies which are relied upon.-

However, there is no discussion on the methodolooy, the data or the assumptions of these analyses.

Please support their validity.

1

12. Page 8 (89R-1006-02) reads:

"In the reassessment of the maximum post LOCA water level, additional increases in the potential water level were caused by the increase in the BWST level and by the use of more conservative assumptions for the water held-up in the RCS".

The statement does not sound correct.

Please identify the " conservative assumptions".

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ENCLOSURE 2 OUESTIONS FROM STRUCTURAL-AND GEOSCIENCES BRANCH

1.

Provide-information on the borated water storage tank (BWST.)

= layout. materials of c on s t ru f.t i on, major attachments, and foundation structure includirg the anchor-bol t chairs, anchor-bolt embedment in concrete, supporting substructure media and response spectra (DE and ME' used for the analysis.

2.

A-review of the submitted calculations on seismic reanalysis

[

of the BWST'~ indicate tha'. by the present analysis method. the

{

. tank is in the category of. flexible tanks.- Provide your plans i

to Check the adequacy of the tank accounting for the

+

-flexibility of the tank.

'Some licensees have committed to check the ad~eouacy of such tanks during the resolution of US]

A-46. " Seismic Quali fication of Eouipmen t in Operating Plants".

using -the. procedures-developed by the Seismic Qualification Utility Group (SOUGL.

This option is available to you.

3.

A,corrosionfallowance of 1/16" as provided~ in the thickness-selection of the shell courses.

Provide inf orma tion on the present thicknesses of the "as is" tank.

Are there any areas of the tank where corrosion is ongoing?

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ENCLOSURE 3 3

OUESTIONS FROM HUMAN FACTORS' ASSESSMENT BRANCH-

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1.

Report No. 89R-1006-02, page 18 Reference 4 references ANO 1

Procedure 1202.01. Rev. 19.

Provide a copy of this procedure, f

2.

Report No. 89R-1006-02, page 18. discusses recommended changes j

to EOP guidance (! tem 3).

Provide a draft of changes to the EOPs.

3.

Document No. 86-1179795-01, page 16 Second paragraph. talks about an initial 111ow imbalance of 2.5%.

Explain where the 2.5% comes from.

.l>

4 Page 2 of the Cover letter, first paragraph. discusses providinQ the control room operator with specific flow rate information.

Identify the new flow rate information that will be available to the operator.

Specifically a.

The physical dimensions of the indication.

b. The location of the indication (where in the control room with. respect to applicable controls).

j

c. What units are used to provide the indication? Are these j

units the same as the units in the EOPs?

What is the rance of the indication. how fine is the range graduated, and is the graduation-appropriate for the operator?

S.

Discuss what' forms of training, including simulator training, j

wil l' be ' per f ormed to incorporate the-new flow indication q

m information.

Will modifications be made to the simulator 1to

'i incorporate the new' indication prior to the commencement'of j

training?

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