ML19282B222
| ML19282B222 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 02/09/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Lundvall A BALTIMORE GAS & ELECTRIC CO. |
| References | |
| NUDOCS 7903090412 | |
| Download: ML19282B222 (4) | |
Text
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UfJITED STATES 4
NUCLEAR REGULATORY COMMISSION
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j WASHlhGTON, D. C. 20555
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February 9,1979 Dockets Nos.: 50-317 and 50-318 Mr. A. E. Lundvall, Jr.
Vice President - Supply Baltimore Gas & Electric Company P. O. Box 1475 Baltimore, Maryland 21203
Dear Mr. Lundvall:
By letter dated November 13, 1978, you requested 11 changes to Facility Operating Licenses Nos. DPR-53 and DPR-69 for Calvert Cliffs Nuc1*ar Power Plant Units Nos.1 and 2.
Request No. 11 was to delece condition 2.C.3 of the Unit n'a. 2 operating license.
This condition relates to the slow lefill rate of the steam generator required to reduce the probability of feedwater flow instability (water hamer) after the steam generator water level has been below the feedwater feed ring. Your request is based on recent modifications made to the steam generator feed ring.
In the process of reviewing your request and to enable us to perform an independent analysis of the feedwater flow instability, we find that the enclosed request for additional information is necessary to complete our review.
Please provide this additional information within 30 days of the receipt of this letter.
In order to provide guidance to you regarding our objectives and the degree of detail that ill be necessary in your response, we are enclosing a recently issued staff evaluation of steam gener-ator feedwater flow instability at the Surry Power Station.
Sincerely,
) k b(
0 Robert W. Re'f, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosures:
1.
Request for Additional Information 2.
Safety Evaluation for the Surry Power Station dtd. 6/7/78 cc w/ enclosures: See next page 7903090 Q t
4 Baltimore Gas & Electric Company cc:
James A. Biddison, Jr.
Mr. R. M. Douglass, Manager General Counsel Quality Assurance Department G and E Building Room 923 Gas & Electric Building Charles Center P. O. Box 1475 Bal timore, Maryland 21203 Baltimore, Maryland 21203 George F. Trowbridge, Esquire Shaw, Pittman, Potts and Trowbridge 1800 M Street, N.tl.
Washington, D. C.
20036 Mr. R. C. L. Ol son Baltimore Gas and Electric Company Room 922 - G and E Building Post Of fice Box 1475 Baltimore, Maryland 21203 Mr. Leon B. Russell, Chief Engineer Calvert Cliffs Nuclear Powbr Plant Baltimore Gas and Electric Company Lusby, Maryla~nd 20657 Bechtel Power Corporation ATTN: flr. J. C. Judd Chief Nuclear Engineer 15740 Shady Grove Road Gaithersburg, Maryland 20760 Combustion Engineering, Inc.
ATTN: Mr. P. W. Kruse, Manager Engineering Services Post Office Box 500 Windsor, Connecticut 06095 Calvert County Library Prince Frederick, Maryland 20678
E REQUEST FOR ADDITIONAL INFORMATION
_CALVERT CLIFFS NUCLEAR POWER PLANT UNITS 1 AND_2 STEAM GENERAT_0R WATER HAMMER l.
Provide a description of the feedwater system and pertinent piping geometry including all condensate and feedwater pump trip signals, feedwater isolation signals, feedwater valve controls, feedwater valve bypass control.s. feedwater sparger vents and discharge ports and clearance between the feedwater sparger nozzle 0.D. and steam generator nozzle I.D.
2.
Provide a description of the auxiliary feedwater system and piping geometry including all signals that initiate operation of all pumps and valves, sources of auxiliary feedwater and injection points, and sources of energy for all pump and valve operations.
3.
Discuss the operation of the main and auxiliary feedwater systems unde-nomal and transient conditions including safety injection actuation.
4 Provide a sumary of the pertinent water hammer experience at the Calvert Cliffs Plant including the results of tests relating to water hamer in the steam generator or feedwater systems.
5.
Describe the means employed at the Calvert Cliffs Plant to reduce the potential for water hammer including steam generatur level controls, top discharge ports in feedwater sparger, main feedwater valve operatien and automatic as well as administrative control of auxiliary feedwater fl ow.
2._
6.
Provide an evaluation of the means employed to avoid water hammer that demonstrates that the feedwater lines and feedwater spargers will remain sufficiently filled with water to preclude water hammer under nonnal and transient operating conditions including: a reactor trip with turbine trip, loss of main feedwater, loss of offsite power, operator error, steam line break ar j LOCA.