ML20027E147
| ML20027E147 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry |
| Issue date: | 10/26/1982 |
| From: | Vassallo D Office of Nuclear Reactor Regulation |
| To: | Parris H TENNESSEE VALLEY AUTHORITY |
| References | |
| NUDOCS 8211120142 | |
| Download: ML20027E147 (3) | |
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Distribution:
Docket File NRC PDR Docket Nos. 50-259 Local PDR OCT 2 61982 ORB #2 Rdg f
50-260 4
50-296 DEisenhut OELD ELJordan RJClark Mr. !! ugh G. Parris SNorris l
Manager of Power NSIC Tennessee Valley Authority Jf1 Taylor 500 A Chestnut Street, Tower II ACRS (10)
Chattanooga, Tennessee 37401 JHeltemes T. Hambach
Dear Mr. Parris:
T. Chan C9
Subject:
10 CFR 50 Appendix R.Section III.G Re:
Browns Ferry Nuclear Plant Units 1, 2 and 3 Reference is made to your submittal of June 30, 1982 presenting your safe shutdown analysis and describing the modifications which you have identi-fied as necessary to bring Browns Ferry Units 1, 2 and 3 into compliance with 10 CFR 50 Appendix R Section III.G. We have determined that we need 3
the additional information identified in the enclosure to this letter as part of our review. We would appreciate a response within 30 days of receipt of this letter.
This request for additional information is specific to one licensee. The reporting and/or recordkeeping requirements contained in this letter effect 4
fewer than ten respondents; therefore OMB clearance is not required under P.L.96-511.
Sincerely.
Origin:1eigned by D. B.Va::cIlo Domenic B. Vassallo, Chief Operating Reactors Branch #2 Division of Licensing I
Enclosure:
Request for Additional Information cc w/ encl:
j See next page j
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l NRC FORM 318 (10-80) NRCM oua OFFICIAL RECORD COPY usom mi-meo
Mr. Hugh G. Parris CC:
H. S. Sanger, Jr.', Esquire U. S. Environmental Protection General Counsel Agency Tennessee Valley Authority Region IV Office 400 Commerce Avenue Regional Radiation Representative E llB 33C 345 Courtland Street Knoxville, Tennessee 37902 Atlanta, Georgia 30308 Mr. Ron Rogers Resident Inspector Tennessee Valley Authority U. S. Nuclear Regulatory Commission 400 Chestnut Street, Tower II Route 2, Box 311 Chattanooga, Tennessee 37401 Athens, Alabama 35611 Mr. Charles R. Christopher Mr. John F. Cox Chairman, Limestone County Commission Tennessee Valley Authority P. O. Box 188 W9-D 207C Athens, Alabama 35611 400 Co6merce Avenue Knoxville, Tennessee 37902 Ira L. Myers, M.D.
State Health Officer George Jones State Department of Public Health Tennessee Valley Authority State Office Building P. O. Box 2000 Montgomery, Alabama 36104 Decatur, Alabama 35602 Mr. H. N. Culver Mr. Oliver Havens 249A HSD U.S. Nuclear. Regulatory Commission 400 Ccamerce Avenue Reactor Training Center Tennessee Valley Authority Osborne Office Center, Suite 200 Knoxville Tennessee 37902 Chattanooga, Tennessee 37411 l
James P. O'Reilly Regional Administrator, Region II l
U.S. Nuclear Regulatory Commission 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 e
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Request for Additional Information Post Fire Safe Shutdown Capability Browns Ferry Units 1, 2 and 3 Docket Nos. 50-259, 50-260 and 50-296 1.
In your proposed method of alternate safe shutdown, a) how much of the core will be uncovered, and for how long? How does this compare with the extent of core uncovery using normal shutdown facilities.
b) What is the predicted peak torus water temperature?
2.
Will the proposed addition of manual safety relief valve controls to the new backup control panel preclude spurious SRV operation as a result of a fire in the Al, C1, and El shutdown board rooms?
3.
Have the following systems been considered in the alternate safe shutdown analysis? If not, provide justification for not including
- them, a) HPCI or RCIC b) Emergency Diesel Generators 4
Are the following process instrum'entation parameters available at the backup control station?
a) Torus Temperature and Level b) Condensate Storage Tank Level 5.
For the mechanical shutdown syste"is, have you considered the possibility of one pump in any system being out of service for maintenance at the outset of the fire? If not, provide justification for your basis.
6.
In your submittal, sheet 4-84 is not consistent with sheets 4-85 and 4-86.
It appears that information is missing.
7.
On pages 4-111 and 4-112, you state that new alternate power supply breakers may be required.for the 480 volt reactor MOV board B and l
I&C power for shutdown and battery boards. What is the status of this potential change?
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