ML20059N938
| ML20059N938 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/10/1990 |
| From: | Mcdonald D Office of Nuclear Reactor Regulation |
| To: | Creel G BALTIMORE GAS & ELECTRIC CO. |
| Shared Package | |
| ML20059N939 | List: |
| References | |
| TAC-68525, TAC-68526, NUDOCS 9010240134 | |
| Download: ML20059N938 (4) | |
Text
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October 10, 1990 Docket Nos. 50-317 and 50-318 i
Mr. G. C. Creel Vice President - Nuclear Energy Baltimore Gas and Electric Company Calvert Cliffs Nuclear Power Plant MD Rts 2 & 4 P. O. Box 1535 Lusby, Maryland 20657
Dear Mr. Creel:
SUBJECT:
RESPONSE TO STATION BLACKOUT RULE - CALVERT CLIFFS NUCLEAR POWER I
PLANT, UNITS 1AND2.TACNUMBERS68525(UNIT 1)AND68526(UNIT 2)
On July 21, 1988, the Code of Federal Regulations 10 CFR Part 50, was amended to include a new Section 50.63, entitled, " Loss of All Alternating Current Power " (Station Blackout).
Thestationblackout(S80)rulerequiresthat j
each light-water-cooled nuclear power plant be able to withstand and recover i
from an SB0 of specified duration.
The SB0 rule also requires that information defined in the rule be provided to the staff for review.
By letters dated April 14, 1989 March 30 and September 24, 1990, you provided your response to the SB0 rule for the Calvert Cliffs Nuclear Power Plant, Units 1 and 2.
The staff, with the assistance of Science App 1' cations Inter-national Corporation (SAIC), has reviewed your responses. The enclosed Safety Evaluation (SE) provides the results of the staff's review including the criteria used to determine compliance with the 580 rule. /ttachment 1 to the staff's SE is the SAIC Technical Evaluation Report which was the basis for our findings and conclusions in the SE.
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Your proposed design includes the addition of two emergency diesel generators (EDGs) which, with the existing three EDGs, will provide two dedicated EDGs per unit plus one spare EDG. The spare EDG will be used as an Alternate AC (ACC) sower source for SB0 conditions and as a substitute for any dedicated EDG ta(en out of serview for an extended period, such as maintenance or repair.
The staff has' concluded that your l>roposed design and methods of dealing with an SB0 to be in conformance with t w SB0 rule.
This finding is contingent upon your confirmation, within 30 days, from receipt of this letter that the
. recommendations identified in this SE will be implemented. Several reevaluations 1
and confirmations still need to be completed as described in the recossendations.
These include reevaluating the plant's ability to cope with an SB0 for 8-hours or provide additional justification for the 4-hour duration, confirmation that the modified EDG to be used as an AAC source meets the criteria of Appendix B Wo \\
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Mr. G. C. Creel,
to Nuclear Management and Resources Council, Inc. (NUMARC) 87-00, reevaluating the effects of loss of ventilation in areas of concern, reevaluating the adequacy of reactor coolant system inventory if an 8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> coping duration is used, confinnation that a quality assurance program for the 5B0 equipment will be implemented in accordance with the guidance of Regulatory Guide (RG) 1.155, i
C.3.5, and confirmation tMt an EDG reliability program in accordance with RG.
1.155, Section 1.2, will be implemented.
Your response to the recommendations j
should also include a schedule for implementin the proposed modifications and procedures in accordance with 10 CFR 50.63(c)( ).
l All analysis, confirmations, and other documentation supporting your SB0 submittels should be maintained and available for further staff inspection and assessment.
The staff is currently considering technical specifications (TS) for SB0 equipment in context of the TS Improvement Program.
In the interim, plant procedures to reflect the appropriate testing and surveillance requirements should be in place to ensure the operability of the necessary S80 equipment.
You will be notified if a detennination is made that TS are required for SB0 equipment.
This request for confirmation and infonnation affects fewer than ten respondents; therefore, OM6 clearance is not required under Public Law 96-511.
j Sincerely.
L w
Daniel G. Mcdonald, Senior Project Manager l
Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: w/ enclosure See next page l
l 1
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g Mr. G. C. Creel Baltimore Gas & Electric Company Calvert Cliffs Nuclear Power Plant CC' Mr. William T. Bowen, President Mr. Joseph H. Walter Calvert County Board of Engineering Division Comissioners Public Service Comission o' Maryland Prince Frederick, Maryland 20678 American Building l
231 E. Baltimore Street Baltimore, Maryland 21202-3486 D. A. Brune, Esq.
General Counsel Baltimore Gas and Electric Company Ms. Kirsten A. Burger, Esq.
P. O. Box 1475 Maryland People's Counsel Baltimore, Maryland 21203 American Building, 9th Floor 231 E. Baltimore Street Mr. Jay E. Silberg, Esq.
Baltimore, Maryland 21202 Shaw, Pittman, Potts and Trowbridge l
2300 N Street, NW Ms. Patricia Birnie Washington, DC 20037 Co-Director Maryland Safe Energy Coalition P. O. Box 902 Ms. G. L. Adams, Licensing Columbia, Maryland 21044 Calvert Cliffs Nuclear Power Plant MD Rts 2 & 4 P. O. Box 1535 Lu sby.. Maryland 20657 Resident inspector c/o U.S. Nuclear Regulatory Comission P. O. Box 437 Lusby, Maryland 20657 b
Mr. Richard McLean Administrator - Radioecology I
Department of Natural Resources 580 Taylor Avenue i
Tawes State Office Building PPER 83 Annapolis, Maryland 21401 Regional Administrator, Region !
U.S. Nuclear Regulatory Comission i
475 Allendale Road King of Prussia, Pennsylvania 19406 l
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L J
i Mr. G. C. Creel '
toNuclearManagementandResourcesCouncil,Inc.(NUMARC)87-00, reevaluating the effects of loss of ventilation in areas of concern, reevaluating the adecuacy of reactor coolant system inventory if an 8-hour coping duration is usec, confirmation that a quality assurance program for the SB0 equipment will be implemented in accordance with the guidance of Regulatory Guide (RG) 1.155, C.3.5, and confirmation that an EDG reliability program in accordance with RG.
1.155. Section 1.2, will be implemented. Your response to the recommendations should also include a schedule for implementing the proposed modifications and procedures in accordance with 10 CFR 50.63(c)(4).
All analysis, confimations, and other documentation supporting your SB0 submittals should be maintained and available for further staff inspection and assessment. The staff is currently considering technical specifications (TS) for SB0 equipment in context of the TS Improvement Program.
In the interim, plant procedures to reflect the appropriate testing and surveillance requirements should be in place to ensure the operability of the necessary SB0 equipment. You will be notified if a detemination is made that TS are required for SB0 equipment.
This request for confimation and information affects fewer than ten respondents; therefore, OMB clearance is not required under Public Law 96-511.
- Sincemly, ORIGINAL StGNED BYi Daniel G. Mcdonald, Senior Project Manager Project Directorate I-1 Division of Reactor Projects - I/II Office of Nuclear Reactor Regulation
Enclosure:
As stated cc: w/ enclosure See next page Distribution L
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