ML20054D688
| ML20054D688 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 04/16/1982 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0737, RTR-NUREG-737, TASK-1.A.3.1, TASK-2.B.2, TASK-2.B.3, TASK-2.B.4, TASK-2.E.1.2, TASK-2.E.4.2, TASK-2.F.1, TASK-TM GL-82-05, GL-82-5, NUDOCS 8204230277 | |
| Download: ML20054D688 (4) | |
Text
Malling Addt:ss Alabama Power Company 600 North 18th Street Post Office Box 2641 Birmingham, Alabama 35291 Telephone 205 783-6081 F. L Clayton, Jr.
Senior Vice President Mahanla POh'Cr Fhntodge Building ite suutten ekxtnc splem April 16, 1982 s
Docket Nos. 50-348 50-364 8
g RECEIVED t. APR 221gg i)
Director, Nuclear Reactor Regulation
" Q W g mens U. S. Nuclear Regulatory Commission T,
noc ff Washington, D. C.
20555 9
Attention:
Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Units 1 and 2 Post - TMI Requirements (Generic Letter No. 82-05)
Gentlemen:
In response to your letter of March 17, 1982, enclosed is the status of the NUREG-0737 items requiring licensee response.
If you have any questions, please advise.
Yours very trul l l
. L. Clayton, Jr.
/
FLCJr/ JAR:jc-D7 Enclosure cc:
Mr. R. A. Thomas (w/ enclosure)
SWORN TO AND SUBSCRIBED BEFORE ME Mr. G. F. Trowbridge (w/ enclosure)
THIS /GdDAY 0F g pf, /, 1932.
Mr. J. P. O'Reilly (w/ enclosure)
Mr. E. A. Reeves (w/ enclosure)
Mr. W. H. Bradford (w/ enclosure)
'WA h$1"d> %//
~ '~ " Notary Piiblic
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My Commission Expires:
Jn/77, ??
8204280 XT-l j
ENCLOSURE Status of NUREG-0737 Items Requiring Licensee Response Item Title APCo Response I.A.3.1 Simulator Exams Alabama Power Company's (include simulator letters of 1-14-81, 2-9-81 exams in licensing and 10-6-81 to the NRC pro-examinations).
vided APCo's implementation schedule, justification and demonstration of the need for that schedule, and descrip-tion of interim compensatory measures.
This schedule calls for plant specific simulator examinations by July 1983 with interim non-plant specific examinations now being utilized.
II.B.2 Plant Shielding Alabama Power Company's let-(modify facility to ters of 2-23-81, 12-22-81 and provide access to 2-11-82 to the NRC provided vital areas under APCo's completion status for accident conditions.)
this requirement.
The elec-trical disconnect devices for Units 1 and 2 and the shield-ing door for Unit 2 are the only remaining modifications to be made.
The electrical disconnect devices on Unit I will be installed and made operational during the fourth refueling outage currently scheduled to begin in January 1983; the Unit 2 electrical disconnect devices will be installed and made operational during the first refueling outage currently scheduled to begin in November 1982.
The Unit 2 shielding door is onsite and is scheduled to be installed by 5-15-82.
The above refer-enced letters provided the NRC with the justification and need for the scheduled installations.
No interim compensatory actions are-re-quired for this item.
On 3-31-82 the NRC confirmed the Unit 2 schedule for this item by granting a license exten-sion until the first refuel-ing outage.
t
Status of NUREG-0737 Items Page 2 Requiring Licensee Response Item Title APCo Response II.B.3 Postaccident This item was completed for Sampling (install Unit 1 by January 1, 1980 as upgraded post-stated in APCo's letter to accident sampling the NRC dated 12-31-79.
Unit capability) 2 was completed prior to ex-ceeding 5% power in May 1981.
II.B.4 Training for This item was completed for Mitigating Core Units 1 and 2 in May 1981.
Damage (complete II.E.1.2 Auxiliary Feedwater Alabama Power Company's let-Initiation and ters of 7-1-81 and 12-22-81 Flow Indicator established the completion (modi fy instrumen-dates for these modifications tation to level of to be the fourth refueling safety grade) outage for Unit 1 and the first refueling outage for Unit 2.
The justification and need for this schedule was also provided in these responses.
No compensatory measures are required for this item.
f II.E.4.2 Containment The containment pressure set-Isolation Depend-point was lowered as stated 4
ability (Part 5 -
in APCo's letters to the NRC lower containment dated 2-13-81 and 9-9-81.
pressure setpoint The Units 1 and 2 containment to level compatible setpoint pressure was lowered with normal op-to 4.0 psig in June 1981.
As eration.
Part 7 -
stated in APCo's letter to isolate purge and the NRC dated 1-14-81, the vent valves on containment purge and exhaust radiation signal) valves, as presently i
designed, close on the receipt of a high radiation signal.
II.F.1 Accident Monitoring The required monitoring capa-1.
Install noble gas bility has been provided as effluent monitors.
stated in APCo's letters to the NRC dated 2-23-81 and 2.
Provide capability 12-22-81.
All requirements for ef fluent monitor-for this item for Units 1 and ing of iodine.
2 were met by 1-1-82.
1
Status of NUREG-0737 Items Page 3 Requiring Licensee Response Item Title APCo Response II.F.1 3.
Install in-containment continued radiation-level monitors 4.
Provide continuous indication of containment pressure.
5.
Provide continuous indication of water level 6.
Provide continuous in-dication of hydrogen concentration in containment.
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