ML20054D688

Forwards Status of NUREG-0737,Items I.A.3.1,II.B.2,II.B.3, II.B.4,II.E.1.2,II.E.4.2 & II.F.1,in Response to NRC 820317 Ltr

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 Fhntodge Building Mahanla POh'Cr 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

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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.

• l Mr. J. P. O'Reilly (w/ enclosure) I 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:

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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.

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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-4 Isolation Depend- point was lowered as stated 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.

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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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