ML20044G986

Requests Addl Info Re Response to GL 92-01,rev 1, Reactor Vessel Structural Integrity

ML20044G986
Person / Time
Site:	Duane Arnold
Issue date:	05/26/1993
From:	Pulsifer R Office of Nuclear Reactor Regulation
To:	Leslie Liu IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
References
GL-92-01, GL-92-1, TAC-M83460, NUDOCS 9306070144
Download: ML20044G986 (5)

Text

- - - - - - _ - _ _ _ - - _ _ _ - - _ _ - -

pC CIC 9

~ k UNITED STATES

[m

,j NUCLEAR REGULATORY COMMISSION

~^

s WASHINGTON, D.C. 20056 0001 gw

/

....+

May 26, 1993 i

Docket No. 50-331 Mr. Lee Liu Chairman of the Board and Chief Executive Officer Iowa Electric Light and Power Company P.O. Box 351 Cedar Rapids, Iowa 52406

SUBJECT:

DUANE ARNOLD ENERGY CENTER (DAEC) - REQUEST FOR ADDITIONAL INFORMATION REGARDING RESPONSE TO GENERIC LETTER (GL) 92-01, REVISION 1, " REACTOR VESSEL STRUCTURAL INTEGRITY" (TAC NO. M83460).

The subject GL was issued on March 6,1992,.to compile information necessary to confirm that licen:ees and permit holders satisfy the requirements-for ensuring reactor vessel integrity.

In the GL, the_ staff requested responses to three questions. These three questions requested that information be provided regarding:

1) Appendix H to 10 CFR Part 50, 2) Appendix G to 10 CFR Part 50, and 3) Commitments made in response to GL 88-11.

By letter dated July 6, 1992, DAEC responded to GL 92-01, Revisio'n 1, by providing the information requested in the Required Information portion of the GL. The staff has completed its initial review of your response and has determined that additional information is needed.

Enclosed is a request for additional information (RAI). We request that-the response to the RAI be provided within 60 days from receipt of this letter.

The information requested by this letter is within the scope of the overall burden estimated in GL 92-01, Revision 1, " Reactor Vessel Structur'al Integrity,10 CFR 50.54(f)." The estimated average number of burden hours is 200 person hours for each addressee's response. This estimate pertains only to the identified response-related matters and does not include the time 010025 NE@ MF @fBTEP P'GPy

~

9306070144 930526 l

)1 PDR ADOCK 05000331

\\

\\

P PDR

j b

Mr. Lee Liu May 26, 1993 i

required to implement actions required by the regulations. This action is.

covered by the Office of Management and Budget Clearance Number 3150-0011, which expires June 30, 1994.

Sincerely, i

fi Robert M. Pulsifer, Project Manager Project Director III-3 Division of Reactor Projects III/IV/V.

Office of Nuclear Reactor _ Regulation

Enclosure:

Request for Additional Information cc w/enclosuret See next page a

l

)

i a

4 i

i

,-o, y

._y,.. _,,,. )

J i

i t

May 26, 1993 Mr. Lee Liu

• i required to implement actions required by the regulations. This action is I

covered by the Office of Management and Budget Clearance Number 3150-0011, wnich expires June 30, 1994.

I Sincerely, Original-Signed By:

l Robert M. Pulsifer, Project Manager Project Dir*ctor III-3 Division of Reactor Projects III/IV/V Office of Nuclear Reactor Regulation

Enclosure:

Request for Additional Information

)

4 cc w/ enclosure:

l See next page j

l DISTRIBUTION:

Docket 4 File NRC & Local PDRs i

PDIII-3 Reading File JRoe JZwolinski JHannon RPulsifer BKorona DMcDonald, 14B2 -

MRushbrook OGC, 15B18 ACRS (10), P315 EGreenman, RIII

//

OFC JDLIJ-3/LA PDIII-3/ INT PDIII-3/PM PDII[,f/D NAME MRukhbNk BKoronN1h RPulsif((

JHannpn DATE R / l d'93 6/d93 5 /f&/93 hd93

(

0FFICIAL RECORD COPY DOCUMENT NAME: DUA83460.RAI 1

3 k

1 l

4 Mr. Lee Liu

- Iowa Electric Light and Power Company Duane Arnold Energy Center i

j cc:

Jack Newman, Esquire

)

. Kathleen H. Shea, Esquire Newman and Holtzinger 1615 L Street, N.W.

Washington, D.C.

20036 i

i Chairman, Linn County j

Board of Supervisors Cedar Rapids, Iowa 52406

\\

Iowa Electric Light and Power Company 1

ATTN:

David L. Wilson Plant Superintendent, Nuclear 3277 DAEC Road i

Palo, Iowa 52324 l

Mr. John F. Franz, Jr.

Vice President, Nuclear Duane Arnold Energy Center 3277 DAEC Road Palo, Iowa 52324 Mr. Keith Young Manager, Nuclear Licensing Duane Arnold Energy Center 3277 DAEC-Road Palo, Iowa 52324 U.S. Nuclear Regulatory Commission Resident Inspector's Office Rural Route #1 Palo, Iowa 52324 Regional Administrator, Region III U.S. Nuclear Regulatory Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 Mr. Stephen N. Brown Utilities Division Iowa Department of Commerce Lucas Office Building, 5th Floor Des Moines, Iowa 50319

,,.--n--,.

,+w,~,

e

-'s

~

i i

i l

i l

\\

l.=

ENCLOSURE RE0 VEST FOR ADDITIONAL INFORMATION CONCERNING GL 92-01. REVISION 1.

" REACTOR VESSEL STRUCTURAL INTEGRITY" 1

The staff needs the following information in order to complete its review of DAEC's response to GL 92-01, Revision 1, " Reactor Vessel Structural Integrity."

Ouestion 2a in GL 92-01 l

The response to GL 92-01 indicates that the initial upper-shelf energy (USE) for two of the four beltline plates and all beltline welds, except i

for the surveillance weld, are not known. A topical report, NED0-32205, titled "BWR Owners' Group Topical Report on Upper Shelf Energy Equivalent Margin Analysis" regarding beltline materials with low USE, was submitted by General Electric Company on April 30, 1993.

The licensee must either confirm that this topical report will be used as i

its licensing bases or provide its plant specific approach to demonstrate that all beltline materials that do not have measured USE will meet requirements of Appendix G, 10 CFR 50.

Question 2b in GL 92-01 The response indicates that data from the drop weight test and Charpy test for beltline materials is either absent or incomplete for initial

)

RT determination. An alternative method developed by General eo Electric (GE) was used in deriving the initial RT for these materials.

IntheGEmethod,theestablishmentoUothe slope for the transition zone of the Charpy curve is crucial in deriving the initial RT, from incomplete test data.

Provide all plate and weld Charpy test n

curves compiled by GE for establishing the 2*F per ft-lb slope for the transition zone of the Charpy curve.

All test data must be from materials equivalent to (i.e., same vendor, fabrication time frame, fabrication process, material specification, etc.) the beltli'ne materials of this reactor vessel.

i i