ML20198G985

Provides Specific Response to NRC 980824 Rai,By Referencing Applicable Sections from GL 97-01 Response

ML20198G985
Person / Time
Site:	Calvert Cliffs
Issue date:	12/22/1998
From:	Cruse C BALTIMORE GAS & ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-97-01, GL-97-1, NUDOCS 9812290211
Download: ML20198G985 (5)

Text

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CHARLES II. CRUSE Baltimore Gas and Electric Company Vice President Calven Cliffs Nuclear Power Plant Nuclear Energy 1650 Calven Clifts Parkway Lusby, Maryland 20657 410 495-4455 p .

December 22,1998 0

U. S. Nuclear Regulatory Commission Washington, DC 20555 ATTENTION: Document Control Desk

SUBJECT:

Calvert Cliffs Nuclear Power Plant

\ Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 Response to NRC Request for Additional Information Regarding Generic Letter 97-01, " Degradation of Control Rod Drive Mechanism Nonle and Other Vessel Closure Head Penetrations" By letter dated August 24,1993 (Reference a), you transmitted a Request for Additional Information (RAI) regarding our April 30,1997, and July 29,1997, responses (References b and c, respectively) to Generic Letter 97-01. You requested that we respond to the RAI within 90 days of the RAI transmittal date. By letter dated November 19, 1998, we requested an extension of the RAI response date from November 22,1998, to December 31,1998 (Reference d), to complete our review of the generic response prepared by the Electric Power Research Institute Materials Reliability Project Alloy 600 issue Task Group (ITG) and prepare a plant-specific response.

As we informed you in Reference (d), the generic response has been submitted to the NRC on December 11,1998 (Reference c). This letter provides our plant specific response to your August 24, 1998, RAI by referencing the applicable sections from the generic response.

NRC REQUESTED INFORMATION Designate which crack susceptibility model is being endorsedfor the assessment of CEDM [ control element drive mechanism] penetration no::les atyourplant.

BEtERESPDNSE l

Our response to this request is provided by the generic response to Question 1 in Enclosure 4 of Reference (e).

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<c 9812290211 981222 PDR ADOCK 05000317 p PDR _

Document Control Desk December 22,1998 Page 2 NRC REOUESTED INFORMATION Indicate how the susceptibility model being endorsed relates to the CEOG's [ Combustion Engineering Owners Group] integrated program for assessing the CEDM penetration no::les at ABB-CE [ Asea Brown Boveri, Inc.-Combustion Engineering, Inc.] designedplants, and whether or not the design of the susceptibility model is consister,: with the contents of Topical Report CE NPSD-1085.

BGE RESPONSE Our response to this request is provided by the generic response to Question 2 in Enclosure 4 of Reference (e).

NRC REOUESTED INFORMATION Ifthe ABB-CE PITMmodel is being endorsedfor the assessment of CEDMpenetration no::les at your plant, address items a. - e. that follow. If the Dominion Engineering susceptibility model is being endorsedfor the assessment ofCEDMpenetration no::les atyourplant, address itemsf - i. thatfollow.

BGE RESPONSE As discussed in response to Question 1 in Enclosure 4 of Reference (e), the Electrical Power Research Institute model, which is developed by Dominion Engineering, is being endorsed for the assessment 1 of CEDM penetration nozzles at our plant. Therefore, Items f. - i are addressed below.

1 NRC REOUESTED INFORMATION j f Provide a description ofhow the various productforms, material specifications, and heat treatments l used tofabricate each CEDMpenetration no::le at the CEOG member utilities are handled in the Dominion Engineering susceptibility model.

BGE RESPONSE Our response to this request is provided by the generic response to Question 3 in Enclosure 4 of l Reference (e). I NRC REOUESTED INFORMATION

g. Provide any additional information, if available, regarding how the model will be refined to allow the input ofplant-specific inspection data into the model's analysis methodology.

BGE RESPOSSE Our response to this request is provided by the generic response to Question 5 in Enclosure 4 of Reference (e).

NRC REOUESTED INFORMATION

h. Describe how the Dominion Engineering crack initiation and crack growth models for assessing postulatedflaws in vessel headpenetration no::les were bench-marked, andprovide a listing and discussion of the standards the models were bench-marked against.

Document Control Desk

' December 22,1998 -

Page 3 BGE RESPONSE Our re:ponse to this request is provided by the generic response to Question 4 in Enclosure 4 of Reference (e).

NRC REQUESTED INFORMATION

i. Provide the latest model susceptibility rankings of CEDMpenetration no:zles in CEOG member plants based on the results of the Dominion Engineering susceptibility model analyses of these CEDMandICI[incore instrumentation] no :les.

BGE RESPONSE Our response to this request is provided by the generic response to Question 6 in Enclosure 4 of Reference (e).

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Document Control Desk Dec:mber 22,1998 j Page 4 I

l Should you have further questions regarding this matter, we will be pleased to discuss them with you.

Very truly yours, i

STATE OF MARYLAND  :

TO WIT:

COUNTY OF CALVERT  :

I I, Charles H. Cruse, being duly sworn, state that I am Vice President, Nuclear Energy Division, l Baltimore Gas and Electric Company (BGE), and that I am duly authorized to execute and file this  !

response on behalf of BGE. To the best of my knowledge and belief, the statements contained in this  !

document are true and correct. To the extent that these statements are not based on my personal J knowledge, they are based upon information provided by other BGE employees and/or consultants. Such information has been reviewed in accordance with company practice and I believe it to be reliable. j

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Subscribed and sworn before me, a Notary Public in and for the State of Maryland and County of u

[2 o lv7 .this 83 day of 3<comded ,1998.

i WITNESS my Hand and Notarial Seal: < t[A_

Notary Public 1 l

l My Commission Expires: A tucviu / ,Q(7)'A I}ite 1 CHC/GT/bjd l

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j Docum:nt Control Desk I j Dectmber 22,1998  !

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REFERENCES:

, (a) Letter from Mr. A. W. Dromerick (NRC) to Mr. C. H. Cruse (BGE), dated August 24,1998, j Generic Letter 97-01, " Degradation of CRDM/CEDM Nozzle and Other Vessel Closure Head i

Penetrations" Responses for Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 and the Relationship of the Responses to Topical Report No. CE NPSD-1085

! (b) Letter from Mr. C. H. Cruse (BGE) to NRC Document Control Desk, dated April 30,1997, 1

30-Day Response to Generic Letter 97-01, " Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations" (c) Letter from Mr. C. H. Cruse (BGE) to NRC Document Control Desk, dated July 29,1997, i

120-Day Response to Generic Letter 97-01," Degradation of Control Rod Drive Mechanism

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Nozzle and Other Vessel Closure Head Penetrations" l l i l (d) Letter from Mr. C. H. Cruse (BGE) to NRC Document Control Desk, dated November 19, i 1998, Request for an Extension of Response Date to NRC Request for Additional Information

. Regarding Generic Letter 97-01, " Degradation of Control Rod Drive Mechanism Nozzle and Other Vessel Closure Head Penetrations" i 5

i j (e) Letter from Mr. D. J. Modeen (NEI) to Mr. G. L. Lainas (NRC), dated December 11,1998,

Response to NRC Request for Additional Information on Generic Letter 97-01 i j cc

R. S. Fleishman, Esquire Resident Inspector, NRC j J. E. Silberg, Esquire R.1. McLean, DNR d

S. S. Bajwa, NRC J. H. Walter, PSC A. W. Dromerick, NRC D. J. Modeen, NEl ,

} H. J. Miller, NRC  !

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