ML20198S631
| ML20198S631 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 11/05/1997 |
| From: | Cruse C BALTIMORE GAS & ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| GL-97-04, GL-97-4, NUDOCS 9711140077 | |
| Download: ML20198S631 (2) | |
Text
_,
.e CnAntxs 11. C;usr Ihltimore Gas and Electric Company Vice President Calvert Cliffs Nuclear Power Plant Nuclear Ene gy 1650 Calvert Cliffs Parkway Lusby. Maryland 2%57 410 495-4455 o
November 5,1997
. U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 ATTENTION:
Document Control Desk
SUBJECT:
Calvert Cliffs Nuclear Power Plant Unit Nos.1 & 2; Docket Nos. 50-317 & 50-318 30-Day Response to Generic Letter 97-04: Assurance of Sufficient Net Positive Suction llead for Emergency Core Cooling and Containment Ileat Removal Pumns
REFERENCE:
(a)
NRC Generic Letter 97 04: Assurance of Sufficient Net Positive Suction Head for Emergency Core Cooling and Containment Heat Removal Pumps, dated October 7,1997 The purpose of this letter is to forward our 30-day response to Reference (a). The generic letter requests tnat within 30 days from the date of the generic letter, each addressee submit a written response indicating whether or not the requested information will be submitted within the requested time period.
The infonnation requested is related to the current design basis analyses used to determine the available Net Positive Suction IIcad (NPSil) for the emergency core cooling and containment heat removal pumps that take suction from the containment sump. Specifically, the NRC requests that we provide the folbwing information within 90 days:
1.
Specify the general methodology used to calculate the head loss associated with the ECCS suction strainers.
2.
Identify the required NPSH and the available NPSH.
3.
Specify whether the current design basis NPSH analysis differs from the most recent analysis j
reviewed and approved by the NRC for which a safety evaluation was issued.
/
4.
Specify whether containment overpressure (i.e., containment pressure above the vapor pressure of the sump or suppression pool fluid) was credited in the calculation of available NPSH. Specify the amount of overpressure needed and the minimum overpressure available.
5.
- When containment overpressure is credited in the calculation of available NPSH, confirm that an appropriate containment pressure analysis was done to establish the minimum containment pressure.
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i Baltimore Gas and Electric Company will respond with the requested informa ion within the speciUed time period.
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Should you have questions regarding this matter, we will be pleased to discuss them with you.
Very truly yers, i
s
~ STATE OF MARYLAND
- TO WIT:
COUNTY OF CALVERT -
J 1, Charles II. Cruse, being duly sworn, state that I am Vice President, Nuclear Energy Division, 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 knowledge, they are based upon information provided by other BGE employees and/or consultants. Such l
information has been reviewed in accordance with company practice and I believe '
be reliable.
uli n M
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Subscribed and sworn before me, a Notary Public in and for the State of Maryland and County of M;w/,
this 5% dayoflm/,nl,1997.
WITNESS ' my lland and Notarial Scal:
Notary Public m
s y Coinmission Expires:
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of,(e CilC/SJR/dtm cc:
R. S. Fleishman, Esquire H. J. Miller, NRC J. E. S:lberg, Esquire Resident inspector, NRC A. W. Dromerick, NRC J. H. Walter, PSC R.1. McLean, DNR Director, Project Directorate 1 1, NRC e.1-c.
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