Letter Sequence Other |
|---|
TAC:59776, (Approved, Closed) TAC:59777, (Approved, Closed) TAC:59900, (Approved, Closed) TAC:59901, (Approved, Closed) TAC:59902, (Open) TAC:60075, (Approved, Closed) TAC:60287, (Approved, Closed) TAC:60288, () TAC:60289, (Approved, Closed) TAC:60290, (Approved, Closed) TAC:60291, (Approved, Closed) TAC:60292, () TAC:60293, (Approved, Closed) TAC:60294, (Approved, Closed) TAC:60355, (Approved, Closed) TAC:60356, (Approved, Closed) |
|
MONTHYEARML20133F8381985-08-31031 August 1985 Heatup & Cooldown Limit Curves for Alabama Power Co, Jm Farley Unit 2 Reactor Vessel Project stage: Other IR 05000348/19850361985-09-19019 September 1985 Insp Repts 50-348/85-36 & 50-364/85-36 on 850811-0910.No Violations or Deviations Noted.Major Areas Inspected: Licensee Action on Previous Enforcement Matters,Monthly Surveillance Observations,Monthly Maint Observation & LERs Project stage: Request ML20133F8351985-09-30030 September 1985 Proposed Tech Specs,Changing Table 4.4-5 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule,Figures 3.4-2 & 3.4-3 Re RCS Heatup & Cooldown Curves & Bases 3/4.4.10 Project stage: Other ML20133F7411985-09-30030 September 1985 Application for Amend to License NPF-8,changing Tech Spec Table 4.4-5 Re Reactor Vessel Matl Surveillance Program Withdrawal Schedule,Figures 3.4-2 & 3.4-3 Re RCS Heatup & Cooldown Curves & Bases 3/4.4.10.Fee Paid Project stage: Request ML20133J2801985-10-14014 October 1985 Forwards Three Addl Requests for Relief from Inservice Insp Program for ASME Code Class 1,2 & 3 Components Re Reactor Vessel Flange Ligaments & Visual Exam of Reactor Coolant Pump Casing Pressure Boundary Surfaces.Fee Paid Project stage: Other ML20138L2191985-10-21021 October 1985 Requests Assistance in Reviewing Encl Util 850919 Proposed Administrative Tech Spec Change,Implementing Listed Mgt Changes.Ser & SALP Input Requested by 851031 Project stage: Other ML20138N3581985-10-25025 October 1985 Application for Amend to License NPF-2,changing Tech Specs to Revise Heatup/Cooldown Curves to Extend Applicability to 24 Efpy.Fee Paid Project stage: Request ML20138N3751985-10-25025 October 1985 Proposed Tech Specs Revising Heatup/Cooldown Curves to Extend Applicability to 24 EFPY Project stage: Other ML20137S6411985-11-17017 November 1985 Proposed Changes to Tech Spec 4.2.4.2 & Action 2.d of Table 3.3-1 to Allow Full Core Flux Map for Verifying Indicated Quadrant Power Tilt Ratio When One ex-core Power Range Detector Channel Inoperable Project stage: Request ML20137H8371985-11-22022 November 1985 Application for Amends to Licenses NPF-2 & NPF-8,revising Note 9 of Tech Spec Table 4.3-1 to Require Clearing of Trip Signal Prior to P-9 Setpoint.Fee Paid Project stage: Request ML20137H8731985-11-22022 November 1985 Proposed Tech Spec Changes to Note 9 of Table 4.3-1, Requiring Clearing of Trip Signal Prior to P-9 Setpoint Project stage: Other ML20137S6241985-11-27027 November 1985 Application for Amends to Licenses NPF-2 & NPF-8 to Permit Full Core Flux Map for Verifying Indicated Quadrant Power Tilt Ratio When One ex-core Power Range Detector Channel Inoperable Project stage: Request ML20137K9071985-11-27027 November 1985 Forwards Summary of Activities Conducted Since 841130 Submittal & Schedule for Completing Remainder of Emergency Response Capability Integrated Implementation Plan Items. W/One Oversize Graphical Presentation of Plan & Schedule Project stage: Request ML20137S5391985-11-27027 November 1985 Proposed Tech Spec Changes,Eliminating Requirement to Shut Down Plant If Coolant Iodine Activity Above 1 Uci/G for Greater than 800 H in 12-month Period,Per Generic Ltr 85-19 Project stage: Other ML20137S5211985-11-27027 November 1985 Application for Amends to Licenses NPF-2 & NPF-8,eliminating Tech Spec Requirement to Shut Down Plant If Coolant Iodine Activity Above 1 Uci/G for Greater than 800 H Period in 12 Months,Per Generic Ltr 85-19.Fee Paid Project stage: Request ML20137U0111985-11-27027 November 1985 Application for Amends to Licenses NPF-2 & NPF-8,deleting Rod Bow Penalty from Tech Specs.Fee Paid Project stage: Request ML20137U0231985-11-27027 November 1985 Proposed Tech Spec Pages 3/4 2-8,3/4 2-10 & B3/4 2-4, Deleting Rod Bow Penalty Project stage: Other ML20138K9851985-12-0909 December 1985 Application for Amends to Licenses NPF-2 & NPF-8,revising Tech Specs to Incorporate Administrative Corrections Re Fire Protection.Fee Paid Project stage: Request ML20138L0261985-12-0909 December 1985 Proposed Tech Specs,Incorporating Administrative Corrections Re Fire Protection Project stage: Other ML20136H6711985-12-27027 December 1985 Forwards Safety Evaluation Granting Util 851014 Request for Exemption from Section XI Requirements Re Reactor Vessel Flange Ligaments & Insp of Internal Pressure Boundary Surfaces & Flange Bolts Project stage: Approval ML20136H6821985-12-27027 December 1985 Safety Evaluation Granting Relief from Certain Inservice Testing/Insp Requirements Re Reactor Vessel Flange Ligaments,Reactor Coolant Pump Casing Internal Surfaces & Flange Bolts Project stage: Approval ML20151X9321986-01-27027 January 1986 Amends 60 & 51 to Licenses NPF-2 & NPF-8,respectively, Revising Administrative Controls Section of Tech Specs to Reflect Titles of Onsite & Offsite Licensee Mgt Project stage: Other ML20151X9631986-01-27027 January 1986 Safety Evaluation Supporting Amends 60 & 51 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20151Z2551986-02-0707 February 1986 Forwards Proposed Schedules for Completion of License Amend Requests & Other NRC-related Submittals Project stage: Other ML20205J7041986-02-18018 February 1986 Application for Amends to Licenses NPF-2 & NPF-8, Supplementing 851209 Submittal,Proposing Administrative Tech Spec Changes Re Fire Detection Instrumentation.Significant Hazards Evaluations Encl Project stage: Supplement ML20155A3231986-02-28028 February 1986 Rev 1 to Heatup & Cooldown Limit Curves for Jm Farley Unit 2 Reactor Vessel Project stage: Other ML20199D8431986-03-14014 March 1986 Safety Evaluation Supporting Amends 61 & 52 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20199D8311986-03-14014 March 1986 Amends 61 & 52 to Licenses NPF-2 & NPF-8,respectively, Revising Tech Spec Surveillance Requirements for Quadrant Power Tilt Ratio,Allowing Use of Full Core Flux Map Using Two Sets of Four Symmetric Thimble Locations Project stage: Other ML20155A3001986-03-27027 March 1986 Proposed Tech Specs,Revising RCS Heatup & Cooldown Curves Project stage: Other ML20155A2731986-03-27027 March 1986 Suppl to 850930 Application for Amend to License NPF-8, Revising Tech Spec RCS Heatup & Cooldown Curves Per Rev 1 to Reg Guide 1.99.Rev 1 to WCAP-10910, Heatup & Cooldown Limit Curves... Encl Project stage: Request ML20141F6431986-04-11011 April 1986 Forwards Amended Significant Hazards Evaluation & Revised Tech Spec Pages Removing Rod Bow Penalty from Nuclear Enthalpy Hot Channel Factor,Per Util 851127 Request to Amend Licenses NPF-2 & NPF-8 Project stage: Other ML20203E0971986-04-15015 April 1986 Safety Evaluation Supporting Amends 62 & 53 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20203E0891986-04-15015 April 1986 Amends 62 & 53 to Licenses NPF-2 & NPF-8,respectively, Revising Tech Spec Table 4.3-1 Re Reactor Trip Sys Instrumentation Surveillance Requirements Project stage: Other ML20210K2611986-04-16016 April 1986 Amend 63 & 54 to Licenses NPF-2 & NPF-8,respectively, Deleting Tech Spec 3.4.9 Action Statement a Requiring Plant Shutdown When Coolant Activity Exceeds Cumulative Spiking Limit Project stage: Other ML20210K2731986-04-16016 April 1986 Safety Evaluation Supporting Amends 63 & 54 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20203N5891986-04-21021 April 1986 Amend 55 to License NPF-8,modifying Tech Spec Table 4.4-5 & Figures 3.4-2 & 3.4-3 Based on Results of Capsule U Reactor Vessel Surveillance Program Project stage: Other ML20203N6201986-04-21021 April 1986 Safety Evaluation Supporting Amend 55 to License NPF-8 Project stage: Approval ML20210P2881986-05-0707 May 1986 Corrected Tech Spec Page 3/4 4-6 from Amend 55 to License NPF-8 Re Analysis of Capsule U in Reactor Vessel Surveillance Program Project stage: Other ML20199B3691986-06-16016 June 1986 Notice of Violation of Antitrust License Condition 2,by Setting Unreasonable Terms & Conditions for Sale of Facility,Per Alabama Electric Cooperative,Inc 840629 Petition Project stage: Request ML20206J0861986-06-16016 June 1986 Amends 64 & 57 to Licenses NPF-2 & NPF-8,respectively, Modifying Tech Spec 3.2.3 to Delete Rod Bow Penalty & Deleting Tech Spec Figure 3.2-3 Project stage: Other ML20206F0871986-06-16016 June 1986 Forwards Questions on 851025 Application for Amend to License NPF-2 Re Proposed Heatup/Cooldown Curves to 24 Efpy. Request Being Held in Abeyance Pending Resolution of Concerns.Response Requested by 860630 Project stage: Other ML20206J0921986-06-16016 June 1986 Safety Evaluation Supporting Amends 64 & 57 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20210T5711986-06-30030 June 1986 Rev 2 to Heatup & Cooldown Limit Curves for Alabama Power Co,Joseph M Farley Unit 1 Reactor Vessel Project stage: Other ML20206R5321986-06-30030 June 1986 Responds to NRC 860616 Request for Addl Info Re 851025 Amend Request to Extend Applicability of Heatup & Cooldown Curves to 24 Efpy.Submittal Will Be Supplemented by Sept 1986 Project stage: Supplement ML20210T5251986-09-29029 September 1986 Suppl to 851025 Application for Amend to License NPF-2, Revising Heatup & Cooldown Curves to Extend Applicability from Existing 7 EFPY to New Limit of 16 EFPY Project stage: Request ML20210T5571986-09-29029 September 1986 Proposed Tech Specs,Revising Heatup & Cooldown Curves to Extend Applicability from Existing 7 EFPY to New Limit of 16 EFPY Project stage: Other ML20209E5981987-04-10010 April 1987 Safety Evaluation Supporting Amends 70 & 62 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20209E5631987-04-10010 April 1987 Amends 70 & 62 to Licenses NPF-2 & NPF-8,respectively, Involving Administrative Changes to Tech Specs,Including Correcting Fire Hose Station Designations & Hydrant Numbers & Correcting Size of mini-purge Valves in Ventilation Sys Project stage: Other ML20216E7401987-06-23023 June 1987 Safety Evaluation Supporting Amend 71 to License NPF-2 Project stage: Approval ML20216E6501987-06-23023 June 1987 Amend 71 to License NPF-2,revising Tech Spec Figures 3.4-2 & 3.4-3 to Reflect Heatup & Cooldown Limitations Based on Results of Analysis of Reactor Vessel Matl Surveillance Program Project stage: Other 1986-02-28
[Table View] |
Forwards Proposed Schedules for Completion of License Amend Requests & Other NRC-related Submittals| ML20151Z255 |
| Person / Time |
|---|
| Site: |
Farley  |
|---|
| Issue date: |
02/07/1986 |
|---|
| From: |
Mcdonald R ALABAMA POWER CO. |
|---|
| To: |
Rubenstein L Office of Nuclear Reactor Regulation |
|---|
| References |
|---|
| TAC-59776, TAC-59777, TAC-59900, TAC-59901, TAC-59902, TAC-60075, TAC-60287, TAC-60288, TAC-60289, TAC-60290, TAC-60291, TAC-60292, TAC-60293, TAC-60294, TAC-60355, TAC-60356, NUDOCS 8602140113 |
| Download: ML20151Z255 (7) |
|
Text
M' Mailing Address Alib1ma Pow 2r Comptny 600 North 18th Striet -
t' Post Office Box 2641 Birmingham, Alabama 35291 Telephone 205 7834090 R. P. Mcdonald
%2'%**u"2"o*"'
Alabama Pmer d
tw.w, ee n,<._.
February 07, 1986 Docket Nos. 50-348 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Mr. L. S. Rubenstein Joseph M. Farley Nuclear Plant - Units 1 and 2 Status of Licensing Items Gentlemen:
Attached for your information are the proposed schedules for the completion of licensing items. Attachment 1 contains a listing of license amendment requests and Attachment 2 contains a listing of other NRC related submittals.
If you have any questions, please advise.
\\
Yours very tr
/
cy !
R. P. Mcdonald RPM / JAR: dst-D17 Attachments i
cc: Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. W. H. Bradford gayWillWS/[
goot P
'l
- ATTACHMENT 1 STATUS OF LICENSE AMENDMENT REQUESTS PROPOSED ACTUAL REQUESTED ACTUAL APCo APCo NRC NRC NRC SUBMITTAL SUBMITTAL APPROVAL APPROVAL TAC ITEM DATE DATE(S)
DATE DATE REMARKS
.1.
ISI Code Relief 10-14-85 12-27-85 59900 Complete R; quest for 10 59901 Year Reactor V;ssel Exami nation, FNP-1 and 2 09-19-85 2.
Administrative 01-27-86 59776 Complete Change for 59777 Offsite and Onsite Organizational Changes, FNP-1 and 2 (T.S.
Figures 6.2-1 and 6.2-2) 10-25-85 05-16-86 60075 Critical 3.. Revised Heatup and Cooldown (FNP-1)
(FNP-1)
Outage Item Curves Based on R;gulatory 09-30-85 03-14-86 59902 Critical Guide 1.99, (FNP-2)
(FNP-2)
Outage Item Rev.
2,.
FNP-1 and 2 4.
ISI Relief 02-28-86 09-01-86 Critical Rsquest for RHR Outage Item and 0ther FNP-1; New Valves, FNP-1 Item and 2 11-27-85 03-31-86 60289 New Item 5.
Quadrant Power Tilt Ratio 60290 (QPTR),FNP-1 and 2 (T.S.
4.2.3.2 and Table 3.3-1) 60287 11-22-85 06-06-86 6.
Correct Note for Rx Trip 60288 Signal on
. Turbine Trip for Plant Start-up, FNP-1 and 2(T.S.
Table 4.3-1, Item 17.B)
ATTACHMENT 1 STATUS OF LICENSE AMENDMENT REQUESTS PROPOSED ACTUAL REQUESTED ACTUAL APCo APCo NRC NRC NRC SUBMITTAL SUBMITTAL APPROVAL APPROVAL TAC ITEM DATE DATE(S)
DATE DATE REMARKS
'7.
Remove' Rod Bow 11-27-85 06-06-86 60291 PInalty, FNP-1 60292 and 2 (T.S.
3.2.3 and Bases, Delete Figure 3.2.3)
- 8.. Clarification 11-27-85 06-06-86 60293 cf Dose 60294 Equivalent I-131 (DEI)
Definition FNP-1 and 2 (T.S. 1.9) 9.
Administrative 12-09-85 06-13-86 60355 Supplemental Change to Fire 60356 information Pr2tection and to be Miscellaneous submi tted Other T.S.,
02-14-86.
FNP-1 and 2
- 10. GL 85-09 RTB &
12-16-86 09-15-86 55354 New Item BYB Action 55355 Statement &
Surveillance, FNP-1 and 2 (T.S. Tables 3/4.3-1)
- 11. Reactor Coolant 02-07-86 08-27-86 Pump Opsrability Change for Mode 3, FNP-1 and 2 (T.S.
3/4.4.1.2)
'12.
Snubber Visual 02-28-86 08-29-86 New dates Inspection Period Adjustment Criteria Change, FNP-1 and 2 (T.S.3/4.7.9)
ATTACHMENT l' STATUS OF LICENSE AENDMENT REQUESTS PROPOSED ACTUAL REQUESTED ACTUAL APCo APCo NRC NRC NRC SUBMITTAL SUBMITTAL APPROVAL APPROVAL TAC ITEM DATE DATE(S)
DATE DATE REMARKS
- 13. Extend Operating 03-07-86 09-05-86 License O
Expiration Date, FNP-1 and
-2 (License)
- 14. Increase RWST' 03-31-86 09-30-86 New dates Boron C:ncentration, FNP-1 and 2 (T.S. 3.5.5, 3.5.1)
- 15. Change to 04-04-86 10-10-86 Clarify Method of QPTR and AFD Channel Calibrations, FNP-1 and 2
-(T.S. 4.2.1.2, 4.2.4.2, Table 4.3-1)
.16.
Steam Generator 05-01-86 11-03-86 Potential Plugging Critical Limits, FNP-1 Outage Item and 2 (T.S.
FNP-1 F1gure 2.1-1 and Section 3.2.2) 12-05-86
- 17. D21etion of 05-30-86 Appendix B of License, FNP-1 and 2 (E.P.P.)
- 18. Tcchnical 06-27-86 01-30-87 New dates
. Specification Optimization
' Program, FNP-1
'and 2 (T.S.
3/4.3)
ATTACHMENT 1 STATUS OF LICENSE AMENDMENT REQUESTS PROPOSED ACTUAL
. REQUESTED ACTUAL APCo APCo NRC NRC NRC SUBMITTAL SUBMITTAL APPROVAL APPROVAL-TAC ITEM DATE DATE(S)
DATE DATE REMARKS
- 19.. Change AFD 08-08-86 02-12-87 New dates Tcrget Band FNP-1 and 2 (T.S. 3.2.1 and 4.2.1.4) 03-12-87
- 20. 031etion of 09-05-86 Na0H Tank, FNP-1 and 2 (T.S. 3/4.6.2.2 and Bases)
- 21.. Small Diesel 09-12-86 03-20-87 New dates G;nerators Testing, FNP-1 and 2 (T.S.
3/4.8.1)
TBD Pending NRC
- 22. Containment TBD Purge and' Vent Safety Operation, Evaluation FNP-1 and 2 (T.S. 3/4.6) 03-13-85 11-19-85 57243 Complete;
- 23. Fire Protection Exemption (FNP-2)
Revised FNP 2 R: quests, FNP-and Shared; 1 and 2 New Item 05-31-85 57854 New Item (FNP-1) 60030 Revised FNP 1 10-18-85 01-27-86 and Shared; (FNP-1)
New Item 60031 Revised FNP 2 10-18-85 01-27-86 and Shared; (FNP-2)
New Item
ft.
ATTACHMENT 2 STATUS OF OTHER NRC RELATED SUBMITTALS PROPOSED ACTUAL APCo APCo NRC SUBMITTAL SUBMITTAL TAC ITEM DATE DATE REMARKS N/A 1.
Inservice.
02-28-86 Inspection Report of Steam Generator
. Tube Inspections 2.
Radial Peaking Factor Report N/A 60 days prior to startup a.
Unit 2, Cycle 5 03-19-86 b.
Unit 1, Cycle 8 10-01-86 N/A 60 days prior to startup N/A 1985 10CFR50.59 Report 3.
Annual Report of 03-30-86 Plant Changes, FNP-1 and 2 N/A Review results and 4.
IEB 85-03, Motor 05-14-86 Operated Valve program completion Comnon Mode Failure schedule During Plant Transients Due to Improper Switch Settings, FNP-l' and 2
48163 WOG generic _ studies 5.
NUREG-0737, 05-30-86 II.K.3.31, SBLOCA 48164 complete Plant-specific Analysis, FNP-1 and 2
N/A Report every 5 years 6.
NUREG-0737, 06-15-86 II.K.3.17, ECCS Outages, FNP-2 N/A Annual update 7.
FSAR Update 07-01-86 8.
Startup Reports N/A 90 days af ter startup a.
Unit 2, Cycle 5 08-19-86 N/A 90 days after startup b.
Unit 1, Cycle 8 03-01-87
f:-
a ATTACHMENT 2 STATUS OF OTHER NRC RELATED SUBMITTALS PROPOSED ACTUAL APCo APCo "NRC SUBMITTAL SUBMITTAL TAC ITEM DATE DATE REMARKS 9.
Generic Letter 82-33, Supplement 1 to NUREG-0737, Requirements for yg Emer9ency Response Capability (SECY 82-111)
N/A a.
CROR Summary 4th Quarter Report 1986 N/A b.
SPDS additional TBD information 59092 10.
10CFR50.62, 90 days Requirements for after NRC 59093 Reduction of Risk SER From ATWS Events m-c--,,---_