ML20135E172

Summary of 970109 Meeting W/Bge in Rockville,Md to Discuss Results of 90 Day Review Effort Assigned at Last Mgt Meeting on 960911 & Future Review Activities.Attendee List & Meeting Handouts Encl

ML20135E172
Person / Time
Site:	Calvert Cliffs
Issue date:	03/04/1997
From:	Scott Flanders NRC (Affiliation Not Assigned)
To:	NRC (Affiliation Not Assigned)
References
NUDOCS 9703060322
Download: ML20135E172 (55)

Text

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'. g g NUCLEAR REGULATORY COMMISSION l o WASHINGTON, D.C. 2066M001 '

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/g March 4, 1997 ORGANIZATION: Baltimore Gas and Electric  ;

SUMMARY

OF MEETING WITH BALTIMORE GAS AND ELECTRIC COMPANY (BGE) ON BGE LICENSE RENEWAL ACTIVITIES On January 9, 1997, the Nuclear Regulatory Commission (NRC) management met with BGE management in Rockville, Maryland, to (1) discuss the results of the 90 day review effort assigned at the last management meeting held on September 11, 1996, and (2) discuss future review activities. A list of meeting attendees is provided in Attachment 1. Attachment 2 is a copy of the materials distributed during the meeting.

At the previous management meeting, NRC management proposed a 90 day effort to exercise the template in the areas of intended function, operating experience, and corrective actions. This assignment was given because the previous 90 day effort had yielded only agreements in principle as to how key issues related  ;

to these areas would be implemented. In addition, NRC management proposed in a letter dated September 23, 1996, to begin technical discussions on BGE's license renewal program for cables.

90-Day Template Exercise i To exercise the template in the areas of intended function, operating experience, and corrective actions, BGE provided sample revisions of three of 1996. The NRC staff reviewed the five technical the sample revisionsreports submitted and conducted siteon May 22, to evaluate visits BGE's ,

implementation of the template. During the 90 day effort, several public meetings were held to discuss the ongoing review of the sample revisions. As a result of these meetings, two major issues associated with BGE's l implementation of the template were identified and discussed. These issues are (1) the need for the technical reports to include specific informatiun to demonstrate that all current licensing basis (CLB) design loading conditions were considered in developing the acceptance criteria / alert value(s) of an i aging management program, and (2) the level of detail and content of operating 1 experience / corrective actions that should be included in the technical /

reports. The BGE and the NRC January 9, 1997, meeting discussion primarily focused on these two issues. p Ol WC RE CEMS COM

'The staff r.lso used the site visits to assist in the ongoing development  ;

of an NRC inspection /on-site review plan.

9703060322 DR 9703o4 ADOCK 05000317 PDR

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Intended functions-design loading conditions l During the meeting, BGE stated that for some aging management programs that  !

utilize pre-analyzed and quantitative specific alert / acceptance criteria,  ;

summary design basis information may be needed to support the staff's j determination as to the adequacy of the program's alert / acceptance criteria.

BGE established criteria to determine when it believes summary design basis information is needed. BGE stated that it will not provide component-by-component design loading or basis information for any aging management program l that meets the following criteria: 1 (1) The program manages the aging effect (2) The program is regulatory based (3) The program is under NRC regulatory oversight (inspected and/or docketed), and (4) The program uses alert / acceptance criteria that will not be changed l solely for the renewal period.

BGE also stated that for an aging management program that does not meet the i criteria listed above, then specific design basis information (summary format) i would be'provided.  ;

The NRC staff stated that it never intended for specific component-by-component loading conditions to be submitted. However, the staff did state  ;

that BGE must provide or reference some basis / justification for any aging ,

management program acceptance criteria / alert value that is not taken directly from the design basis information in the final safety analysis report (FSAR).

In explaining the bases for this position, the staff made two points: (1) regardless of whether the program is regulatory based, the rule requires a demonstration that the effects of aging on long-lived passive components will be adequately managed, and (2) a key part of that demonstration is that timely corrective actions are taken to maintain the functionality of the component.

In most cases, the program acceptance criteria / alert value is the trigger for corrective actions. For that reason, the staff wants assurance that the acceptance criteria / alert value is set appropriately (i.e., such that there is reasonable assurance that the component's condition does not degrade to a point where it can no longer perform its intended function under all CLB conditions). During the meeting, BGE ar, reed to reference the basis for program acceptance criteria / alert values.

Operating experience / corrective actions During the meeting, BGE stated that it would include, in the technical reports, a discussion of significant operating experierice that would address the overall historical operating experience for the system, significant age related events that may have affected a system, structure, or component, and a discussion of significant improvements to plant operations, equipment, and/or

i

. I maintenance. BGE also presented examples that illustrate the type of operating experience BGE i'itends to include in the technical reports. These examples were also presented at a November 21, 1996, public meeting.

The NRC staff stated that it believed significant progress had been made on this issue. The staff stated that the examples discussed meet the staff's expectations for the type of operating experience that should be included in the technical reports. However, the staff stated that it was concerned that BGE's position to submit only significant operating experience may result in a threshold that could preclude BGE from including some important operating experience in its technical reports. The staff stated that the threshold for providing operating experience / corrective actions in the technical reports should be set such that (1) aging effects that have actually affected a I structure or component are included, (2) a reasonable characterization of the  ;

program's se ast perf:rmance at monitoring the aging effect is described, and (3) the ar.tions taken as a result of an event or new information to improve the program's ability to manage the aging effect is included. NRC management eiso stated thct this operating experience should also include any change in operating conditions and/or any operation in an abnormal configuration (s) that could exacerbate or create an aging effect.

90-Day Cable Aging Management Exchange BGE discussed the cable aging management information it provided to the staff over the 90 day effort. BGE stated that the information provided included its approaches for addressing environmentally qualified (EQ) equipment and non-EQ cables for license renewal. BGE also pointed out that it believes its approach for EQ equipment is not a deferral of the EQ time limited aging analyses (TLAA). BGE stated that the NRC staff has not communicated any significant concerns to BGE regarding its approaches. The staff stated that its intent over the 90 day review effort was to gain a better understanding of i BGE's approach to cable aging management for renewal. The staff stated that '

it will review BGE's technical reports on EQ equipment and non-EQ cables when they are submitted. The staff also emphasized that the manner in which the EQ TLAA can be addres ted in a renewal application is an issue that is evolving and being addressed as a part of the regulatory guide development.

During the meeting, both the staff and BGE summarized a November 5, 1996, public meeting which incused on the 10 CFR Part 51 environmental review for license renewal. At the November 5, 1996, meeting, BGE proposed that an environmental report (ER) template activity be initiated to assure that BGE fully understands the staff expectations for the format and content of an ER.

BGE also stated that it would like to begin discussing some of the technical issues that must be addressed in the ER. These issues include severe accident mitigation design alternatives (SAMDA), transportation, and environmental justice.

At the November 5, 1996, meeting, the staff agreed to inform BGE at the next management meeting as to whether it would commit to an ER template review activity. Therefore, during the meeting, the staff informed BGE that it would

commit to an ER template activity and that a kickoff meeting, for the ER template review, should be held to develop the scope and schedule for the activity.

BGE concluded it 3 portion of the meeting by stating that it believes the second 90 day effort was beneficial to the NRC, BGE, and the public by clarifying NRC expectations regarding the renewal of an operating license.

BGE also stated that it believes commercial nuclear power plants can continue to operate safely beyond 40 years, and that BGE has not found any aging that is unique to license renewal. BGE also discussed its submittal schedule, which includes submitting 7 (revisions to the 5 reports submitted in May 1996, and two additional reports) reports for review in April 1997 and the remaining 23 reports by the end of the second quarter of 1997.

The staff concluded by stating that it believes significant progress was made over the 90 day review. In particular, the staff believes this effort clarified the content and level of detail of information that must be in a technical report to properly implement the template. The staff pointed out that it continues to believe the template, if properly implemented, should result in technical reports with a format and content sufficient for the staff to begin a technical review. The staff does not see a need for any further iteration on the template, and is prepared to begin the technical review of BGE reports written in accordance with the template.

//

5 k. nder [a t Manager License Renewal Project Directorate Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket Nos. 50-317, 50-318 Attachments: 1. Attendance List

2. Meeting Handouts

Mr. Charles H. Cruse Calvert Cliffs Nuclear Power Plant Calvert Cliffs Nuclear Power Plant Unit Nos. I and 2 CC:

President Mr. Joseph H. Walter. Chief Engineer Calvert County Board of Public Service Commission of Commissioners Maryland 175 Main Street Engineering Division Prince Frederick. MD 20678 6 St. Paul Centre ]

Baltimore. MD 21202-6806 4 D. A. Brune. Esquire '

' General 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 I 2300 N Street NW Co-Director Washington, DC 20037 Maryland Safe Energy Coalition P.O. Box 33111 Mr. Terrence J. Camilleri. Director. Baltimore, MD 21218 NRM Calvert Cliffs Nuclear Power Plant Mr. Larry Bell 1650 Calvert Cliffs Parkway NRC Technical Training Center Lusby. MD 20657-47027 5700 Brainerd Road Chattanooga. TN 37411-4017 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 287 St. Leonard MD 20685 Mr. Richard I. McLean

. Administrator - Radioecology Department of Natural Resources 580 Taylor Avenue j Tawes State Office Building. B3 -

Annapolis, MD 21401 Regional Administrator. Region I i U.S. Nuclear Regulatory Commission 475 Allendale Road l King of Prussia, PA 19406  :

l 1

l l

l -. . - . , --.

l

. ATTENDANCE LIST NRC MEETING WITH BALTIM0RE GAS AND ELECTRIC January 9. 1997 fWiE ORGANIZATION

1. Scott Flanders NRC/NRR/DRPM/PDLR

2. Sam Lee NRC/NRR/DRPM/PDLR

3. Alexander Dromerick NRC/NRR/DRPW-PDI-l 4

4. P. T. Kuo NRC/NRR/PDLR i 5. Scott Newberry NRC/NRR/PDLR l 6. Tim Martin NRC/NRR/DRPM

7. Frank Miraglia NRC/NRR

8. R. E. Denton BGE

9. P. G. Chabot BGE

10. W. J. Lippold BGE j 11. M. E. Bowman BGE

12. B. M. Tilden BGE

13. Don Shaw BGE

14. Barth W. Dc.oshak BGE

15. Rebecca McSwain BGE

16. Tricia Herouy for EPRI

17. C. A. Negin i

Oak Technologies -I

18. Karl Neddenien BGE 2 19. S. Singh Bajwa NRC/NRR/DRPE/PDI-1  ;

20. Paul Shemanski NRC/NRR/DRPM/PDLR

21. Steve Hoffman NRC/NRR/DRPM/PGEB

22. Claudia Craig NRC/NRR/DRPM/PGEB

23. Barry Zalchman NRC/NRR/DRPM/PGEB

24. John Moulton NRC/NRR/DRPM/PDLR

25. Martin G. Malch NRC/0GC l

l l

Attachment 1

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- Since May 1996, the staff has been reviewing a BGE developed template and BGE's implementation of the template.

- The Staff's review focused only on format and content.

- In September 1996, NRC and BGE management held a public meeting to discuss the template.

. NRC management informed BGE that the template, if properly implemented, should result in reports with a format and content sufficient for the staff to begin a technical review.

. NRC management also informed BGE that it's implementation of the template did not satisfy the staff's expectations in three areas: intended functions, operating experience, and corrective actions.

- At the September 1996 management meeting, NRC management proposed a 90-day effort .

to exercise the template in these three areas to ensure that BGE's implementation would '

satisfy the staff's expectations.

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License Renewal Discussions with U. S. Nuclear Regulatory Commission t

i January 9,1997 i Barth W. Doroshuk  :

Principal Engineer ,

6 LCMP-97-002 Slide 1 i

Presentation Objectives

- Review objectives of second 90-day effort.

- Discuss second 90-day activities.

- Present BGE-specific responses to USNRC expectations regarding template implementation.

- Review results of other 90-day discussions.

BGE observations.

BGE 1997 schedule of activities.

LCMP-97-002 Slide 2

e i

Conclusions of Initial 90-Day Effort USNRC conclusions: l "The staff concludes that when properly implemented, the template should result in reports with a format and content sufficient for the staff to begin a technical review."

Senior Management Meeting September 11,1996 i

LCMP-97-002 Slide 3 l

[

Conclusions of Initial 90-Day Effort (continued)

USNRC additionally concluded: ,

"Although it appears agreements in principle have been reached to resolve each issue, BGE has not prepared, nor has the staff reviewed revised reports that implement the agreements reached. As a result the staff proposed . . . another 90-day effort to implement the template with respect to each of the issues."

U.S. NRC letter to BGE September 23,1996 ,

I LCMP-97-002 Slide 4

N ,

Objectives of Second 90-Day Effort  :

Exercise the template to specifically demonstrate proper implementation in the areas of:

- Operating experience,

- Corrective action, .

- SC intended function and the use of design basis information to support " demonstration."

Initiate discussions regarding cable aging management.

Initiate discussions regarding execution of 10CFR Part 51.

LCMP-97-002 Slide 5 '

N .

90-Day Effort Activities - Template Exercises

- BGE and NRC held eight public meetings at Calvert Cliffs and USNRC headquarters during this effort.

- BGE re-wrote three out of five May 22,1996 reports in two phases:

- Scoping and plausible aging effects section, and

- Aging management demonstration section.

USNRC staff reviewed submittals and site information and provided written comments to BGE during each exchange of information.

- BGE will discuss its observations / positions on this set of issues.

LCMP-97-002 Slide 6

.i

4 M I

Cable Agina Management Technical Exchannes o BGE provided USNRC with overview of cable aging i management activities during site tour September 11, 1996.

- BGE and USNRC held a public meeting at USNRC .

headquarters on October 16 where BGE presented technical details to USNRC staff. 1 USNRC made one site visit in November to review on-site documentation.

\

LCMP-97-002 Slide 7

N .

10CFR Part 51 Environmental Report Technical Exchange l BGE and NRC held a public meeting in November where BGE presented:

- BGE's understanding of the revised 10CFR Part 51,

- BGE's overall environmental LCM efforts, including initial ER ,

results, and ,

- Requests for clarification in certain areas of 10CFR Part 51 In addition, BGE presented NRC with an ER .

" template" and proposed conducting a similar effort to ensure USNRC expectations on level of detail were clear.

LCMP-97-002 Slide 8 i

7_,-

i Operating Experience issue In first 90-day effort:

- NRC expectations were that the inclusion of operating .

experience in the " demonstration" would provide objective evidence of plant aging, effectiveness of aging programs and licensee's incorporation of aging lessons learned into .

corrective action programs,

- BGE agreed with these expectations; however, first 90-day effort did not fully exercise the use of this information,

- BGE and NRC agreed that the operating experience and corrective action issue were really one.

(

\

LCMP-97-002 Slide 9

4 Operating Experience Information to be included in application:

- Specific information on operating experience and maintenance history,

- References should be cited in application and details should be available on site for staff review / audit.

Reference:

NRC Handout dated 11/14/96 LCMP-97-002 Slide 10

Operatina Experience issue (continued)

BGE Response BGE agrees that historical operating experience with respect to aging can provide meaningful insight that should be used in dernonstrating that aging will be, or will continue to be managed during the License Renewal period.

l

\

Y LCMP-97-002 Slide 11

F Operating Experience issue (continued)

BGE Response

- BGE intends on including a discussion of significant operating experience in an LRA that would address three (3) areas:

- Overall historical system performance with respect to aging,

- Significant age-related events that may have affected any SSC's intended function within the scope of license renewal,

- A discussion of significant improvements to plant operations, equipment and/or engineering, maintenance and/or practices I pertaining to these events.

I LCMP-97-002 Slide 12

N Operatina Experience issue (continued)

BGE Response - Examples System level

- Reactor Coolant System - Discovery of SCC of PZR heater sleeves, resulting in leakage, and follow-on conclusions and corrective actions, including applicability to renewal term (1989),

- CVCS System - Charging Pump block cracking and follow-on conclusions and corrective actions, including applicability to renewal term,

- Saltwater System - General corrosion / pitting of piping resulting in through-wall leakage and follow-on conclusions and corrective action, including applicability to renewal term,

- Diesel Fuel Oil System -Inspection history of tank bottom wall thickness and follow-on conclusions and corrective action, including applicability to renewal term,

- Containment-Tendon grease leakage and follow-on conclusions and corrective action, including applicability to renewal term.

LCMP-97-002 Slide 13

1 N

Operatina Experience issue  :

(continued)

BGE Response - Examples (continued)

Sigriificant age-related issues

- Thermal stratification of piping systems (e.g. RCS, FW) and follow-on '

conclusions and corrective action, including applicability to renewal term,

- SCC of Alloy 600 and follow-on conclusions and corrective action, including -

applicability to renewal term, .

- IASCC of reactor vessel internals and follow-on conclusions and corrective action, including applicability to renewal term,  ;

- Neutron embrittlement of the reactorvessel and follow-on conclusions and corrective action, including applicability to renewal term,

- Steam generator tube degradation issues and follow-on conclusions and corrective action, including applicability to renewal term,

- External pipe surface SCC in CVSS system due to heat tracing adhesive and follow-on conclusions and corrective action, including applicability to renewal term.

LCMP-97-002 slide 14

Operating Experience issue (continued)

BGE Response - Examples (continued)

- Aging management program improvements

- SCC Alloy 600 inspection program,

- Boric acid corrosion inspection program,

- Saltwater system GL 89-13 inspection activities,

- Fatigue management program,

- Radiation embrittlement of the reactor vessels.

LCMP-97-002 Slide 15

~

Intended Function

- Issue:

- NRC management stated that the discussion ofintended functions should also include the identification of current licensing basis (CLB) loading conditions under which the intended function of the SC must be maintained.

- Information to be included in application:

- Specific information that all CLB design conditions are considered in developing " alert values" for programs.

- References should be cited in application and details should be available on site for staff review / audit.

Reference:

NRC Handout dated 11/14/96 2

LCMP-97-002 Slide 16

N NRC Intended Function Guidelines BGE Response BGE believes that defining the design conditions and/or parameters belongs in two places of the application:

1) Scopina Sections: High level design loading condition descriptions as they apply to the SSCs and intended function (s). ,

2) Aaina Management Proaram

Description:

For some aging management programs that utilize pre-analyzed and quantitative specific alert / acceptance criteria (e.g. wall thinning, fatigue usage) summary design basis information may be needed to support NRC review.

LCMP-97-002 Slide 17

_______._.__._..._-_.__-.__m.___ _ _ _ _ . _ _ _ _ _ _ . _ _ _ _ _ . . _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ . _ _ _ _ . . _ - _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ . _ . _ _ _ _ _ . . _ . _ .

NRC Intended Function Guidelines BGE Response

- BGE will include in the scoping portions of the LRA the high level design loading conditions as they apply to the specific SSC's (device types) being included in the aging management review of the IPA.

- Examples include (and were included in 10/10/96 template package):

Piping class Seismicrequirements Code of construction 1E requirements & standards Missile barrier requirements Tornado / hurricane requirements etc.

- Some or all of the specific loading conditions may be referenced as allowed by the template.

s Slide 18 LCMP-97-002

/

N -

NRC Intended Function Guidelines BGE Response - Agina Management Demonstration  !

BGE agrees with NRC guidelines where they state that when I an aging management program is implemented to prevent or '

eliminate aging, no design loading and/or basis information needs to be provided in application.

Example *:

Piping supports / corrosion (painting) program:

- Piping supports designed to support piping consistent with system piping design loading conditions,

- Painting ensures that no material is lost due to corrosion and thus, piping supports would continue to perform their intended '

function as originally designed (include references to the painting and inspection programs).

Reference:

NRC Handout dated 11/14/96 LCMP-97-002 Slide 19

NRC Intended Function Guidelines BGE Response - Agina Management Demonstration (continued)

- BGE believes that two cases exist that dictate when specific design loading and/or basis information should be included in the application (or referenced).

- Both cases involve aging management programs that include pre-analyzed, quantitative conditions which are used as alert values or acceptance criteria.

- If a program does not rely on pre-analyzed conditions, design information would not be provided in the application for that aging management program because it doesn't exist.

i LCMP-97-002 Slide 20

N NRC Intended Function Guidelines BGE Response - Aging Management Demonstration (continued)

Case 1

- If an aging management program to be relied on by BGE meets all of the following criteria no specific component-by-component design loading or basis information (e.g. the basis for min wall) would be included in the application other than what the template (10/24/96) examples already include:

The program must

- manage the aging effect, and

- be regulatory based, and

- under NRC regulatory oversight (inspected and/or docketed), and

- use alert / acceptance criteria that will not be changed solely for the renewal period.

LCMP-97-002 Slide 21

W NRC Intended Function Guidelines BGE Response - Aging Management Demonstration (continued)

Case 1 Examples

- Fatigue /ISI program,

- Radiation embrittlement of reactor vessel,

- Environmental qualification program,

- Erosion / corrosion program,

- Saltwater system (GL 89-13) programs.

LCMP-97-002 Slide 22

c NRC Intended Function Guidelines BGE Response Aging Management Demonstration (continued)

Case 1 Examples illustrate

- Comprehensive establishment of regulatory basis,

- Comprehensive dissemination of regulatory response requirements for licensees,

- Comprehensive incorporation of plant and industry operating experience,

- Comprehensive licensea response, including addressing design and licensing basis adequacy,

- Comprehensive NRC review, oversight and judgment regarding  ;

adequacy of plant program response on an ongoing basis.

LCMP-97-002 Slide 23

f E NRC Intended Function Guidelines BGE Response Aging Management Demonstration (continued)

Case 2 If an aging management program to be relied upon by BGE does not meet the criteria of Case 1, then specific design basis information (summary format) would be supplied to allow USNRC to determine the adequacy of the specific pre-analyzed quantitative alert value and/or acceptance criteria.

t LCMP-97-002 Slide 24

Cable Aging Management Discussions

- At NRC senior management meeting on September 11,1996, USNRC stated that the aging of cables is an emerging issue.

- BGE and USNRC agreed to exchange information about Calvert Cliffs aging management actiorf on .

cables.

- Objectives of discussions were tc determine if " path" BGE was on was reasonable.

LCMP-97-002 Slide 25

o Cable Aging Management Discussions (continued)

- BGE provided NRC with following information on cable aging management activities:

- Overview of cables at Calvert Cliffs,

- Potential / plausible aging mechanisms identified,

- Details of Calvert Cliffs evaluation process (thermal screening),

- Results of work performed to date.

- BGE provided NRC with our approach to addressing EQ equipment for license renewal.

- BGE provided NRC with our involvement with industry activities associated with cable aging.

i LCMP-97-002 Slide 26

=7 i

Cable Aging Management Discussions i

Summary of Results USNRC has not communicated any significant -

concerns to BGE regarding our approach to ,

managing aging for non-EQ cables. .

BGE has communicated to NRC that Calvert Cliffs will not " defer" the actions required by 10CFR Part 54 regarding TLAAs as they apply to EQ equipment.

BGE noted that several issues may remain open for any early license renewal applicant.

- Cable condition monitoring is still undefined by NRC and industry.

V Slide 27 LCMP-97-002 i

E 10CFR Part 51 Environmental Report Discussion November 5,1996 Meeting Summary BGE proposed that an ER " template" activity be initiated with USNRC to assure USNRC expectations

were clear.

- In addition, BGE believes that several technical issues required to be evaluated by licensees in an ER need to be discussed to understand scope as well: ,

- SAMDA,

- Transportation, NA" issues (EMF, environmentaljustice).

- BGE is ready to support these exchanges.

i LCMP-97-002 Slide 28 ,

t

N BGE Observations

- BGE believes that this second 90-day effort continues to benefit NRC, BGE and the public by clarifying NRC .

expectations regarding renewing operating licenses.

- BGE appreciates NRC commitment of resources on license renewal and in working with BGE.

- BGE strongly believes that with adequate aging management commercial nuclear power plants can continue to safely operate beyond 40 years.

- BGE has not discovered any aging that is unique to license renewal. .

LCMP-97-002 Slide 29

. . _ _ . . . _ m . . . . . . ..m_. . - .. . . . . _ . - . . -. . -

- m BGE 1997 Schedule of Activities t 1

BGE will respond to initial 268 questions on May 22, 1996 submittal in February 1997.

BGE has begun the formal re-write of May 22,1996 '

reports and expects to re-submit them by April 1997.

I BGE will complete the remaining 23 technical reports by end of second quarter and will be submitting them to NRC for review and approval during this time.

BGE will complete ER by second quarter of 1997.

LCMP-97-002 Slide 30

l l

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i commit to an ER template activity and that a kickoff meeting, for the ER

. template review, should be held to develop the scope and schedule for the activity.

BGE concluded its portion of the meeting by stating that it believes the second 90 day effort was beneficial to the NRC, BGE, and the public by clarifying NRC expectations regarding the renewal of an operating license. ,

BGE also stated that it believes commercial nuclear power plants can continue l to operate safely beyond 40 years, and that BGE has not found any aging that is unique to license renewal. BGE also discussed its submittal schedule, which includes submitting 7 (revisions to the 5 reports submitted in May 1996, and two additional reports) reports for review in April 1997 and the remaining 23 reports by the end of the second quarter of 1997.

The staff concluded by stating that it believes significant progress was made over the 90 day review. In particular, the staff believes this effort clarified the content and level of detail of information that must be in a j technical report to properly implement the template. The staff pointed out 4 that it continues to believe the template, if properly implemented, should l result in technical reports with a format and content sufficient for the staff to begin a technical review. The staff does not see a need for any further iteration on the template, and is prepared to begin the technical review of BGE reports written in accordance with the template.

Original signed by: i Scott C. Flanders, Project Manager License Renewal Project Directorate  !

Division of Reactor Program Management Office of Nuclear Reactor Regulation Docket Nos. 50-317, 50-318 Attachments: 1. Attendance List

2. Meeting Handouts cc w/ attachments: See next page I

i DOCUMENT NAME: Ayl)GE0109.MTS (SFlanders/ Disk)

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