ML15223A544
| ML15223A544 | |
| Person / Time | |
|---|---|
| Site: | Davis Besse, Oconee, Arkansas Nuclear, Crystal River, Rancho Seco  |
| Issue date: | 11/21/1979 |
| From: | Reid R Office of Nuclear Reactor Regulation |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7912100478 | |
| Download: ML15223A544 (7) | |
Text
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TreIR,. WJ'Busse,a lnga Docket Nos.: d
,0-270, 50-287, 50-302 RL -312, 50-313, 50-346 TO ALL BABCOCK & WILCOX (8&W) OPERATING PLANTS (ECEPT T zE MILE ISLAND, UNITS 1 AND 2)
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - SMALL BREAK LOSS-OF COOILANT ACCIDENT Mr. C1. Michaeison of the Tennessee Valley Authority has identified a nymber of concerns which w rI addressed to the Combustion Enginee rng
- ystem 80 design. Mowget cetai'n of these concerns are considered applicable to all press ~~
water reactors. Therefore, enelosed is a request for additicial rmatten, containing the concerns which are applicable tBW d sig d'plants.
Responses to these quest3 ns ([tncluding commitments and schedule for those problems which re substantial time for resolution) are requested by D in-order for us to incrporate your respogses toNUREG-0565 a~tff Report on Generic Evaluation of Small Break ikess-of-Coolant Acc et Behavior for Babcock & Wilcox Operating Plants").
If any additional informatioqn is requested concerning this matter, please co act Mr. R. Capra (301) 4 2-7745.
Original Signed By:
R.. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Request for Additional Ihnformation -
Metropolitan Edison Co.
Babcock &WWiox O
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SpR EG&IU UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 Docket Nos.:
50-269, 50-270, 50-287, NOV 2 1 1979 50-302, 50-312, 50-313, 50-346 TO ALL BABCOCK & WILCOX (B&W) OPERATING PLANTS (EXCEPT THREE MILE ISLAND, UNITS 1 AND 2)
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION - SMALL BREAK LOSS-OF COOLANT ACCIDENT Mr. C. Michaelson of the Tennessee Valley Authority has identified a number of concerns which were addressed to the Combustion Engineering System 80 design. However, certain of these concerns are considered applicable to all pressurized water reactors. Therefore, enclosed is a request for additional information, containing the concerns which are applicable to B&W designed plants.
Responses to these questions (including commitments and schedule for those problems which require substantial time for resolution) are requested by December 3, 1979, in order for us to incorporate your responses to NUREG-0565 ("Staff Report on Generic Evaluation of Small Break Loss-of-Coolant Accident Behavior for Babcock & Wilcox Operating Plants").
If any additional information is requested concerning this matter, please contact Mr. R. Capra (301) 492-7745.
R. W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Request for Additional Information - SB LOCA cc w/enclosure:
See next page
B&W ADDRESSEES -
REQUEST FOR ADDITIONAL INFORMATION -SMALL BREAK LOCA November 21, 1979 Mr. James H. Taylor Mr. R. C, Arnold Manager, Licensing Babcock & Wilcox CompanySeirVcPesdn Babcck &Wilcx CopanyMetropolitan Edison Company Power Generation Group 260 Cherry Hill Road P. 0. Box 1260 Lynchburg, Virginia 24505 PripnNwJre 75 Mr. William 0. Parker, Jr.
Mr. J. G. Herbein Vice President -
Steam Production Vice President Duke Power Company Metropolitan Edison Company P. 0. Box 2178 P. 0. Box 480 422 South Church St.7 Charlotte, North Carolina 28242 Mr. W. P. Stewart Vnager, Nuclear Operations Florida Power Corporation P. 0. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 Mr. J. J. Mattimoe Assistant General Manager and Chief Engineer Sacramento Municipal Utility District 6201 S Street Sacramento, California 95813 Mr. William Cavanaugh, III Vice President, Generation and Construction4 Arkansas Power & Light Company P. 0. Box 551 Little Rock, Arkansas 72203 Mr. Lowell E. Roe Mr. Ted Myers Vice President, Facilities Licensing Engineer Development Toledo Edison Company Toledo Edison Company Edison Plaza Edison Plaza 300 Madison Avenue 300 Madison Avenue Toledo, Ohio 43652 Toledo, Ohio 43652
Request for Additional Information:
Small Break Loss-of-Coolant Accident
- 1. Transitions from solid natural circulation to reflux boiling and back to solid natural circulation may cause slug flow in the hot leg piping. By use of analysis and/or experiment, address the mechanical effects of the induced slug flow on steam generator tubes.
- 2. How are the HPSI pumps protected against deadheading if the system repressurizes? If operator action is required, show that there is sufficient time for operator response. How is this covered in guide lines for emergency procedures? (Applicable to Davis-Besse 1 only)
- 3. Evaluate the impact.of RCP seal damage and leakage due to loss of seal cooling on loss of offsite power. How long can the RCP seals sustain loss of cooling without damage?
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON,D.
C. 20555 Docket Nos.:
50-269, 50-270, 50-287, NOV 21 1979 50-302, 50-312, 50-313, 50-346 TO ALL BABCOCK & WILCOX (B&W) OPERATING PLANTS (EXCEPT THREE MILE ISLAND, UNITS 1 AND 2)
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION -
SMALL BREAK LOSSrOF COOLANT ACCIDENT Mr. C. Michaelson of the Tennessee Valley Authority has identified a number of concerns which were addressed to the Combustion Engineering System 80 design. However, certain of these concerns are considered applicable to all pressurized water reactors. Therefore, enclosed is a request for additional information, containing the concerns which are applicable to B&W designed plants.
Responses to these questions (including commitments and schedule for those problems which require substantial time for resolution) are requested by December 3, 1979, in order for us to incorporate your responses to NUREG-0565 ("Staff Report on Generic Evaluation of Small Break Loss-of-Coolant Accident Behavior for Babcock & Wilcox Operating Plants").
If any additional information is requested concerning this matter, please contact Mr. R. Capra (301) 492-7745.
R. W. Reid, Chief Operating Reactors Branch #4 Division of Operating Reactors
Enclosure:
Request for Additional Information -
See next page 7912100
B&W ADDRESSEES - REQUEST FOR ADDITIONAL INFORMATION -SMALL BREAK LOCA November 21, 1979 Mr. James H. Taylor Mr. R. C, Arnold Manager, Licensing Senior Vice President Babcock & Wilcox Company Metropolitan Edison Company Power Generation Group 260 Cherry Hill Road P. 0. Box 1260 Lynchburg, Virginia 24505 PrlpnNwJre 75 Mr. William 0. Parker, Jr.
Mr. J. G. Herbein Vice President -
Steam Production Vice President Duke Power Company Metropolitan Edison Company P. 0. Box 2178 P. 0. Box 480 422 South Church St.
Middletown, PA 17057 Charlotte, North Carolina 28242 Mr. W. P. Stewart Vnager, Nuclear Operations Florida Power Corporation P. 0. Box 14042, Mail Stop C-4 St. Petersburg, Florida 33733 Mr. J. J. Mattimoe Assistant General Manager and Chief Engineer Sacramento Municipal Utility District 6201 S Street Sacramento, California 95813 Mr. William Cavanaugh, III Vice President, Generation and Construction Arkansas Power & Light Company P. 0. Box 551 Little Rock, Arkansas 72203 Mr. Lowell E. Roe Mr. Ted Myers Vice President, Facilities Licensing Engineer Development Toledo'Edison Company Toledo Edison Company Edison Plaza Edison Plaza 300 Madison Avenue 300 Madison Avenue Toledo, Ohio 43652 Toledo, Ohio 43652
Request for Additional Information:
Small Break Loss-of-Coolant Accident
- 1. Transitions from solid natural circulation to reflux boiling and back to solid natural circulation may cause slug flow in the hot leg piping. By use of analysis and/or experiment, address the mechanical effects of the induced slug flow on steam generator tubes.
- 2. How are the HPSI pumps protected against deadheading if the system repressurizes? If operator action is required, show that there is sufficient time for operator response. How is this covered in guide lines for emergency procedures? (Applicable to Davis-Besse 1 only)
- 3. Evaluate the impact.of RCP seal.damage and leakage due to loss of seal cooling on loss of offsite power. How long can the RCP seals sustain loss of cooling without damage?