Letter Sequence Other |
|---|
TAC:60075, (Approved, Closed) TAC:60355, (Approved, Closed) TAC:60356, (Approved, Closed) TAC:62187, (Approved, Closed) TAC:62188, (Approved, Closed) TAC:62811, (Approved, Closed) TAC:62812, (Approved, Closed) TAC:64210, (Open) TAC:64211, (Approved, Closed) TAC:64435, (Approved, Closed) TAC:64436, (Approved, Closed) TAC:65482, (Open) TAC:65489, (Approved, Closed) |
|
MONTHYEARML20101T3591985-01-31031 January 1985 Forwards Implementation Schedule for Detailed Control Room Design Review,In Response to Generic Ltr 82-33,Suppl 1 to NUREG-0737.Safety Significance Rankings of Human Engineering Deficiencies & short-term Corrective Actions Encl Project stage: Other ML20108D7451985-02-14014 February 1985 Forwards Safety Evaluation & Technical Evaluation Rept Based on Review of 840629 Detailed Control Room Design Review Summary Rept,Per Suppl 1 to NUREG-0737.Supplemental Rept Addressing Items Identified in Safety Evaluation Requested Project stage: Approval ML20112F6631985-03-22022 March 1985 Responds to NRC Re Schedule for Submitting Supplemental Summary Rept for Detailed Control Room Design Review & Status of Special Studies.Addl Info Will Be Discussed During Preimplementation Audit in Late Apr 1985 Project stage: Supplement 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 ML20077D2221985-10-28028 October 1985 Forwards Outline of Submittal to NRC Summarizing 851009 post-audit Meeting Re Dcrdr Project stage: Meeting ML20138L0261985-12-0909 December 1985 Proposed Tech Specs,Incorporating Administrative Corrections Re Fire Protection 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 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 ML20214E3081986-02-28028 February 1986 Forwards Descriptions of Safety Significant Human Engineering Discrepancies (Heds) Identified During Dcrdr,Per Commitments Made in Util Comments on Draft Ser.Justification for Heds That Will Not Be Addressed Also Encl Project stage: Draft 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 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 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 ML20209E9881986-09-0202 September 1986 Application for Amends to Licenses NPF-2 & NPF-8,changing Snubber Surveillance Requirements to Increase Allowable Time Interval Between Visual Surveillances When Snubber Sys Operating at High Level of Dependability.Fee Paid Project stage: Request 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 ML20214D2161986-11-18018 November 1986 Notification of 861120 Meeting W/Util,Southern Co Svcs,Inc & Bechtel in Bethesda,Md to Discuss Proposed Change to Tech Specs Re Snubber Surveillances Project stage: Meeting ML20207D5031986-12-19019 December 1986 Application for Amends to Licenses NPF-2 & NPF-8,revising Tech Specs to Authorize Repair of Steam Generator Tubes W/Indications of Degradation as Alternative to Tube Plugging.Fee Paid Project stage: Request ML20236S4401986-12-30030 December 1986 Summary of 861120 Meeting W/Util Re Proposed Tech Spec Changes to Snubber Surveillance Insp Intervals Project stage: Meeting ML20207D5341986-12-31031 December 1986 Proposed Tech Specs Authorizing Repair of Steam Generator Tubes W/Indications of Degradation as Alternative to Tube Plugging Project stage: Other ML20212J7661987-01-13013 January 1987 Requests Relief from ASME Code,Section XI,1974 Edition Through Summer 1975 Addenda,Table IWB-2600,Item B3.2 & Table IWB-2500,Category B-D,permitting Visual Exam of Each Steam Generator Primary Side Nozzle.Fee Paid Project stage: Other ML20210F8011987-02-0909 February 1987 Application for Amends to Licenses NPF-2 & NPF-8,changing Tech Specs Re Snubber Surveillance Requirements.Request Suppls 860902 Tech Spec Submittal by Providing Requested Revised Proposed Snubber Visual Insp Schedule.Fee Paid Project stage: Request ML20210G8471987-02-0909 February 1987 Proposed Tech Specs,Incorporating Revised Proposed Snubber Visual Insp Schedule Project stage: Other ML20211P5001987-02-25025 February 1987 Application to Amend Licenses NPF-2 & NPF-8,revising Tech Specs to Allow Snubber Failures to Be Expressed as Percentage of Specific Snubber Population in New Snubber Visual Insp Schedule Project stage: Request ML20211P5691987-02-25025 February 1987 Proposed Tech Specs Re Snubber Surveillance Requirements & Visual Insp Schedule Project stage: Other ML20147F5041987-02-25025 February 1987 Forwards Comments on Licensee Training Performance During Period of INPO Accreditation Effort.Certification of Licensed Operator Training Program Encl Project stage: Request ML20212C8781987-02-27027 February 1987 Forwards Info Re Plant Snubbers,Including Date of Failures & Current safety-related Snubber Population Project stage: Other ML20206G3561987-03-30030 March 1987 Safety Evaluation Supporting Amends 69 & 61 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20206G3341987-03-30030 March 1987 Amends 69 & 61 to Licenses NPF-2 & NPF-8,respectively, Modifying Tech Specs Re Visual Insp Requirements for Snubbers on one-time Basis Project stage: Other 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 ML20209E5981987-04-10010 April 1987 Safety Evaluation Supporting Amends 70 & 62 to Licenses NPF-2 & NPF-8,respectively Project stage: Approval ML20210D2371987-04-27027 April 1987 Requests That Proprietary Rev 1 to WCAP-11178, Steam Generator Sleeving Rept (Mechanical Sleeves), Be Withheld (Ref 10CFR2.790).Affidavit for Withholding Encl Project stage: Other ML20210D2281987-05-0404 May 1987 Revised Application for Amends to Licenses NPF-2 & NPF-8, Changing Tech Specs Re Repair of Steam Generator Tubes W/ Indications of Degradation.Ra Wiesemann & Revs 1 to WCAP-11179 & Proprietary WCAP-11178 Also Encl Project stage: Request 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 ML20216E7401987-06-23023 June 1987 Safety Evaluation Supporting Amend 71 to License NPF-2 Project stage: Approval ML20235K4211987-07-0808 July 1987 Forwards Safety Evaluation Granting Relief from ASME Section XI Volumetric Exam Requirements for Steam Generator Nozzle Inside Radiused Sections.Requirements Impractical & Alternative Methods Acceptable Project stage: Approval ML20235K4441987-07-0808 July 1987 Safety Evaluation Supporting Granting Licensee Relief from Volumetric Exam of Steam Generator Primary Side Noozles Inside Radiused Sections Project stage: Approval ML20235J4551987-07-10010 July 1987 Forwards Section 2.3 of Proprietary Version WCAP 11178,Rev 1 & Nonproprietary Version WCAP 11179,Rev 1 of Rept Applicability. Section Discusses Steam Generator Tube Repair.Encl for Insertion Into 870504 Tech Spec Change Project stage: Other ML20237L0021987-08-25025 August 1987 Forwards Replacement Pages for Proprietary Rev 1 to WCAP 11178 & Nonproprietary Rev 1 to WCAP 11179 Re Steam Generator Tube Repair & Tubesheet Region Plugging Criterion. Proprietary Pages Withheld (Ref 10CFR2.790) Project stage: Other ML20235C9931987-09-18018 September 1987 Amends 72 & 63 to Licenses NPF-2 & NPF-8,respectively, Revising Tech Spec 3/4.4.6 to Allow Use of Approved Steam Generator Tube Sleeving Technique in Lieu of Plugging Defective Tubes Project stage: Other ML20148T4481988-01-28028 January 1988 Proposed Revs to Tech Specs,Deleting Surveillance Requirement 4.4.10.1.2 & Table 4.4-5 Re Surveillance Specimen Withdrawal Times.Related Info Encl Project stage: Other ML20148L7741988-03-29029 March 1988 Requests Relief from Requirements of Second 10-yr Interval Inservice Testing Program for ASME Class 1,2 & 3 Pumps & Valves to Enable Use of Valve Disassembly & Installation of Instrumentation as Acceptable Test Alternatives Project stage: Other ML20150F3341988-03-30030 March 1988 Grants Revised Interim Approval for Reliefs for Inservice Testing Program for Second 10 Yr Interval Until NRC Final Action & Safety Evaluation Issued.Agrees That Remaining Two Valves Do Not Need to Be Included in Subj Program Project stage: Approval ML20154C9601988-05-12012 May 1988 Forwards Safety Evaluation Re Util 880428 & 0505 Submittals of Results of Inservice Insp Exam.Flaw Indications Conditionally Acceptable for Svc.Augmented Inservice Insp Required During Next Three Insp Periods,Per ASME Code Project stage: Approval ML20154C9651988-05-12012 May 1988 Safety Evaluation Re Flaw Indications in Reactor Pressure Vessel Project stage: Approval ML20154H9341988-05-20020 May 1988 Application for Amends to Licenses NPF-2 & NPF-8,retaining Portion of Paragraph 4.4.10.1.2 Which Reiterates 10CFR50, App H Requirement That Reactor Vessel Matl Irradiation Surveillance Specimens Shall Be Removed & Examined Project stage: Request ML20154L9331988-05-26026 May 1988 Application for Amends to Licenses NPF-2 & NPF-8,revising Ref of Senior Vice President to President - Nuclear to Reflect Organizational Titles Project stage: Request ML20196E4951988-06-22022 June 1988 Requests Exemption from Program Update Requirements of 10CFR50.55a(g)(4)(ii).Proposes to Update Unit 2 Program to ASME Code 1983 Edition Rather than Update Program to Code of Record on 910731 Project stage: Other 1987-02-25
[Table View] |
Forwards Proposed Schedules for Completion of Licensing Items,Including Prioritized Listing of License Amend & Other Requests & Listing of NRC-related Submittals| ML20154E847 |
| Person / Time |
|---|
| Site: |
Farley  |
|---|
| Issue date: |
09/09/1988 |
|---|
| From: |
Hairston W ALABAMA POWER CO. |
|---|
| To: |
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM) |
|---|
| References |
|---|
| TASK-2.D.1, TASK-TM GL-87-09, GL-87-9, GL-88-12, IEB-88-002, IEB-88-2, TAC-60075, TAC-60355, TAC-60356, TAC-62187, TAC-62188, TAC-62811, TAC-62812, TAC-64210, TAC-64211, TAC-64435, TAC-64436, TAC-65482, TAC-65489, NUDOCS 8809190157 |
| Download: ML20154E847 (9) |
|
Text
o
~
/ Jab:ma Poo Cornpry 600 North ich SUeet Post Off ce Escu 2641 B.rm ngham. A:atama 35291-04Co
' Telephone 205 25o t837 W. O. Hairston,Ill Senior Vice Pres; dent b
N # ear Opera'ons
)
1 v sourwn exec som 10CFR50.90 September 9, 1988 Docket Nos. 50-348 50-364 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Vashington, DC 20555 Gentlemen Joseph M. Farley Nuclear Plant - Units 1 and 2 Status of Licensing Items Attached for your information are the proposed schedules for the completion of licensing items. Attachment I contains a prioritized listing of license amendment and other requests and Attachment 2 contains a listing of other NRC related submittals.
During 1987 fifteen requested licensing actions and two interim approvals vere dispositioned by the NRC.
Alabama Pover Company appreciates NRC efforts in this area.
If you have any questions, please advise.
Respectfully submitted, W / H. k V. G. Hairston, III VGH III/JARidst-V8.3 Attachment cci Mr. L. B. Long Dr. J. N. Grace Mr. E. A. Reeves Mr. G. F. Maxwell ch890909 0 I l L
ATTACHMENT 1 STATUS OP LICENSE AMENDMENT AND OTHER REQUESTS PROPOSED ACTUAL REQUESTED ACTUAL j
APCo APCo NRC NRC NRC j
j SUBMITTAL SUBMITTAL APPROVAL APPROVAL TAC
{
ITEM DATE DATE (S)
DATE DATE 4
REMARKS 1.
Extend 08-11-86 10-14-88 62187 Approval I
Operating License 07-22-87 62188 required to l
Expiration Date, support i
FNP-1 and 2 depreciation (License) charge upda t e.
l I
l 2.
Snubber Visual 09-15-88 02-28-89 Required by Inspection March 1989 i
Table Inter-to prealude pretation, FNP-1 submittal of (T.S. 3/4.7.9) one-time license 1
amendment.
i i
l 3.
NRC Bulletin No.
08-29-88 02-10-89 Required i
88-02 Analysis prior to l
- Approval, 6th R.O.
FNP-1 and 2 (03-24-89).
i t
Required
(
0.
Updated ISI 12-15-88 03-15-89 Program Relief prior to i
Requests, FNP-2 6th R.O.
I J
(03-24-89).
[
L Required J
5.
Updated IST 12-15-88 03-15-89 Program Relief prior to Requests, FNP-2 6th R.O.
(03-24-89).
6.
End of Life 12-15-88 06-15-89 Required by Cycle Moderator July 1989 Temperature Co-for Unit 1.
4 efficient, FNP-1 and 2 I
(T.S. 3.1.1) 7.
Control Rod 10-28-88 04-28 89 Insertion Limits, FNP-1 i
and 2 (T.S. 3.1.3.5) l
ATTACHMENT 1 STATUS OF LIC2NSE AMENDMENT AND OTHER REQUESTS PROPOSED ACTUAL REQUESTED ACTUAL APCo APCo NPC NRC NRC SUBMITTAL SUBMITTAL APPROVAL APPROVAL TAC ITEM DATE DATE (S)
DATE DATE REMARKS 8.
Additional ISI 09-13-88 03-07-89 Reliefs for 2nd 10-Year Interval, FNP-1 9.
Additional IST 09-13-88 03-07-89 Reliefs for 2nd 10-Year Interval, FNP-1 10.
Fuel Recon-12-04-88 06-05-89 stitution, FNP-1 and 2 (T.S. 5.3)
Letter only, 11.
n lta Flux 09-23-88 04-21-89 e
Deviation not an Alarm Setpoint, amendment FNP-1 and 2 request.
t (T.S. Bases 3/4.2.1)
- 13. Removal of 01-20-89 07-21-89 Fire Protection Requirements from Technical Specifications (Generic Letter 88-12), FNP-1 i
and 2 i
l
- 13. RHR Suction 01-27-89 07-27-89 Valve Auto i
Closure Inter-r lock Removal, FNP-1 and 2 (T.S. 3/4.9.8) lo. RHR Val"e 11-18-88 05-19 89
- Closure, 1
FNP-1 and 2 (T.S. 3/4.5.3) i
- 19. VCT Suction 11-30-88 05-30-89 i
Valve Stroke Time, FNP-1 i
and 2 (T.S. Table 3.3-5) l 1
ATTACHMENT 1 STATUS OF LICENSE AMENDMENT AND OTHER REQUESTS PROPOSED ACTUAL REQUESTED ACTUAL APCo APCo NRC NRC NRC SUBMITTAL SUBMITTAL APPROVAL t.PPROVAL TAC ITEM DATE DATE (S)
DATE DATE 9
REMARKS 16.
Auxiliary 12-09-88 06-09-89 Sampling Grace Period, FNP-1 and 2 (T.S. 3.3.3.11) 17.
Radial Peaking 10-28-88 07-14-89 Factor Report Submittal within 30-days, FNP-1 and 2 (T.S. 6.9.1.11) i
- 18. Generic Letter 12-23-88 06-23-89 87-09 Changes, FNP-1 and 2 (T.S. 3.0, 4.0)
- 19. Miscellaneous 10-21-88 07-07-89 T.S. Changes, J
FNP-1 and 2 Letter only, 20.
Lov Flov DNBR 09-30-88 04-14-89 Bases Correction, not an FNP-1 and 2 amendment
]
(T.S. Bases request.
2.2.1) 31.
ISI Reliefs for 05-27-87 See Remarks 65482 Interim 2nd 10-Year 11-23-87 approval Interval, FNP-1 granted 12-10-87.
Avaiting final approval.
33.
IST Reliefs for 05-27-87 See Remarks 65489 InteriP 2nd 10-Year 09-30-87 spproval Interval. FNP-1 11-20-87 granted 03-29-88 12-10-87 and i
03-30-88.
Avaiting i
final approval.
ATTACHMENT 1 STATUS OF LICENSE A
AMENDMENT AND OTHER REQUESTS PROPOSED ACT UAL REQUESTED ACTUAL APCo APCo NRC NRC NRC SUBMITTAL SUBMITTAL APPROVAL APPROVAL TAC ITEM DATE DATE (S)
DATE
. DATE,,
t REMAKKS t
- 23. RCI'tS (Rx 09-30-88 59732 Vessel 1.evel) 59733 Surveillance, FNP-1 and 2 24.
Deletion of Fire 07-16-87 See Remarks On hold I
Protection from per NRC Technical letter of Specifications, 02-24-88, t
FNP-1 and 2
- 35. Corrected Pages 10-08-86 01-07-87 Complete for Heatup and l
Cooldovn Curves, FNP-2 26.
Snubber Visual 09-02-86 03-30-87 62811 Complete Inspection 02-09-87 62812 Criteria 02-25-87 One-Time Change.
02-27-87 i
FNP-1 and 2 (7.S. 3/4.7.9) i
- 37. Administrative 12-09-85 04-10 87 60355 Complete i
Change to Firo 02-18-86 60356 I
Protection and Miscellaneous i
Other T.S.,
FNP-1 and 2 i
t
- 28. Revised Heatup 10-25-85 06-23-87 60075 Complete i
and Cooldovn 06-30-86 Curves Based 09-29-86 on Regulatory Guide 1.99, TNP-1 39.
ISI Reliefs 01-13-87 07-08-87 64435 Complete for 1st 10-year 64436 seriod, FNP-1 and 2 30.
Steam Generator 12
-86 09-18 R7 64210 Complete Tube Sleeving 05-04-87 64211 FNP-1 and 2 07-10-87 (T.S. 3/4.4.6) 08-25-87
s ATTACHMENT 1 STATUS OF LICENSE AMENDMENT AND O'rHER REQUESTS PROPOSED ACTUAL REQUESTED ACTUAL APCo APCo NRC NRC NRC i
SUBMITTAL SUBHITTAL APPROVAL APPROVAL TAC i
ITEM DATE DATE (S)
DATE DATE 9
REMARKS r
31.
Steam Generator 05-04-87 09-21-87 65287 Complete
(
l F*,
FNP-2 08-25-87 (T.S. 3/4.4.6) 33.
Steam Generator 08-25-86 10-26-87 62283 Complete Prbe Plugging 10-13-86 622G4 7 aits, TNP-1 06-02-87 and 2 (T.S.
08-18-87 Figure 2.1.-1 09-16-87 and Section 09-23-87 3.2.2) l 33.
Cor.tainment 05-04-87 11-16-87 65454 Complete l
Purge and Vent 65455 l
Operation, FNP-1 and 2 (T.S. 3/4.6) 30.
12-09-87 03 08-88 66777 Complete Meteorological Data Change, 66778 FNP-1 and 2 (T.S. 6.9.1.9) l 03-17-88 03-30-88 67559 Complete l
35.
Interim IST Reliefs for 2nd 10-year
.j Period FNP-1 1
1 36.
Reactor Vessel 04-28-88 05-12-88 67960 Complete ISI Indications 05-05 88 I
Approval, FNP-1 i
l
~
None 05-27-88 65224 Complete
(
37.
Physical Security Plan License 65225 t
Amet.dment i
i l
- 38. Removal of 04-28-88 07-08-88 68013 Complete
(
Organization 68014 i
Charts from l
Tech Spec l
Control FNP-1 i
and 2 (T.S.6.2) j
- 39. Organization 05-10-88 07-18-88 68236 Complete
(
Change of SVP 05-26-88 68237 j
to VP, TNP-1 and 2 (T.S.
6.1, 6.2, 6.5, 6.6) i
ATTACHMENT 1 STATUS OF LICENSE AKENDMENT AND OTHER REQUESTS PROPOSED ACTUAL REQUESTED ACTUAL APCo APCo NRC NRC NRG SUBMITTAL SUBMITTAL
'.PPROVAL APPROVAL TAC ITEM DATE DATE (S)
DATE DATE REMARKS 08-22-88 67109 Complete 40.
Surveillance 01-28-88 Capsule 05-20-88 67110 i
Vithdrawal l
- Schedule, l
TNP-1 and 2 (t.S. table 4.4-5) 41.
Inservice 11-20-87 08-31-88 66678 Complete Inspection 06-22-88 and Testing Schedule l
Exemptions to Utilize 1
Latest ASME Code,Section XI. FNP-2 l
1 i
l
ATTACHMENT 2 STATUS OF OTHER NRC RELATED SUBMITTALS PROPOSED ACTUAL APCo APCo NRC SUBMITTAL SUBMITTAL TAC ITEM CATE DATE (S) e REMARKS 1.
10CTR50.62 AMSAC 59092 Operational Unit 1 59093 8th R.O., Unit 2 5th R.O.
a.
Isolatten Device 02-27-87 Coaplete Information 12-09-87 Complete b.
Plant specific questions addressed c.
Additional informa-04-28-88 Complete tion 2.
Startup Reports a.
Unit 1. Cycle 9 09-13 88 N/A 90 days after startup b.
Unit 2 Cycle 7 08-01-89 N/A 90 days after startup 03-31-88 N/A 1987 report 3.
Annual Report of Plant changes.
TNP-1 and 2 07-e1-88 N/A Complete 4.
FSAR Update 5.
Radial Peaking Factor Report 03-10-88 N/A Complete a.
Unit 1, Cycle 9 b.
Unit 2, Cycle 7 03-01-89 N/A 60 days prior to startup Formerly TAC 444579 6.
NUREG-0737, Item II.D.1, Upon Safety Valve Discharge completion and #44580.
of valk-dovns and feasibility
- studies, approximately 09-13-88
I ATTACHMENT 2 STATUS OF OThER NRC RELATED SUBMITTALS j
l PROPOSED ACTUAL APCo AFCo NRC SUBMITTAL SUBMITTAL TAC ITEM DATE DATE (S) 1 P.EMARKS Monthly Plant Status Monthly Monthly N/A to NRC Project Manager 8.
Status of Licensing Semi-Annual Semi-Aitnual N/A i
Items 5
l 1
I i
i f
I I
i l
i l
l l
I 4
l f
I I
i I
i 1
I
_