ML20035B261

Summary of 930317 Meeting W/Bg&E Re Qualified Test Program for New Emergency Diesel Generators

ML20035B261
Person / Time
Site:	Calvert Cliffs
Issue date:	03/24/1993
From:	Mcdonald D Office of Nuclear Reactor Regulation
To:	Office of Nuclear Reactor Regulation
References
NUDOCS 9304010100
Download: ML20035B261 (6)

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,k UNITED STATES

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NUCLEAR REGULATORY COMMISSION s'

i March 24, 1993 Docket Nos. 50-317 and 50-318 LICENSEE:

Baltimore Gas and Electric Company (BG&E)

FACILITY: Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2

SUBJECT:

MEETINC MINUTES REGARDING THE MARCH 17, 1993, MEETING TO DISCUSS THE QUALIFICATION TEST PROGRAM FOR THE NEW EMERGENCY DIESEL GENERATORS - CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT 1 (TAC NO. M85715) AND UNIT 2 (TAC NO. M85716)

BACKGROUND:

On July 21,1988, Part 50 of' Title 10 of the Code of Federal Regulations was amended to include a new Section 50.63, entitled, " Loss of All Alternating Current Power," referred to as the station blackout (SBO) rule.

The SB0 rule requires that each light-water cooled nuclear power plant be able to withstand and recover from an SB0 of specified duration.

The SB0 rule also requires that information defined in the rule be provided to the staff for review.

BG&E responded to the requirements of the rule and the staff approved its response by letter dated February 12, 1992. The staff's approval included the addition of two new safety-related Class-lE emergency diesel generators (EDGs).

A series of meetings are being held to discuss various design aspects of the EDG addition.

BG&E has provided a Civil Engineering Report and the Qualification Test Program for NRC staff review and approval.

These submittals will be followed by other submittals addressing the additional design requirements for the EDG addition which are being discussed during the series of meetings.

PURPOSE This meeting focused on the Qualification Test Program for the EDGs which was submitted on January 29, 1993. The Qualification Test Program addresses the qualification requirements, proposed testing at the factory, proposed testing on-site, previous qualification testing performed on the same model EDGs, and other qualification issues including seismic and environmental requirements.

A list of attendees is enclosed.

SUMMARY

The NRC staff and BGSE representatives discussed the details of the January 23, 1993, submittal to identify any areas needing additional t

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information or clarification to allow the staff to complete its review prior to BG&E initiating the Qualification Test Program for the EDGs.

It was determined that additional information is required in the following areas:

1) Clarification of the starting conditions for_ the load tests.

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2) Clarification of the load capability testing including the percentage range of the continuous load value, short time load tests, and rated load tests.

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3) Definition of acceptable limits for the loss of short-time load transient response and the light and no load operation.

4) Clarification on the start and acceptance load tests including the number of step loads, value of the largest load, percentage range of acceptance, and the acceptance criteria for the loss-of-load tests.

5) Clarification on the site testing including percentage of manual loading, number of tests, and starting conditions for the tests.

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6) Clarification on the integrated safeguards preoperational testing.

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7) Clarification of torsional vibration considerations.

BG&E indicated that a supplemental submittal would be provided to address the l

areas detailed above.

BG&E further indicated that the supplemental submittal would be provided in early April to allow the staff to complete its review in a timely fashion.

The information requested affects one respondent and, therefore,- is not subject to the Office of Management and Budget review under P.L.96-511.

, _ J_

i Daniel G. Mcdonald, Senior Project Manager Project Directorate I-l i

Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation Enclosure-Attendance List j

cc w/ enclosure:

See next page

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Calvert Cliffs Nuclear Power Plant i

Baltimore Gas & Electric Company Unit Nos. I and 2 cc:

Mr. Michael Moore, President Mr. Joseph H. Walter Calvert County Board of Engineering Division I

Commissioners Public Service Commission of l

175 Main Street Maryland Prince Frederick, Maryland 20678 American Building l

231 E. Baltimore Street t

D. A. Brune, Esquire Baltimore, Maryland 21202-3486 General Counsel Baltimore Gas and Electric Company Kristen A. Burger, Esquire P. O. Box 1475 Maryland People's Counsel Baltimore, Maryland 21203 American Building, 9th Floor 231 E. Baltimore Street Jay E. Silberg, Esquire Baltimore, Maryland 21202 Shaw, Pittman, Potts and Trowbridge 2300 N Street, NW Patricia T. Birnie, Esquire Washington, DC 20037 Co-Director Maryland Safe Energy Coalition Mr. G. L. Detter, Director, NRM P. O. Box 33111 l

Calvert Cliffs Nuclear Power Plant Baltimore, Maryland 21218 1650 Calvert Cliffs Parkway Lusby, Maryland 20657-4702 Mr. Robert E. Denton Vice President - Nuclear Energy Resident Inspector Baltimore Gas and Electric Company c/o U.S. Nuclear Regulatory Calvert Cliffs Nuclear Power Plant Commission 1650 Calvert Cliffs Parkway P. O. Box 287 Lusby, Maryland 20657-4702 St. Leonard, Maryland 20685 Mr. Richard I. McLean Administrator - Radioecology Department of Natural Resources l

580 Taylor Avenue Tawes State Office Building B3 l

Annapolis, Maryland 21401 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 l

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ENCLOSURE MARCH 17. 1993 EDG MEETING ATTENDANCE LIST l

NAME COMPANY Daniel Mcdonald NRC/NRR/PDI-l l

Saba N. Saba NRC/NRR/EELB Om P. Chopra-NRC/NRR/EELB Richard 14. Skokowski NRC/ Region I/EBES

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D. Plercf.on SACM Diesel

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f Darrell Thornley SACM Diesel Dale G. Dixon NPS Contract To BG&E T. L. Konerth-BG&E J. R. Adams Bechtel.

l Bob Yamrus

~Bechtel i

Pat Furio BG&E v

P. J. Hebrank BG&E i

Don Perrine BG&E Christy Leskovar Sechtel j

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March 24, 1993 information or clarification to allow the staff to complete its review prior to BG&E initiating the Qualification Test Program for the EDGs.

It was determined that additional information is required in the following areas:

1) Clarification of the starting conditions for the load tests.

2) Clarification of the load capability testing including the percentage range of the continuous load value, short time load tests, and rated load tests.

3) Definition of acceptable limits for the loss of short-time load transient response and the light and no load operation.

4) Clarification on the start and acceptance load tests including the number of step loads, value of the largest load, percentage range of acceptance, and the acceptance criteria for the loss-of-load tests.

5) Clarification on the site testing including percentage of manual loading, number of tests, and starting conditions for the tests.

6) Clarification on the integrated safeguards preoperational testing.

7) Clarification of torsional vibration considerations.

BG&E indicated that a supplemental submittal would be provided to address the areas detailed above.

BG&E further indicated that the supplemental submittal would be provided in early April to allow the staff to complete its review in a timely fashion.

The information requested affects one respondent and, therefore, is not subject to the Office of Management and Budget review under P.l.96-511.

Original signed by:

Daniel G. Mcdonald, Senior Project Manager Project Directorate I-l Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation

Enclosure:

Attendance List cc w/ enclosure:

See next page Distribution:

See next page LA:PDl-1 PM:PDI-l D:PDI-l _ s w

DMcDonald:smm RACapra CVogan

~/;'/93 03/ Qi93 3 /24/93

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OFFICIAL RECORD COPY FILENAME: CC85715.MTS

DISTRIBUTION LIST FOR MEETING

SUMMARY

OF. MARCH 17, 1993:

~ Docket File-NRC & Local PDRs PDI-I Reading i

T. Murley/F. Miraglia,12/G/18 J.'Partlow, 12/G/18 S. Varga J. Calvo R. A. Capra D. Mcdonald i

C. Vogan i

OGC E. Jordan S. Saba, 7/E/4

0. Chopra, 7/E/4 R. Skokowski, RGN-1 ACRS (10)

V. McCree, EDO, 17/G/21 C. Cowgill, RGN-I i

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