ML20028B214
| ML20028B214 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 11/19/1982 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S NRC |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.1.1, TASK-1.A.1.3, TASK-2.E.1.1, TASK-2.E.1.2, TASK-2.E.4.1, TASK-2.E.4.2, TASK-2.K.2.08, TASK-2.K.2.13, TASK-2.K.3.03, TASK-2.K.3.12, TASK-TM GL-82-16, NUDOCS 8211300174 | |
| Download: ML20028B214 (3) | |
Text
Mailing Addr.ss Alabama Power Company 600 North 18th Street Post Office Box 2641 Birmingham. Alabama 35291 Telephone 205 783-6081 b
F. L. Clayton, Jr.
S O,'ol 3 % d*"'
AlabamaPower g
I Iff 50UttMJrn C LCffC System November 19, 1982 Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention:
Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Units 1 and 2 NUREG-0737 Technical Specifications (Generic Letter 82-16)
Gentlemen:
In accordance with Generic Letter No. 82-16, Alabama Power Company has reviewed the Joseph M. Farley Technical Specifications for Units 1 and 2 to determine whether they are consistent with the guidance provided.
The results of this review are attached and further action is not required.
If there are any questions, please advise.
Yours very truly, D
H F
. Clayto, J r.
FLCJr/GGY:jc-D30 Attachment-cc:
Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly
[{D8 Mr. E. A. Reeves Mr. W. H. Bradford F2113OO174 821119 '
~
PDR ADOCK 05000348 P
e ATTACHMENT RESPONSE TO GENERIC LETTER NO. 82-16 (1) STA Training (I.A.1.1.3)
The technical specification requirements in the NRC letter of July 2, 1980 were addressed in the original Unit 2 Technical Specifications and Amendment No. 25 to the Unit 1 Technical Specifications. No further action is required.
(2) Limit Overtime (I.A.1.3)
The technical specification requirements in NRC Generic Letter 82-12, dated June 15, 1982 were addressed in the APCo letter of August 8, 1982. As stated in that letter, APCo has complied with the requirements of NUREG-0737, Item I.A.1.3, such that a technical specification change is not required.
No further action is required.
(3) Short Term Auxiliary Feedwater System Evaluation (II.E.1.1)
The technical specification requirements in NUREG-0737, Item II.E.1.1, were addressed in the original Unit 1 and Unit 2 Technical Specifica-tions.
No further action is required.
(4) Safety Grade AFW System Initiation and Flow Indication (II.E.1.2)
The technical specification requirements in the NRC letter of July 2, 1980 were addressed in the original Unit 2 Technical Specifications and Amendment No. 25 to the Unit 1 Technical Specifications. No further action is required.
(5) Dedicated Hydrogen Penetrations (II.E.4.1)
The hydrogen recombiners at the Farley Nuclear Plant are internal to the containment building such that the requirements of NUREG-0737, Item II.E.4.1, are not applicable.
(6) Containment Pressure Setpoint (II.E.4.2.5)
The technical specification requirements in NUREG-0737, Item II.E.4.2.5, were addressed in the original Unit 2 Technical Specifications and Amendment No. 25 to the Unit 1 Technical Specifications. No further action is required.
(7) Containment Purge Valve (II.E.4.2.6)
The technical specification requirements in NUREG-0737, Item II.E.4.2.6, were addressed in the original Unit 2 Technical Specifications and in Amendment No. 26 to the Unit 1 Technical Specifications. No further action is required.
o Response to Generic Letter No. 82-16 Page 2 (8) Radiation Signal on Purge Valves (II.E.4.2.7)
The technical specification requirements in NUREG-0737, Item II.E.4.2.7, were addressed in the original Unit 1 and Unit 2 Technical Specifications.
No further action is rquired.
(9) Upgrade B&W AFW System (II.K.2.8)
Not applicable to Westinghouse PWRs.
(10) This item left blank in Generic Letter 82-16.
(11) B&W Thermal - Mechanical Report (II.K.2.13) 4 No technical specification changes are requi,ed to comply with NUREG-0737, Item II.K.2.13, for Westinghouse PWRs.
(12) Reporting SV and RV Failures and Challenges (II.K.3.3)
The technical specification requirements in NUREG-0737, Item II.K.3.3, were addressed in Amendment No. 26 to the Unit 1 Technical Specifica-tions and in the original Unit 2 Technical Specifications. No further action is required.
(13) Anticipatory Trip on Turbine Trip (II.K.3.12)
The technical specification requirements in NUREG-0737, Item II.K.3.12, were addressed in the original Unit 1 and Unit 2 Technical Specifica-tions.
No further action is required.
D-27
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