ML18025B966
| ML18025B966 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 04/22/1983 |
| From: | Mills L TENNESSEE VALLEY AUTHORITY |
| To: | Harold Denton Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.A.1.3, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.K.3.03, TASK-2.K.3.13, TASK-2.K.3.15, TASK-2.K.3.19, TASK-2.K.3.22, TASK-2.K.3.27, TASK-2.K.3.45, TASK-TM GL-83-02, GL-83-2, NUDOCS 8304290029 | |
| Download: ML18025B966 (7) | |
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'CCESSION NBR:8304290029 DOC,DATE: 83/04/22 NOTARIZED:
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FACIL:50 259 Browns Ferry Nuclear Power-Stationi Unit 1E Tennessee 05030259 50 260 Browns Ferry Nuclear Power Station< Unit 2i Tennessee 002 50 296 Browns'erry tVuclear Power StationE Unit 3i Tennessee 50052 AUTH,NAME AUTHOR AF F ILIATION MILLSEL,M, Tennessee Valley Authority REC IP, NAME RECIPIENT AFFILIATIOlV DENTONEH ~ RE Office of Nuclear Reactor Regulationi Director SUBJECT; Forwards response to Generic Ltr 83-02 re Tech Specs required by NUREG"0737 'ech Specs incorporating qualificationitraining L on-duty requirements for shift tecllnical advisors issued on 810718.
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TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 400 Chestnut Street Tower II April 22, 1983 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 By letter from D. G. Eisenhut to All BWR Licensees dated January 10, 1983 (Generic Letter No. 83-02) we were requested to submit technical specifications as required by certain NUREG-0737 items.
Enclosed is our response to the NUREG-0737 items listed in Enclosure 1 of the generic letter for the Browns Ferry Nuclear Plant.
Very truly yours, TENNESSEE VALLEY AUTHORITY Q. hq.
L. M. Mills, Ma ager Nuclear Licensing Subscribed an/ sworn t before me ttts ~tn/'day of'.
1983.
I 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, Suite 2900 Atlanta, Georgia 30303 Mr. R. J. Clark Browns Ferry Project Manager U.S. Nuclear Regulatory Commission 7920 Norfolk Avenue
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ENCLOSURE
'RES NSE TO GENERIC LETTER NO. 83>>02 DATED JANUARY 10, 1983 BROWNS FERRY NUCLEAR PLANT STA Training (1.A.1.1.3)
Technical specifications incorporating the qualification, training, and on-duty requirements of the shift technical advisors were approved and issued on July 18, 1981.
2.
Limit Overtime (I.A.1.3)
In a letter from T. A. Ippolito to H. G. Parris dated December 8,
- 1981, the TVA policy for limitation of overtime was found acceptable.
TVA is in the process of updating this policy to more generally meet the revised guidelines provided in June 15, 1982 commission policy sentence (generic letter 82-12).
We do not believe. that including our administratively controlled overtime limits in the technical specifications will have any impact on safe plant operation.
Consequently, we do not plan to submit technical specifications.
4 3.
Dedicated Hydrogen Penetrations (II.E.4. 1)
Technical specifications are to be submitted as appropriate when modifications are performed.
4.
Containment Pressure Setpoints (ZI.E.4.2.5)
Justification for not changing the setpoint was provided'n TVA letters from L. M. Mills to H. R. Denton dated December 23, 1980 and August 10, 1981.
No further actions are required.
5.
Containment Purge Valves (II.E.4.2.6)
As noted in enclosure 1 to generic letter 83-02, the technical specifications for this item are being handled separately.
6.
Radiation Signal on Purge Valves (ZI.E.4.2.7)
Technical resolution of this item is not completed; therefore, technical specifications are not required.
7.
Reporting SRV Failures and Challenges (ZI.K.3.3)
TVA anticipates submitting technical specification changes that will include reporting of SRV challenges in the annual operating reporting section in July 1983. It is our belief that section 6.7.2 (reportable occurrences) of the Browns Ferry technical specification already meets the reporting requirement for SRV failures.
8.
RCIC Restar t and RCIC Suction - (II.K.3.13, II.K.3.22) 1.
Appropriate technical specifications covering the RCIC restart will be submitted after modifications are complete.
2.
Technical specifications are not required since the addition of an automatic switchover of RCIC suction is believed to be unnecessary as
.discussed in TVA letter from L. M. Mills to H. R. Denton dated December 23, 1980.
9.
Isolation of HPCI and RCIC Modifications (II.K.3.15)
Browns Ferry units 2 and 3 technical specifications were issued in amendments 85 (issued March 11, 1983) and 51 (issued March 29, 1982),
respectively.
Unit 1 technical specifications will be submitted after modifications are complete.
10.
Interlock on Recirculation Pump Loops (II.K.3.19)
NA - Browns Ferry is a get pump plant.
11.
Common Reference Level (II.K.3.27)
NA - Browns Ferry technical specifi.cations do not contain a figure defining reactor water levels.
12.
Manual Depressurization (II.K.3.45)
NA - Staff does not require any modification in plant design.
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