ML20212J781

Requests That Licensee Address Potential Aging Mgt Issue Re Effects of Void Swelling of Rv Internals by Making Plant Specific Commitment to Implement Focused age-related Degradation Insp for Evidence of Void Swelling in Future

ML20212J781
Person / Time
Site:	Calvert Cliffs
Issue date:	09/30/1999
From:	Dave Solorio NRC (Affiliation Not Assigned)
To:	Cruse C BALTIMORE GAS & ELECTRIC CO.
Shared Package
ML20212J785	List: ML20212J781 ML20212J786 ML20212J791
References
PROJECT-690 NUDOCS 9910050290
Download: ML20212J781 (6)

Text

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't NUCLEAR REGULATORY COMM:SSION WASHINGTON. D.C. 20665 0001 l

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t Mr. Charles H. Cruse, Vice President Nuclear Energy Division l Baltimore Gas and Electric Company 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702

SUBJECT:

REQUEST FOR INFORMATION REGARDING THE POTENTIAL AGING EFFECT OF VOID SWELLING

Dear Mr. Cruse:

During the NRC staff's review of Babcock & Wilcox Owners' Group (B&WOG) Generic License Renewal Program Topical Report entitled, " Demonstration of the Management of Aging Effects for the Reactor Vessel Intemais," BAW-2248, July 1997, the potential aging management issue regarding the effects of void swelling of reactor vesselinternals was identified in addition, the B&WOG aging management program for reactor vessel internals is involved with and closely l following the results of the issue task group formed to study emerging reactor pressure vessel material issues, which includes evaluating the potential for void swelling, under the pressurized water reactor material reliability project managed by the Energy Power Research Institute.

BGE did not identify void swelling as a plausible degradation mechanism in its license renewal application for Calvert Cliffs nor did the NRC staff identify this potential aging effect in its review of the Calvert Cliff application, which was the first application for license renewal reviewed by the staff. Subsequently, void swelling was identified as an applicable aging effect for reactor vessel internals during the review of the B&W topical report and the B&WOG vessel intemals program.

The staff acknowledges that it would have been preferable if this potential aging effect had been identified earlier dureg the preparation of NRC's review of the Calvert Cliffs application.

Nonetheless, recognizing that this is a plausible aging effect, NRC staff has concluded that it it appropriate for BGE to address this issue on a plant specific basis for Calvert Cliffs.

Also, in a recent letter from the NRC Advisory Committee on Reactor Safeguards (ACRS) (dated September 13,1999) related to the license renewal of Oenoee Nuclear Station, the ACRS recommended that a focused inspection program, as suggested by the staff, was a prudent approach for this aging management issue even as the staff and industry conduct additional research and gain experience to determine the significance of void swelling as a potential mode of degradation for pressurized water reactor intemals.

One acceptable way for Baltimore Gas and Electric Company (BGE) to address this issue for Calvert Cliffs is to make a plant-specific commitment to implement a focused age-related

, degradation inspection for evidence of void swelling in the future, to support the following safety evaluation conclusion:

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Charles H. Cruse September 30, 1999 I

l Industry programs, including the Reactor Pressure VesselIntemals issue Task Group l (ITG) of the pressurized water reactor (PWR) Materials Reliability Project (MRP), have l proposed to address void swelling as an aging effect applicable to reactor vessel

{ intemals. These efforts propose evaluation of available data on void sweHing as well as examination of removed PWR component items for evidence of void swelling, with an ultimate goal of assessing the significance of void sweHing for the license renewal period. As an example, the B&W Owners Group willutilize data andinformation from these industry programs to perform design-specific analyses, which should ultimately

determine appropriate actions forlicensees to ensure that reactor vesselintemals continue to perform their intended functions.

For the time being, assuming void swelling is a significant issue in the renewal term, l renewal applicants should address aging management of void sweHing within their applications. An adequate aging management program (AMP) wouldinclude participation in industry program (s) to address the significance of void swelling (either individually or through an owners or industry group), a commitment to develop a sufficient inspection program (including the basis, rnethods, locations to be examined, timing, frequency and acceptance criteria) for management of the issue based upon the l results of the industry programs, and a commitment to implement the inspection program prior to the end of the current license period.

Should industry programs determine that void sweHing is not a significant issue in the renewal term, then licensee:: would not need to develop norimplement any additional inspections beyond the current ASME Code Section XI VT-3 visualinspection of core support structures (Examination Category B-N-3 of Table IWB-2500-1).

The staff would be receptive to alternate commitments BGE may want to propose to resolve this aging effect, because we recognize that further efforts are needed to develop an optimized i

! approach to inspection. The need for this action was decided by the responsible division l managers in the NRC's Office of Nuclear Reactor Regulation. Therefore, it may be appropriate l to hold a management meeting to discuss your views on this issue to facilitate your response to I this letter.

Sincerely, MdMOF

! David L. Solorio, Project Manager License Renewal and Standardization B anch l Division of Reactor Program Management l l Office of Nuclear Reactor Regulation l Docket Nos. 50-317 and 50-318 1l cc: . See next page l DISTRIBUTION See next page (W #1y d

• See previous concurrence DOCUMENT NAME:G:\RLSB\SOLORIO\Ltr BGE Regarding Void Swelling.w3d OFFICE LA PM:RLSBh PD:RLSB _ , D:DE NAME EHylton DLSojoriM CIGrimesM JRStrosnider*

DATE 09/23/99* l 09h9 09/24/99 09/24/99 l

OFFKIIAL RECORD COPY a

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lk ' Charles H. Cruse I Industry programs, including the Reactor Pressure Vessel Intemals Issye Task Group (ITG) of the pressurized water reactor (PWR) Materials Reliability Pr} ject (MRP), have

!. proposed to address void swelling as an aging effect applicable to actor vessel l internals. These efforts propose evaluation of available data on id swelling as wellas 1

examination of removed PWR component items for evidence void swelling, with an ultimate goal of assessing the significance of void swelling licensa renewalperiod.

As an example, the B&W Owners Group will utilize data a information from these

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industry programs to perform design-specific analyses, ich should ultimatelydetermine appropriate actions forlicensees to ensure that reactor sselintemals continue to perform theirintended functions.

For the time being, assuming void swelling is a sjQnificant issue in the renewal term, l renewal applicants should address aging management of void swelling within their applications. An adequate aging managemeyt program (AMP) wouldinclude participation in industry program (s) to address the significance of void swelling (either individually or through an owners orindustry group), a commitment to develop a sufficient inspection program (including the basis,pethods, locations to be examined, timing, frequency and acceptance criteria) fortnanagement of the issue based upon the results of the industryprograms, and a com ilment to implement the inspection program prior to the end of the currentlicense peri Shouldindustryprograms dete ine that void swelling is not a significant issue in the renewal term, then licensees w uld not need to develop norimplement any additional inspections beyondthe curre ASME Code Section XI VT-3 visualinspection of core support structures (Examina on Category B-N-3 of Table IWB-2500-1).

The staff would be receptive to al rnate commitments BGE may want to propose to resolve this aging effect, because we recog ze that further efforts are needed to develop an optimum focused inspections. The nee or this action was decided by the responsible division managers in the NRC's Office of Nuclea eactor Regulation. Therefore, it may be appropriate to hold a management meeting to disc ss your views on this issue to facilitate your response to this letter.

Sincerely, j l

i I

David L. Solorio, Project Manager License Renewal and Standardization Branch  ;

! Division of Reactor Program Management Office of Nuclear Reactor Regulation  ;

Docket Nos. 50-31 and 50-318  ;

p cc: See next page' i DISTRIBUTION: See next page

• See previous concurrence DOCUMENT NAME:GARLSB\SOLORIO\Ltr to BGE Regarding VM15 welling wpd OFFICE LA PM:RLSB PD:RLSB D:DE Q NAME EHylton DLSolor(ch ClGrimesh JRStrahider DATE 09/23/99* 09 0/99 09/2,M9 098$/99 OFFICIAL RECORD COPY e

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l Charles H. Cruse  !

Industry programs, including the RPV Intemals Issue Task Group (ITG) of the PWR

! Materials Reliability Project (MRP), have proposed to address void swelling as an aging l effect applicable to reactor vesselintemals. These efforts propose evaluation of \

a alfable data on void swelling as well as examination of removed PWR component ite s for evidence of void swelling, with an ultimate goal of assessing the significance of voi welling for the license renewalperiod. As an example, the B&W Owners Group will l utiliz data andinformation from these industry programs to perform design-specific analys s, which should ultimately determine appropriate actions forlicensees to ensure that rea or vesselintemals continue to perform theirintended functions.

Forthe ti being, assumit,g void swelling is a significant issue in the renewal term, renewal ap ' cants should address aging management of void swelling within their applications. n adequate aging management program (AMP) would include participation in ' dustryprogram(s) to address the significance of void swelling (either individually or th ugh an owners orindustry group), a commitment to develop a sufficient inspection progra (including the basis, methods, locations to be examined, timing, frequency and ac tance criteria) for management of the issue based upon the results of the industry prog s, and a commitment to implement the inspection program pn'or to the end of the* current ense period.

Shouldindustryprograms termine that void swelling is not a significant issue in the renewalterm, then licensee ould not need to develop norimplement any additional inspections beyond the curren SME Code Section XI VT-3 visualinspection of core support structures (Examination tegory B-N-3 of Table IWB-2500-1). 1 i

l The staff would be receptive to alternate com itments BGE may want to propose to resolve this l aging effect, because we recognize that further orts are needed to develop an optimum i l focused inspections. The need for this action wa decided by the responsible division managers I l in the NRC's Office of Nuclear Reactor Regulation. herefore, it may be appropriate to hold a management meeting to discuss your views on this is e to facilitate your response to this letter.

i

! Sincerely, '

l i

David L. Solorio, Project nager License Renewal and Stand ization Branch Division of Reactor Program M gement Office of Nuclear Reactor Regulatibq j Docket Nos. 50-317 and 50-318 i cc: See next page DISTRIBUTION: See next page l DOCUMENT NAME:G:\RLSB\SOLORIO\Ltr to BGE Regarding Void Sweihng wpd OFFICE LA f) PM:RLS8% PD:RLSB D:DE NAME Mon DLSolgrj M CIGrimes JRStrosnida DATE 09M/99 09/439 09/ /99 09/ /99 OFFICIAL RECORD COPY

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( . Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant

! cc: Unit Nos.1 and 2 1

President Mr. Joseph H. Walter, Chief Engineer l l Calvert County Board of Public Service Commission of I

Commissioners Maryland  ;

l 175 Main Street Engineering Division Prince Frederick, MD 20678 {

6 St. Paul Centre Baltimore, MD 21202-6806 James P. Bennett, Esquire Counsel Kristen A. Burger, Esquire Baltimore Gas and Electric Company Maryland People's Counsel P.O. Box 1475 6 St. Paul Centre Baltimore, MD 21203 Suite 2102 Baltimore, MD 21202-1631 Jay E. Silberg, Esquire Shaw, Pittman, Potts, and Trowbridge Patricia T. Birnie, Esquire 2300 N Street, NW Co-Director Washington, DC 20037 '

Maryland Safe Energy Coalition P.O. Box 33111 Mr. Bruce S. Montgomery, Director Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Loren F. Donatelt 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby, MD 20657-4702 5700 Brainerd Road Chattanooga, TN 37411-4017 Resident inspector U.S. Nuclear Regulatory Commission Mr. David Lewis P.O. Box 287 Shaw, Pittman, Potts, and Trowbridge St. Leonard, MD 20685 l 2300 N Street, NW Washington, DC 20037 Mr. Richard I. McLean i Nuclear Programs Douglas J. Walters Power Plant Research Program Nuclear Energy Institute Maryland Dept. of Natural Resources l 1776 l Street, N.W. l Tawes State Office Building, B3 Suite 400 Annapolis, MD 21401 Washington, DC 20006-3708 DJW@NEl.ORG Regional Administrator, Region i U.S. Nuclear Regulatory Commission Cari Yoder 475 Allendale Road Baltimore Gas and Electric Company King of Prussia, PA 19406 Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Mr. Charles H. Cruse, Vice President NEF 1st Floor Nuclear Energy Division Lusby, Maryland 20657 Baltimore Gas and Electric Company 1650 Calvert Cliffs Parkway National Whistlebicwer Center Lusby, MD 20657-47027 '

3233 P Street, N.W.

Washington, DC 20007

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