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	Issue date	Title	Topic
ML20217M185	19 October 1999	Forwards NRC Rept Number 17, Requal Tracking Rept from Operator Licensing Tracking Sys.Rept Was Used by NRC to Schedule Requalification Exam for Operators & Record Requal Pass Dates
ML20212F834	22 September 1999	Forwards Insp Rept 50-333/99-07 on 990718-0828.No Violations Noted	Significance Determination Process
ML20212A695	9 September 1999	Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics	Safe Shutdown Fire Barrier Coatings Exemption Request Fire Protection Program Backfit
ML20212A834	9 September 1999	Requests That Licensees Affected by Kaowool Fire Barriers Take Issue on Voluntary Initiative & Propose Approach for Resolving Subj Issues.Staff Plans to Meet with Licensees to Discuss Listed Topics	Safe Shutdown Fire Barrier Coatings Exemption Request Fire Protection Program Backfit
ML20211N430	8 September 1999	Discusses Proposed Meeting to Discuss Kaowool Fire Barriers. Staff Requesting That Affected Licensees Take Issue on Voluntary Initative & Propose Approach for Resolving Issues	Safe Shutdown Fire Barrier Coatings Exemption Request Fire Protection Program Backfit
ML20210U262	12 August 1999	Forwards Insp Rept 50-333/99-06 on 990601-0717.No Violations Noted	Power change
ML20216D942	28 July 1999	Forwards Safety Evaluation Granting Requests for Relief from Requirements of ASME Code,Section XI for Second 10-year ISI Interval for James a FitzPatrick NPP
ML20210A700	16 July 1999	Forwards Request for Addl Info to Supplement Response Provided for GL 97-05, Steam Generator Tube Insp Techniques
ML20209D551	6 July 1999	Informs That as Result of NRC Review of Licensee Response to GL 92-01,rev 1,suppl 1,staff Revised Info in Reactor Vessel Integrity Database & Releasing Database as Rvid Version 2
ML20196G298	18 June 1999	Forwards Insp Rept 50-333/99-04 on 990412 to 0529.Violations Being Treated as non-cited Violations
ML20212J054	17 June 1999	Responds to Requesting That NRC Staff ...Allow BWR Plants Identified to Defer Weld Overlay Exams Until March 2001 or Until Completion of NRC Staff Review & Approval of Proposed Generic Rept,Whichever Comes First	Weld Overlay
ML20196L145	7 June 1999	Informs That NRC Office of Nuclear Reactor Regulation Reorganized Effective 990328.As Part of Reorganization,Div of Licensing Project Mgt Created.Ss Bajwa Will Be Section Chief for Ja Fitzpatrick & Indian Point NPPs	Enforcement Discretion
ML20207D919	27 May 1999	Informs That on 990521 NRC Staff Held Planning Meeting to Identify Insp Activities at Facility Over Next Six Months
ML20207A675	17 May 1999	Forwards RAI Re 960626 Submittal & Suppl Related to IPEEEs for Plant.Licensee Committed to Revise Plant Fire IPEEE to Reflect Issues Associated with EPRI Fire PRA Implementation Guide within 120 Days of Issues Resolution
ML20206N072	11 May 1999	Forwards Insp Rept 50-333/99-03 on 990301-0411.Four Violations of NRC Requirements Occurred & Being Treated as non-cited Violations,Consistent with App C of Enforcement Policy
ML20206C855	27 April 1999	Informs That Util 990406 Submittal, Licensing Rept for Reracking of Ja FitzPatrick Spent Fuel Pool,Rev 7, Will Be Marked as Proprietary & Will Be Withheld from Public Disclosure Pursuant to 10CFR2.790(b)(5) & Section 103(b)
ML20205P464	15 April 1999	Forwards for Review & Comment Draft Info Notice That Describes Unanticipated Reactor Water Draindown at Quad Cities Nuclear Power Station Unit 2,Arkansas Nuclear One Unit 2 & Ja Fitzpatrick NPP	Reactor Vessel Water Level
ML20205P199	9 April 1999	Discusses 990224 PPR & Forwards Plant Issues Matrix & Insp Plan.Advises of Planned Insp Effort Resulting from Plant PPR Review	Systematic Assessment of Licensee Performance Fire Protection Program
ML20205F803	2 April 1999	Forwards Draft Info Notice Describing Unanticipated Reactor Water Draindown of Listed Plants	Reactor Vessel Water Level
ML20205C104	26 March 1999	Forwards Insp Rept 50-333/99-02 on 990125-0209.No Violations Noted.Insp Evaluated Results of Investigation Into Causes of 990114 Hydrogen Fire Event & Licensee Response to Event. Licensee Overall Response to Event,Acceptable	Unanalyzed Condition
ML20204J379	23 March 1999	Forwards Insp Rept 50-333/99-01 on 990111-0228.No Violations Noted.Security Program Was Effectively Implemented
ML20203E923	10 February 1999	Forwards Insp Rept 50-333/98-08 on 981123-990110.No Violations Noted.Conduct of Activities Generally Characterized by safety-conscious Operations,Sound Engineering & Maintenance Practices
ML20203B900	8 February 1999	First Partial Response to FOIA Request for Documents. Forwards Documents Listed in App a Already Available in PDR, Documents in App B Released in Entirety & Documents in App C Being Withheld in Part (Ref Exemption 6)
ML20202J057	3 February 1999	Forwards Safety Evaluation Authorizing Rev 2 of Third Interval Inservice Testing Program for Pumps & Valves for James a FitzPatrick Nuclear Power Plant
ML20202C187	26 January 1999	Forwards Request for Addl Info Re Util 971014 Request for Changes to James a Fitzpatrick Nuclear Power Plant TSs to Increase Capacity of Sf Pool.Response Requested within 30 Days of Date of Ltr	Time to boil
ML20203H894	21 January 1999	Forwards Notice of Withdrawal of Application for Amend to License DPR-59.Amend Would Have Modified TS Re Inservice Leak & Hydrostatic Testing Operations	Hydrostatic
ML20199G716	19 January 1999	Informs That NRC Review of Relief Requests Submitted on 980126 for James a FitzPatrick Nuclear Power Plant, Considered Complete
ML20198L404	17 December 1998	Forwards Insp Rept 50-333/98-07 on 981005-1122 & NOV Re Design Deficiency That Resulted in Main Steam Safety Relief Valve Pilot Solenoid Cables Not Being Installed in Conduit
ML20198C233	15 December 1998	Ltr Contract:Task Order 236, Review & Evaluation of Fitzpatrick Nuclear Power Plant Application for Conversion to Improved TS, Under Contract NRC-03-95-026
ML20198B453	10 December 1998	Advises of Planned Insp Effort Resulting from Insp Resource Planning Meeting on 981110.Historical Listing of Plant Issues Encl	Fire Barrier Missed surveillance Maintenance Rule Program Fire Protection Program
ML20198F986	4 December 1998	Forwards Assessment Re Util 980916 Info Re NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in Bwr. NRC Agrees with Util Conclusion That Plant Remains within Licensing Basis
ML20196J343	4 December 1998	Forwards SER Accepting Util Program for Periodic Verification of MOV design-basis Capability at FitzPatrick in Response to GL 96-05
ML20196F918	25 November 1998	Forwards Safety Evaluation Re Third 10-year Interval Inservice Insp Program Relief Requests for Plant
ML20195K363	17 November 1998	Forwards SE Authorizing IST Program Relief Request VRR-05, Per 10CFR50.55a(a)(3)(i) & Relief Requests PRR-01,PRR-02R1, PRR-03,PRR-04,VRR-02,VRR-03 & VRR-04,per 10CFR50.55a(a)(3)(ii)
ML20195D971	13 November 1998	Forwards SE Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Issued on 950817
ML20195B733	5 November 1998	Submits Request for Addl Info Re Proposed Extension of Emergency Diesel Generator Allowed Outage Time
ML20155H525	3 November 1998	Forwards SE Authorizing Licensee 980508 Request for Relief from Certain ASME Code Requirements at Ja FitzPatrick Npp. Licensee Requested Relief from Requirements for Addl Exams of CRD Bolting When Cracks Detected in head-to-shank Area
ML20155H575	3 November 1998	Forwards SE Authorizing Proposed Alternative to RPV Shell Weld Exam Requirements of Both ASME BPV Code,Section XI,1989 Edition & Augmented Exam Requirements of 10CFR50.55a(g)(6)(ii)(A)(2) for Ja FitzPatrick NPP	Incorporated by reference
ML20155B568	27 October 1998	Informs That GE Rept GENE-187-30-0598,DRF B13-01920-30, CRD Bolting Flaw Evaluation for Ja FitzPatrick Np, Rev 0,dtd May 1998,submitted by 980507 Affidavit Will Be Withheld from Public Disclosure,Per 10CFR2.790(b)(5)
ML20154Q925	19 October 1998	Forwards RAI Re GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML20154Q511	16 October 1998	Responds to Re Concerns on Use of Reactor Building Crane to Move Sf with Fuel Pool at Jafnpp.Regrets That Did Not Address Concerns in Satisfactory Manner & Provides Addl Info Re Concerns	Emergency Lighting
ML20154M095	14 October 1998	Forwards Insp Rept 50-333/98-06 on 980824-1004.No Violations Noted.Testing & Control Room Operations Were Conducted Appropriately with Formal Communications
ML20154L638	14 October 1998	Forwards SE Accepting Licensee 980126 Submittal of ISI Program & Relief Requests for Third 10-year Interval for Plant
ML20154L237	13 October 1998	Responds to Util Re NRC Bulletin 96-003, Potential Plugging of ECC Suction Strainers by Debris in BWR, Which Addressed Issues Discussed in 980521 Meeting. Request to Defer Completion of Actions Acceptable
ML20154B395	29 September 1998	Provides Addl Info Re Response to GL 96-06, Assurance of Equipment Operability & Containment Integrity During Design Basis Accident Conditions
ML20154B342	28 September 1998	Advises That Info Contained in 980803 Application Re cycle-specific Safety Limit Min Critical Power Ratio for Cycle 14,will Be Withheld from Public Disclosure,Per 10CFR2.790	Minimum Critical Power Ratio
ML20154B820	28 September 1998	Forwards Insp Rept 50-333/98-05 on 980727-0814 & NOV Re Failure to Analyze Effects of LOCA Plus LOOP on Containment Penetration Protection
ML20153F879	22 September 1998	Forwards RAI Re Licensee Response to GL 96-05 for Plant & Indicating Intent to Implement Provisions of JOG Program on motor-operated Valve Periodic Verification
ML20153D255	21 September 1998	Forwards SE Accepting Proposed Alternative Testing of Containment Following ECCS Suction Strainer Replacement
ML20153B334	14 September 1998	Advises That Matl Marked as Proprietary in from Pasn & 980625 Affidavit from Holtec Intl Will Be Withheld from Public Disclosure Per 10CFR2.790(b)(5) & Section 103(b) of Atomic Energy Act of 1954,as Amended

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