ML18026A905
| ML18026A905 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 03/07/1984 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-2.B.1, TASK-2.B.3, TASK-2.F.1, TASK-3.D.3.4, TASK-TM GL-83-36, NUDOCS 8403130007 | |
| Download: ML18026A905 (7) | |
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REGULATORYlFORMATION DISTRIBUTION S'EM (RIDS) 7
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ACCESSION NBR:8403130007 DOC ~ DATE: 84/03/07 NOTARIZED:
YES DOCKET FACIL:50 259 Drowns Ferry Nuclear Power Stations Unit 1< Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station~
Unit 2E Tennessee 05000260 50 296 Browns Ferry Nuclear Power Stations Unit 3~ Tennessee 05000296 AUTHNAME AUTHOR AFFILIATION MILLSgL ~ H, Tennessee Val l ey Author i ty REC IP ~ NAME RECIPIENT AFFILIATION DENTONgH ~ R+
Office of Nuclear Reactor Regulationg Director
SUBJECT:
Forwards response to Generic Ltr 83-36 re NUREG 0737 Tech Specs'ISTRIBUTION CODE A046S COPIES RECEIVED LTR ENCL
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TITLE; OR Submittal:
TMI Action Plan Rgmt NUREG-0737 8
NUREG-0660 NOTES:NHSS/FCAF icy, 1cy NMSS/FCAF/PH, NHSS/FCAF icy, icy NMSS/FCAF/PH, NHSS/FCAF 1cy, 'icy NHSS/FCAF/PH, 05000259 05000260 05000?96 REC IPIENT ID CODE/NAME, NRR ORB2 BC 01 COPIES LTTR ENCL 7
7 RECIPIENT ID CODE/NAME COPIES LTTR ENCL 1
0 3
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1 1
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1 INTERNAL: ELD/HDS4 IE/DEPER/EPB NRR ERICKSON' NRR/DHFS DEPY29 NRR/DL/ORAB 18 NRR/DS I/AEB AB G
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LTTR 43 ENCL 42
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TENNESSEE YALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II March 7, 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. 50-259 50-260 50-296 Generic Letter No. 83-36 dated November 1,
1983 provided guidance and model technical specifications for certain item numbers of NUREG-0737.
The generic letter requested that licensees review their plant's technical specifications for consistency with the model and submit application for license amendment if necessary.
Enclosed is the response for the Browns Ferry Nuclear Plant units 1, 2, and 3.
If you have any questions concerning this information, please get in touch with us through the Browns Ferry Project Manager.
Very truly yours, TENNESSEE VALLEY AUTHORITY Sgbscribe sworn to efor e me this day of L. M. Mills, anager Nuclear Licensing 1984.
Notary Public My Commission Expires Enclosure cc (Enclosure):
U.S. Nuclear Regulatory Commission Region II ATTN:
James P. O'Reilly, Regional Administrator 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30303 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
- Bethesda, Maryland 20814 eyp3~
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ENCLOSURE
Response
to Generic Letter No. 83-36 NUREG-0737 TECHNICAL SPECIFICATION Br owns Ferry Nuclear Plant
Reference:
Letter from L. M. Mills to H. R. Denton dated January 23, 1984 (TVA BFNP TS 195) 1.
Reactor Coolant S stem Vents (II.B.1)
N/A - Browns Ferry does not have isolation condensers.
2.
Postaccident Sam lin (II.B.3)
Postaccident sampling at Browns Ferry has not yet been implemented.
In a letter from L. M. Mills to H. R. Denton dated June 28,
- 1982, a
schedule for outage-related work was identified.
When the modifications are complete and the PASF operational, an administrative procedure will be established for PASF operations.
This procedure will then be referenced in the administrative controls section of the technical specifications.
3.
Noble Gas Effluent Monitors (II.F. 1. 1)
Noble gas effluent monitors have not yet been installed at Browns Ferry.
When they are installed, technical specifications for this equipment will be included in each respective reload technical specification submittal.
4.
Sam lin and Anal sis of Plant Effluents (XI.F.1.2)
This item has not yet been implemented at Browns Ferry.
When it is implemented, proposed technical specification revisions will be included in each respective reload technical specification submittal.
5.
Containment Hi h-Ran e Radiation Monitors (II.F.1.3)
Portions of the containment high-range radiation monitoring system were installed on unit' during the reload' outage.
No technical specifications were submitted because the modifications were not completed.
When the modifications for this system are completed on each unit, appropriate technical specification revisions will be submitt'ed.
6.
Containment Pressure Monitor (II.F.1.4)
Technical specifications were submitted for unit 1 on July 13, 1983, in the reload submittal.
Revisions for unit 2 will be submitted in the next reload submittal.
Appropriate technical specifications for unit 3 were included in the referenced letter.
7.
Containment Mater Level Monitor (II.F.1.5)
Technical specifications were submitted for unit 1 on July 13, 1983, in the reload submittal.
Revisions for unit 2 will be submitted in the next reload submittal.
Revisions for unit 3 were included in the referenced letter.
8.
Containment H dro en Monitor (II.F.1.6)
Browns Ferry units 1, 2, and 3 currently have adequate technical specifications on the containment hydrogen monitors.
9.
Control Room Habitabilit Re uirements (III.D.3.4)
In the D. B. Vassallo, NRC, letter to H. G. Parris dated August 30,
- 1982, NRC concluded that Br owns Ferry's current configuration meets the requirements of item III.D.3.4.
Table 3.2.G of the technical specifications lists the control room isolation instrumentation; therefore, no revisions are required.
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