ML20077K557

Forwards List of Licensing Items Requiring NRC Approval in 1983

ML20077K557
Person / Time
Site:	Farley
Issue date:	01/04/1983
From:	Clayton F ALABAMA POWER CO.
To:	Varga S Office of Nuclear Reactor Regulation
References
NUDOCS 8301130113
Download: ML20077K557 (9)

Text

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1 Malling Address

• Alibim2 Power CompIny 600 North 18th Street Post Offce Dox 2H1 Birmingham, Alabama 35291 Telephone 205 783-0081 F. L Clayton, Jr.

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AlabamaPower thesouthem electnc spStem January 4,1983 1

Docket Nos. 50-348 50-364 l

l Director of Nuclear Reactor Regulation l

U. S. Nuclear Regulatory Commission l

Washington, D. C.

20555 Attention:

Mr. S. A. Varga l

Joseph M. Farley Nuclear Plant - Units 1 and 2 Licensing Items Requiring NRC Approva s in 1983 Gentlemen:

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Attached is a list of identified licensing items for NRC review and approval in 1983.

Some of these items have been sub-mitted to the NRC and others will be transmitted in the future.

For all items the actual or projected Al,abama Power submittal date and the requested NRC approval date are delineated.

Other changes to technical specifications / licenses may be required during 1983 due to unforeseen 6 vents.

It should be noted that these unforeseen changes may be of either temporary or permanent nature based on the particular circumstances.

Alabama Power considers each of the attached items critical to either the operation or license compliance of the Farley Nuclear Plant and should not be delayed unless mandated by other issues subsequent to this letter.

This schedule has been discussed with Mr. E. A. Reeves, the Farley Nuclear Plant NRC Project Manager. It is requested that the appropriate scheduling arrangements be made for NRC review of the 0

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Mr. S. A. Varga January 4,1983 Director of Nuclear Reactor Regulation Page 2 U. S. Nuclear Regulatory Commission i

attached items.

Alabama Power Company has committed resources to support the resolution of these items.

Yours very truly, i

. L. Clayton J r.

F LCJ r/BDM:jc-D33 Attachment cc:

Mr. R. A. Thomas Mr. G. F. Trowbridge Mr. J. P. O'Reilly Mr. E. A. Reeves Mr. W. H. Bradford i

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ATTA090lT LICD61E ITB6 IE)JIRIE NIC APPIWWE. IN 198 Actual */ Prgnaad Ra9mted MIC Item APCo Submittal Date Ayrtwal Date Cemets

1. Movable Control Rod Asserblies for FNP 1 and 2 02-22-8 09-01-8 Remves the six hour require 7ent to obtain Hot Standby for (T.S.3/4.1.3) non-trip conditions.

2. Charcoal Filters for FrP 1 and 2 (T.S. 4.7.7, 03-01-0 09-01-8 Clarifies the testing procedures used for diarcoal filters by 4.7.8and4.9.14) specifying efficiencies to te used when testing and corrects adninistrative errors.

3. River Water System for FrP 1 and 2 (T.S. 3/4.7.5) 12-30-82*

07-01-83 Deletes the river water system frun the technical specifica-tions. Sare letter as Iten 4.

4. Diesel Geneator Overload Test for FNP 1 and 2 0%03-82*

07-01-83 Reduces the surveillance load test requirements to prevent (T.S.4.8.1.1.2.c.5)

(original sutraittal) potential diesel damage frm current testing requirements.

12-30-82* (sub-Same letter as Iten 3.

sequent sutxnittal)

5. BIT Reduction for FrP 1 and 2 (T.S. 3/4.3.4) 12-30-82*

03-31-83 Reduces boron concentration in the boron irdection tank to zero ppm. Required die date to prment unnecessary batching of the tank *ich could chlay scheduled restart of the mit.

6. Turbine Valve Surveillance for FrP 2 (T.S.

10-08-82*

12-01-82 Deleted requirement of turbine overspeed protection testing.

3/4.3.4)

Required due date to preclude power reduction to conduct tests.

ATTMMENI LICDISIE ITEMS IIESIIRIIG NC #Pfl0tAL D1123 Actial*/Ponpnuwt Reg W NC Iten AFCo Sibuittal Drte Apprwal Dite Omments

7. RCS Pressure Isolation Valves for FfP 1 and 2 08-10L-82*(Original 09-21-82 Incorporates Unit 1 criteria for leak testing of mactor (T.S.3/4.4.7.2and3/4.4.7.3) submittal) -

(Original coolant systen isolatim valves into Unit 2 specificatims.

12-23-82*(Additional request)

Deletes paragraph 4.4.7.3.2 for Units 1 and 2.

submittal) 07-01-83

8. ftchanical Snubber Functional Test Exerption 11-05-82*

12-01-82 Requests mechanical snubber quantitative fmctional testing for FfP 1 (T.S. 4.7.9.e) requirement be changed fmn fourth mfueling outage mtil the fifth refueling outage due to mavailability of mquimd testing equipment. Lack of change old delay scheduled restart of the mit. The fourth refueling outage is scheduled to begin January 14,1983.

9. Waste Gas Hydmgen/0xygen Analyzers for FTP 1 and 06-01-83 12-01-83 Requests the requimnent of cparterly channel calibrations and 2(T.S. Table 4.3-9) mmthly functional tests for the este gas systen be clunged to annually.

10. ISI/IST Licensing Program:

a. Unit 1 Inservice Inspection Progran for 04-17-81*

07-01-83 Requests relief fron the closure head clad inspection.

ASK Code Class 1 and 2 Cmponents b.

Anendrent to Unit 1 ISI Progran for ASK 01-12-83 07-01-83 Addendun to cover additional clad patch problens.

Code Class 1 and 2 Cotponents

c. Relief for hydrus on ISI frogran 01-14-83 07-01-83 Requests hydros relief.

d.

IST Progran Unit 2 Revision 2 08-06-82*

07-01-83 Requests valve stroke relief.

e.

IST Progran, Unit 1 Revision 4 10-25-82*

01-07-83 Requests valve stroke relief. Required due date to reduce likelihood of plant transients following startup fmn the fourth refueling outage, scheduled to begin January 14, 1983.

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ATTMMENT LICENSIE UDES IElllIRIE NC JFPIGAL IN 19E0 Actual */Ponprmt ilm=d:ari MC Itan APCo Sd mittal Dste Apprwal Ihte Ommunts

11. Spmt Fuel Pool Storage Additions for Ffe 1 03-19-82*

11-01-82 Increases storage capacity of spent fuel fim 675 to 1407 locaticns.

12. Change 18 Month Interval to Refueling 04-01-83 10-01-83 Change is necessary to nuke surveillance intervals (Dnsistent with new 18 month fuel cycle outage schedule as opposed to arbitrary time interval.

13. Meteorological Tower Surveillance for FTP 1 and 2 02-01-83 08-01-83 Mds backup tower in response to t0 REG-0737 III A.2.2. to (T.S.3.38and4.35) preclude report issuance cn failure of primary tower instru-ments.

14. In-Core Thinbles for FrP 1 and 2 (T.S. 3.3.3.2)

See Cm ments See Coments APCo will advise the PRC by 03-01-83 of actim to be taken.

15. Safety Evaluations for Next Fuel Reloads :

a. Unit 1 Upflow Fbdificati(n 08-16-82*

N/A Mvise IRC of Unit I reactor vessel internal nodifications.

b. Unit 1 Cycle 5 03-14-83 N/A Mvise NRC of Unit 1 Cycle 5 core desip status.

c. I' nit 2 Cycle 318 Month Fuel Cycle 09-01-83 N/A Mvise NRC of Unit 2. Cycle 3 core desim status.

ATTAD90fr LI NSIE ITD6 REI)JIRI!G MC APPRDWAL IN 123 Actual */Pnymrt Rupestai IRC Item AFCo Sibuittal Date Appmel Date Omments

16. F4H and Positive Moderator Tamerature See Cmments See Coments APCo will advise the tRC by 03-01-83 of action to be taken.

Coefficient

17. Contairment Spray 04-01-83 10-01-83 Incorporates 5% pmp head nanjin to allow for potential pmp degradation.

18. Tectnical Specificatim Optimization Generic review to begin in 1983.

Westinghouse Owners Group

19. Safety Related Battery Changes 04-15-83 10-15-83 Reflects accepted industry and vendor practices.

20. Rod Sep Test During Low Power Physics Testing See Conments See Cm ments Approval of this generic issue (WCAP 9863/9864) by the tRC is anticipated by Feburary 25,1983. Provided generic approval is granted, APCo will utilize the rod swap technique for the thit 1, Cycle 5 reload and inform the tRC as pirt of the previously scheduled 50.59 sutnittal. If generic approval is delayed beyond February 25,1983, /PCo will, by Mirch 1,1983, request interim approval by April 1,1983 for Unit 1 Cycle 5 only.

21. Rod Drop Timing Test During Low Power Physics See Cm ments See Cmments APCo will advise the PRC by 03-01-83 of action to be taken.

Testing

A1TA09 0 E LICDISIE 16 IE)lIRIE E #PInfAL IN 1983 Actual /Ponpnawf AP00 Rapired E Itse Siemittal Date Approval Date Coments

22. toto Rod Control Above 90 % Poer for Unit 2, 03-01-83 N/A Advise NRC of application for new pmposed md dmp methodology 1

Cycle 2 and Unit 1, Cycle 5 to Farley. New nethodology will be included in Unit 1, C)cle 5 mload analysis and has been included in Unit 2 Cycle 2 mload analysis. This date is dependent upon MC approval of the Westinghouse mport in January 1983.

23. Unit 2 Licensing Deletion Amen &ent 01-12-83 N/A Close out license conditions discussed in APCo's 10-19-82 Clarification Letter letter.

24. FSARlbdate 07-01-83 WA Pmvide NRC with required annual update of the Farley FSAR.

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ATTAD H NT LIENSI!G ITD6 EINIRI!G NIC APPIOfAL IN 198 I

i Actual */Fi W R m m ted NIC Comets APCo Sutmittal Date Tw g,al Date Itse

25. A&iinistrative Changes Changs "bmaker" to disconnect &vice for clarification 02-01-83 09-01-8 Acctrulator and ECCS Subsysts for FtP 1 and 2 purposes.

a.

(T.S. 4.5.1.1.(c) and 4.5.2.(a))

Requires FTP technical specification chan@ to incorporate 10-25-82*

09-01-8 Generic Letter 82-17 on Audit of Energency Plan an audit of eergency pmpartdiess program every 12 ronths b.

for FfP 1 and 2 (T.S. 6.5.2.8.e) vice eery 24 ronths.

Modify the pmsent list of safety mlated snubbers to reflect Of>-01-83 09 8 Mechanical and Hydraulic Snubber Lists for FNP 1 actual assunptions nede in seismic safety-related analyses.

c.

and Hydraulic Snubber List for FtP 2 (T.S. Table 3.7-46)

Reflects actual plant desigi and other adninistrative chan@s.

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i 03-01-8 09-01-83

d. Adainistrative Changes for FtP 1 and 2:

Iten 5 change will paclut sicultaneous shutdown of both I

1) Fim Detectors Table 3.3-12 units to perform service water tuttery test.

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2) RfR Isolation 4.5.2.d.1

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3) River Water Surv 3/4.7.5 l

4) Yard Fire Hydrant Table 3.7-7 i

5) Service Water Battery 4.8.2.5.2(d)

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6) Organization Chart Figare 6.2-2 1

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LI NSIE ITB6 EQlIRI!G NtC APPIOR. IN 198 Actual */Prgased Rwp M MIC Item APCo Sutwittal Date Apprael Date r==rits

25. Abinistrative Changes (continued)

e. Unit 2 Pmssum Sensor Table (T.S. 3.3.3.7) 03-01-8 09 8 Reflects actual plant desim.

f. linit 1 Refueling Outage Change: Contaiment 03-01-83 09 8 Reflects new plant &sim.

Vent g.

Turtine Building Hydraulic Snubbers for FNP 2 12-10-82*

09-01-8 Reflects actual plant &sim by &leting non safety-related snubbers.

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Incorporation of Licensing Requirwents 11-24-82*

09-01-83 for FfP 2

1) FNP 2 License Condition 2.C.(17) -

Replaces the 18 inch mini-purge valves with the new 8 inch Containment Vent Line vents.

2) Mechanical Snubber List for FNP 2 (T.S.

Adds the list of safety related nechanical snubbers.

Table 3.7-4b)

3) FtP 2 License Condition 2.C.(19)(b) -

Containment Overcurrent Protection Adds the list of Containment Overcurrent Protection & vices.

i. Organization Change to Offsite Managenent for 11-16-82*

09-01-83 Changes the corporate organization far the Nuclear Generation FfP 1 and 2 Department.

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