ML18029A304
| ML18029A304 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 12/13/1984 |
| From: | Domer J TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.F.1, TASK-TM NUDOCS 8412180370 | |
| Download: ML18029A304 (8) | |
Text
REGULATORY 1NFORMATION DISTRIBUTION SY M (RIDS)
ACCESSION NBR; 8412180370, DOC ~ DATE: 84/12/15 NOTARIZED:
YES DOCKET FACIL:SO '260 Browns Ferry Nuclear Power Stations Un) t 2< Tennessee'5000260
,'50-296 Browns Ferry Nucl,ear Power Stations Unit 3~
Tennessee 05000296
'AUTH'AME AUTHOR AFFILIATION DOMERgJ ~
AD
'ennessee" Valley Authority
>REC IP ~ NAME<
RECIPIENT AFFILIATION DENTONiH ~ RE Office< of Nuclear Reactor< Regulationi Director
SUBJECT:
- Application for"amend to Licenses DPR 52 8 DPR-68ichanginp
'completion date of mods to provide monitoring capability for nobly gas p,iodine effluents-,w/local readout per NUREG 0737/
Items II.F,1, 1 8 II.F, F 1.Fee paid.
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TENNESSEE VALLEYAUTHORITY CHQ)A)OOGA. $E@ESSP 3'7401 December 13, 1984 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C.
20555
Dear Mr. Denton:
In the Matter of the Tennessee Valley Authority Docket Nos. 50-260 50-296 By J.
W. Hufham's letter to you dated November 28,
- 1984, we requested an extension of the deadline for NUREG-0737 items II.F. 1.1 and II.F. 1.2 from the Orders dated March 25, 1983 for the Browns Ferry Nuclear Plant units 2 and 3.
By letter from D. B. Vassallo to H. G. Parris dated December 7,
- 1984, we were informed that this request for Order extension must be handled as a request for license amendment.
Accordingly, we hereby request that the subject request for Order extension for Browns Ferry units 2 and 3 be reviewed as a proposed license amendment pursuant to 10 CFR 50.90.
A pr oposed determination of no significant hazards consideration required by 10 CFR 50.91(a)(1) is enclosed.
Enclosed is a check for the 4150 amendment fee required by 10 CFR Part 170. 12 If you have any questions, please get in touch with us through the Browns Ferry Project Manager.
Very truly yours, TENNESSEE VALL Y AUTHORITY
,Subscrib y@d sworn t me this
.~ day of ames A. Domer Nuclear Engineer before r
~ 1984.
Notary Public My Commission Expires 1.
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Mr. Harold R. Denton December 13, 1984 cc (Enclosure);
U.S. Nuclear Regulatory Commission Region II ATTN:
James P. O'Reilly, Regional Administrator 101 Marietta Street, Suite 2900 Atlanta, Georgia 30323 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
- Bethesda, Maryland 20814
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ENCLOSURE 10 CFR 50.91(a)(1)
DETERMINATION OF NO SIGNIFICANT HAZARDS SUPPORTING REQUEST FOR MODIFICATION OF ORDERS NUREG<<0737 ITEMS II.F. 1. 1 AND II.F. 1.2 BROWNS FERRY NUCLEAR PLANT Descri tion of Amendment Re uest Orders confirming commitments on post-TMI related issues (NUREG-0737) dated Mar ch 25, 1983, issued to the Tennessee Valley Authority (the licensee) required that the monitoring capability for noble gas and iodine effluents with local readout be provided by December 31, 1984, for Browns Ferry Nuclear Plant units 2 and 3.
The proposed amendment would change the date for completion of the modifications required to provide monitoring capability for noble gas and iodine effluents with local readout (NUREG-0737, Items II.F. 1. 1 and II.F. 1.2) for units 2 and 3.
The licensee's completion schedule for items II.F. 1. 1 and II.F.1.2 with local readout capability, units 2 and 3, would be revised to read "prior to unit 2 startup in cycle 6" instead of December 31, 1984.
Browns Ferry unit 2 is currently shutdown in its cycle 5 r efueling outage.
Basis for Pro osed No Si nificant Hazards Consideration Determination Under the Commission's regulations in 10 CFR 50.92, a proposed amendment involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not
( 1) involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. It is proposed that the amendment involves no significant hazards considerations for the following reasons.
The purpose of these modifications is to provide high level noble gas, iodine, and particulate effluent monitoring after an accident has occurred, and not to provide information necessary to prevent radioactive releases in excess of 10 CFR 100 limits for accidents analyzed in the FSAR.
Whether the monitors are installed before or after December 31, 1980 will have no effect on the probability or consequences of an accident previously evaluated, since the monitors are used solely for post;-accident; evaluations and do not affect any system used for shutting the reactor down, controlling reactivity, or cooling of the reactor vessel and internals.
Because the monitors do not affect any of these
- systems, their installation, or a delay in their installation, will not create the possibility for a new or different kind of accident.
Similarly, because the monitors do not affect any safety system a delay in their installation will not cause a reduction in any margin of safety.
Based on those reasons we believe that a change in the completion schedule for these items involves no significant hazards considerations.