Similar Documents at Maine Yankee |
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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20211G4771999-08-27027 August 1999 Notification of 990908 Meeting with Util in Rockville MD to Discuss License Termination Plan That Myap & Contractors Are Preparing as Part of Decommissioning of Myaps ML20210P1311999-08-11011 August 1999 Notification of 990823 Meeting with Maine Yankee Atomic Power Co in Rockville,Md to Discuss License Termination Plan That Util & Contractors Preparing as Part of Decommissioning of Maine Yankee Atomic Power Station ML20212H9551999-06-23023 June 1999 Notification of 990707 Meeting with Myap in Rockville, Maryland to Discuss License Termination Plan for Maine Yankee Atomic Power Station ML20196E1351999-06-23023 June 1999 Notification of 990707 Meeting with Util in Rockville,Md to Discuss License Termination Plan for Plant ML20207A6481999-05-19019 May 1999 Discusses Director Review of Plant Backfit Claim Re beyond- design-basis SFP Accidents & NRR Staff Response to Backfit Review Panel Findings ML20206H1571999-05-0606 May 1999 Notification of 990525 Meeting with Util in Rockville,Md to Discuss License Termination Plan That MYAPC & Contractors Preparing as Part of Decommissioning of Maine Yankee Atomic Power Station ML20207G2921999-03-0404 March 1999 Provides Status on Wits Item 9600184, Clarity & Intent of NRC Safety Guide 1, as It Related to Isat Insp of Maine Yankee Atomic Power Station ML20196D5271998-11-24024 November 1998 Notification of 981215 Meeting for Docket 7200030 with Myap in Rockville,Md,To Discuss Plans for General License to Store Spent Fuel at Onsite ISFSI ML20155C3891998-10-29029 October 1998 Notification of 981102 Meeting with Util in Rockville,Md to Discuss industry-wide Power Reactor Decommissioning Issues as Well as Status of Plant Licensing Action ML20195C3941998-10-28028 October 1998 Discusses Results of Backfit Review Panel Re Emergency Preparedness Requirements for Maine Yankee Panel Determined That Staff Not Imposed Backfit on Licensee.Other Issues, Which Arose During Panel Deliberations,Identified & Encl ML20154L1371998-10-14014 October 1998 Notification of 981109 Meeting W/Util to Present NRC Staff Overview of Mgt of Decommissioning of Maine Yankee Atomic Power Station,Including Proposed Schedule ML20237B3941998-08-11011 August 1998 Forwards Hg Brack s Re Grossly Careless NRC Oversight of Licensees.Copy of Response to Brack Ltr Will Be Provided ML20236V9151998-07-31031 July 1998 Notification of 980814 Meeting W/Util Re Proposed License Defueled Security Plan ML20237A7521998-07-31031 July 1998 Notification of Cancelled 980814 Meeting W/Util in Rockville,Md to Discuss Proposed Plant Defueled Security Plan ML20236F6531998-06-30030 June 1998 Notification of 980710 Meeting W/Maine Yankee in Rockville,Md to Provide Myap Opportunity to Discuss Appeal of NRC Backfit Determination Re Maine Yankee Emergency Preparedness Exemption Request ML20248M0341998-06-0909 June 1998 Informs of Appointment to Backfit Review Panel to Review 980506 Appeal Filed by Myap Re NRC Determination Involving Backfit Claim Made by Licensee Under 10CFR50.109.Util Requests for Exemption from EP Requirements Unwarranted ML20248A4391998-05-26026 May 1998 Notification of 980609 Meeting W/Util in Rockville,Md to Discuss Maine Yankee Spent Fuel Heatup Analysis in Support of Emergency Plan & Financial Protection Exemption Requests ML20247N3471998-05-0808 May 1998 Responds to 980126 Memo Requesting Action Taken as Result of Event Inquiry - Public Concerns W/Nrc Rept of Independent Safety Assessment at Plant ML20247N3001998-05-0505 May 1998 Responds to 980210 Memo Re Event Inquiry Involving Public Concerns W/Nrc Rept of Independent Safety Assessment at Plant ML20217K4941998-04-28028 April 1998 Notification of 980501 Meeting W/Licensee in Rockville,Md to Discuss Defueled Security Plan ML20217M6221998-04-28028 April 1998 Notification of 980501 Meeting W/Util in Rockville,Md to Discuss Util Defueled Security Plan.Meeting Cancelled ML20216C4421998-04-0808 April 1998 Notification of 980423 Predecisional Enforcement Conference W/Myap in King of Prussia,Pennsylvania to Discuss Apparent Violations Identified During Three Investigations Conducted by Oi,As Transmitted on 971219 to Myap ML20199B2621998-01-13013 January 1998 Notification of Significant Licensee Meeting 98-02 W/Util on 980128 to Discuss Licensee Approach to Upcoming Decontamination of Reactor Sys,Design for Sf Island Concept & Use of 10CFR50.59 for Sys Safety re-classification ML20198P7321998-01-12012 January 1998 Notification of 980121 Meeting W/Util in Rockville,Md to Discuss Proposed Plant Defueled Security Plan ML20199C2241997-11-12012 November 1997 Notification of 971125 Meeting W/Maine Yankee Atomic Power Co in Rockville,Md to Discuss Proposed Maine Yankee Atomic Power Station Defueled Technical Specifications ML20198S9401997-11-0606 November 1997 Notification of 971120 Meeting W/Util in Rockville,Md to Discuss Proposed Myaps Defueled TSs ML20217G4061997-10-0707 October 1997 Notification of 971106 Meeting W/Licensee in Wiscasset,Me to Solicit Public Comments on Plant Post Shutdown Decommissioning Activities Rept.Meeting Agenda Encl ML20211G0331997-09-29029 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970609-12 IR 05000309/19970041997-09-29029 September 1997 Forwards NRC Operator Licensing Exam Rept 50-309/97-04OL (Including Completed & Graded Tests) for Tests Administered on 970609-12 ML20217E1631997-09-26026 September 1997 Revised Notification W/Agenda Change of 971007 Public Meeting in Wiscasset,Maine,To Brief Public on Regulatory Process for Decommissioning of NPP ML20217E2741997-09-24024 September 1997 Requests That Mk Webb Be Added to Site Access Authority.Site Access Were Completed & Thus Capable of Safe Conduct in Radiologically Restricted Areas ML20217C1381997-09-22022 September 1997 Notification of 971007 Meeting W/Public in Wicasset,Maine to Discuss Regulatory Process for Decommissioning of Npp. Meeting Held in Response to Recent Announcement by Myapco to Permanently Cease Operation of Myaps ML20217B0741997-09-0303 September 1997 Notification of 970903 Meeting W/Maine Yankee Atomic Power Co in Rockville,Md to Discuss Independent Sf Storage Installation Options Available to Maine Yankee for Storage of Sf.Notice Being Reissued to Revise Meeting Room Number ML20216A9881997-08-29029 August 1997 Notification of 970911 Meeting W/Util in Rockville,Md to Discuss Independent Spent Fuel Storage Installation Options Available to Plant for Storage of Spent Fuel ML20210Q7291997-08-21021 August 1997 Forwards OIG Audit Rept Entitled, NRC Needs Comprehensive Plan to Resolve Regulatory Issues. Rept Reflects Results of OIG Audit of Agency Response to Events at Plants ML20217K8121997-08-13013 August 1997 Notification of 970820 Meeting W/Util in Rockville,Md to Discuss Decommissioning Activities ML20148D1731997-05-23023 May 1997 Forwards Maine Yankee Restart Action Plan for Review & Approval in Accordance W/Nrc Inspection Manual Chapter 0350. RAP Contains List of Issues That NRC Will Inspect to Assess Licensee Compliance W/Applicable Requirements.W/O Encl ML20148D1701997-05-23023 May 1997 Notification of Significant Licensee Meeting 97-58 W/Util on 970606 in King of Prussia,Pa to Discuss Licensee Approach to Resolve Cable Separation Issues at Plant ML20236N2211997-05-0505 May 1997 Discusses Interpretation of Plant TS Re Acceptability of Grab Sampling on Leakage Detection Sys within Meaning of TS 3.14A ML20137U0031997-04-10010 April 1997 Forwards Proposed Response to Ltr from H Myers & Informs of No Need for Further Commission Review ML20137M6141997-04-0303 April 1997 Submits Documents Being Released to Public Re DSI-11, Operating Reactor Program Oversight ML20137E2041997-03-24024 March 1997 Requests Copy of Maine Yankee Restart Readiness Plan & 10CFR50.54(f) Response ML20137H4341997-03-24024 March 1997 Notification of Significant Licensee Meeting 97-30 W/Util on 970403 in Wiscasett,Me to Discuss Plant Restart Readiness Plan as Documented in to NRC ML20137H4361997-03-24024 March 1997 Notification of Significant Licensee Meeting 97-31 W/Util on 970403 in Wiscassett,Me to Discuss Plant Restart Readiness Plan as Documented in to NRC ML20136F9561997-03-13013 March 1997 Notification of 970320 Meeting W/Licensee to Discuss Proposed TS Change 194 Re Operation W/Reduced Reactor Coolant Sys Flow Rate ML20136F9651997-03-13013 March 1997 Notification of 970326 Meeting W/Licensee in Rockville,Md to Discuss SG Insp Plans & Contingencies ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20136F2431997-02-27027 February 1997 Notification of Significant Licensee Meeting 97-21 W/Util on 970311 to Discuss Apparent Violations Identified in Listed NRC Insp Repts ML20137M8101997-02-18018 February 1997 Informs That Paper Very Difficult to Get One Arms Around in Part Because It Tries to Deal Simultaneously W/Licensing, Insp & Performance Assessment in Each of Options & in Part Because Paper Implicit Assumption Ongoing Millestone. ML20134J9981997-02-10010 February 1997 Notification of 970212 Meeting W/Listed Attendees in Rockville,Md to Discuss Pending Phase I Mgt Svcs Agreement Between MYAPC & Nuclear Entergy,Inc 1999-08-27
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20211G4771999-08-27027 August 1999 Notification of 990908 Meeting with Util in Rockville MD to Discuss License Termination Plan That Myap & Contractors Are Preparing as Part of Decommissioning of Myaps ML20210P1311999-08-11011 August 1999 Notification of 990823 Meeting with Maine Yankee Atomic Power Co in Rockville,Md to Discuss License Termination Plan That Util & Contractors Preparing as Part of Decommissioning of Maine Yankee Atomic Power Station ML20212H9551999-06-23023 June 1999 Notification of 990707 Meeting with Myap in Rockville, Maryland to Discuss License Termination Plan for Maine Yankee Atomic Power Station ML20196E1351999-06-23023 June 1999 Notification of 990707 Meeting with Util in Rockville,Md to Discuss License Termination Plan for Plant ML20207A6481999-05-19019 May 1999 Discusses Director Review of Plant Backfit Claim Re beyond- design-basis SFP Accidents & NRR Staff Response to Backfit Review Panel Findings ML20206H1571999-05-0606 May 1999 Notification of 990525 Meeting with Util in Rockville,Md to Discuss License Termination Plan That MYAPC & Contractors Preparing as Part of Decommissioning of Maine Yankee Atomic Power Station ML20207G2921999-03-0404 March 1999 Provides Status on Wits Item 9600184, Clarity & Intent of NRC Safety Guide 1, as It Related to Isat Insp of Maine Yankee Atomic Power Station ML20196D5271998-11-24024 November 1998 Notification of 981215 Meeting for Docket 7200030 with Myap in Rockville,Md,To Discuss Plans for General License to Store Spent Fuel at Onsite ISFSI ML20155C3891998-10-29029 October 1998 Notification of 981102 Meeting with Util in Rockville,Md to Discuss industry-wide Power Reactor Decommissioning Issues as Well as Status of Plant Licensing Action ML20195C3941998-10-28028 October 1998 Discusses Results of Backfit Review Panel Re Emergency Preparedness Requirements for Maine Yankee Panel Determined That Staff Not Imposed Backfit on Licensee.Other Issues, Which Arose During Panel Deliberations,Identified & Encl ML20154L1371998-10-14014 October 1998 Notification of 981109 Meeting W/Util to Present NRC Staff Overview of Mgt of Decommissioning of Maine Yankee Atomic Power Station,Including Proposed Schedule ML20237B3941998-08-11011 August 1998 Forwards Hg Brack s Re Grossly Careless NRC Oversight of Licensees.Copy of Response to Brack Ltr Will Be Provided ML20236V9151998-07-31031 July 1998 Notification of 980814 Meeting W/Util Re Proposed License Defueled Security Plan ML20237A7521998-07-31031 July 1998 Notification of Cancelled 980814 Meeting W/Util in Rockville,Md to Discuss Proposed Plant Defueled Security Plan ML20236F6531998-06-30030 June 1998 Notification of 980710 Meeting W/Maine Yankee in Rockville,Md to Provide Myap Opportunity to Discuss Appeal of NRC Backfit Determination Re Maine Yankee Emergency Preparedness Exemption Request ML20248M0341998-06-0909 June 1998 Informs of Appointment to Backfit Review Panel to Review 980506 Appeal Filed by Myap Re NRC Determination Involving Backfit Claim Made by Licensee Under 10CFR50.109.Util Requests for Exemption from EP Requirements Unwarranted ML20248A4391998-05-26026 May 1998 Notification of 980609 Meeting W/Util in Rockville,Md to Discuss Maine Yankee Spent Fuel Heatup Analysis in Support of Emergency Plan & Financial Protection Exemption Requests ML20247N3471998-05-0808 May 1998 Responds to 980126 Memo Requesting Action Taken as Result of Event Inquiry - Public Concerns W/Nrc Rept of Independent Safety Assessment at Plant ML20247N3001998-05-0505 May 1998 Responds to 980210 Memo Re Event Inquiry Involving Public Concerns W/Nrc Rept of Independent Safety Assessment at Plant ML20217K4941998-04-28028 April 1998 Notification of 980501 Meeting W/Licensee in Rockville,Md to Discuss Defueled Security Plan ML20217M6221998-04-28028 April 1998 Notification of 980501 Meeting W/Util in Rockville,Md to Discuss Util Defueled Security Plan.Meeting Cancelled ML20216C4421998-04-0808 April 1998 Notification of 980423 Predecisional Enforcement Conference W/Myap in King of Prussia,Pennsylvania to Discuss Apparent Violations Identified During Three Investigations Conducted by Oi,As Transmitted on 971219 to Myap ML20199B2621998-01-13013 January 1998 Notification of Significant Licensee Meeting 98-02 W/Util on 980128 to Discuss Licensee Approach to Upcoming Decontamination of Reactor Sys,Design for Sf Island Concept & Use of 10CFR50.59 for Sys Safety re-classification ML20198P7321998-01-12012 January 1998 Notification of 980121 Meeting W/Util in Rockville,Md to Discuss Proposed Plant Defueled Security Plan ML20199C2241997-11-12012 November 1997 Notification of 971125 Meeting W/Maine Yankee Atomic Power Co in Rockville,Md to Discuss Proposed Maine Yankee Atomic Power Station Defueled Technical Specifications ML20198S9401997-11-0606 November 1997 Notification of 971120 Meeting W/Util in Rockville,Md to Discuss Proposed Myaps Defueled TSs ML20217G4061997-10-0707 October 1997 Notification of 971106 Meeting W/Licensee in Wiscasset,Me to Solicit Public Comments on Plant Post Shutdown Decommissioning Activities Rept.Meeting Agenda Encl ML20211G0331997-09-29029 September 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970609-12 IR 05000309/19970041997-09-29029 September 1997 Forwards NRC Operator Licensing Exam Rept 50-309/97-04OL (Including Completed & Graded Tests) for Tests Administered on 970609-12 ML20217E1631997-09-26026 September 1997 Revised Notification W/Agenda Change of 971007 Public Meeting in Wiscasset,Maine,To Brief Public on Regulatory Process for Decommissioning of NPP ML20217E2741997-09-24024 September 1997 Requests That Mk Webb Be Added to Site Access Authority.Site Access Were Completed & Thus Capable of Safe Conduct in Radiologically Restricted Areas ML20217C1381997-09-22022 September 1997 Notification of 971007 Meeting W/Public in Wicasset,Maine to Discuss Regulatory Process for Decommissioning of Npp. Meeting Held in Response to Recent Announcement by Myapco to Permanently Cease Operation of Myaps ML20217B0741997-09-0303 September 1997 Notification of 970903 Meeting W/Maine Yankee Atomic Power Co in Rockville,Md to Discuss Independent Sf Storage Installation Options Available to Maine Yankee for Storage of Sf.Notice Being Reissued to Revise Meeting Room Number ML20216A9881997-08-29029 August 1997 Notification of 970911 Meeting W/Util in Rockville,Md to Discuss Independent Spent Fuel Storage Installation Options Available to Plant for Storage of Spent Fuel ML20210Q7291997-08-21021 August 1997 Forwards OIG Audit Rept Entitled, NRC Needs Comprehensive Plan to Resolve Regulatory Issues. Rept Reflects Results of OIG Audit of Agency Response to Events at Plants ML20217K8121997-08-13013 August 1997 Notification of 970820 Meeting W/Util in Rockville,Md to Discuss Decommissioning Activities ML20148D1731997-05-23023 May 1997 Forwards Maine Yankee Restart Action Plan for Review & Approval in Accordance W/Nrc Inspection Manual Chapter 0350. RAP Contains List of Issues That NRC Will Inspect to Assess Licensee Compliance W/Applicable Requirements.W/O Encl ML20148D1701997-05-23023 May 1997 Notification of Significant Licensee Meeting 97-58 W/Util on 970606 in King of Prussia,Pa to Discuss Licensee Approach to Resolve Cable Separation Issues at Plant ML20236N2211997-05-0505 May 1997 Discusses Interpretation of Plant TS Re Acceptability of Grab Sampling on Leakage Detection Sys within Meaning of TS 3.14A ML20137U0031997-04-10010 April 1997 Forwards Proposed Response to Ltr from H Myers & Informs of No Need for Further Commission Review ML20137M6141997-04-0303 April 1997 Submits Documents Being Released to Public Re DSI-11, Operating Reactor Program Oversight ML20137H4361997-03-24024 March 1997 Notification of Significant Licensee Meeting 97-31 W/Util on 970403 in Wiscassett,Me to Discuss Plant Restart Readiness Plan as Documented in to NRC ML20137E2041997-03-24024 March 1997 Requests Copy of Maine Yankee Restart Readiness Plan & 10CFR50.54(f) Response ML20137H4341997-03-24024 March 1997 Notification of Significant Licensee Meeting 97-30 W/Util on 970403 in Wiscasett,Me to Discuss Plant Restart Readiness Plan as Documented in to NRC ML20136F9561997-03-13013 March 1997 Notification of 970320 Meeting W/Licensee to Discuss Proposed TS Change 194 Re Operation W/Reduced Reactor Coolant Sys Flow Rate ML20136F9651997-03-13013 March 1997 Notification of 970326 Meeting W/Licensee in Rockville,Md to Discuss SG Insp Plans & Contingencies ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20136F2431997-02-27027 February 1997 Notification of Significant Licensee Meeting 97-21 W/Util on 970311 to Discuss Apparent Violations Identified in Listed NRC Insp Repts ML20138M2431997-02-21021 February 1997 Staff Requirements Memo Re Briefing by Maine Yankee & NRC on 970204 Concerning Status of Corrective Actions at Facility ML20137M8101997-02-18018 February 1997 Informs That Paper Very Difficult to Get One Arms Around in Part Because It Tries to Deal Simultaneously W/Licensing, Insp & Performance Assessment in Each of Options & in Part Because Paper Implicit Assumption Ongoing Millestone. 1999-08-27
[Table view] |
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November 7, 1985 Docket No. 50-309 DISTRIBUTION:
Docket f1)e4 MEMORANDUM FOR: Hugh L. Thompson, Jr., Director NRC PDR Division of Licensing L PDR ORB #3 Rdg Robert M. Bernero, Director GClainas Division of Systems Integration EJButcher PMKreutzer James P. Knight, Acting Director Division of Engineering William T. Johnston, Acting Director Division of Human Factors Safety Themis P. Spets, Director i Division of Safety Technology 4
THRU: Edward J. Butcher, Acting Chief Operating Reactors Branch #3
[
Division of Licensing Gus C. Lainas, Assistant Director r for Operating Reactors Division of Licensing FROM: Patrick M. Sears, Project Manager Operating Reactors Branch No. 3 Division of Licensing
SUBJECT:
DRAFT NRR SALP INPUT FOR MAINE YANKEE Enclosed is a draft of the NRR input to the SALP review for Maine Yankee.
The draft report is based partly upon input from selected staff personnel who have substantial contact and involvement with Maine Yankee licensing material. Please review the draft evaluation and provide any comments you feel appropriate. In particular, any comments from your reviewers who are currently doing work on fire protection for Maine Yankee will be appreciated. '
All connents received by November 12, 1985 will be considered in the final i report. Your coments may be provided verbally due to the short turn-around
' time. Please note that the licensee was evaluated to be a. Category 2.
ii 7 /s/
i Patrick M. Sears, Project Manager ppR l
k120104hoo0309 o
ADOCK Operating Reactors Branch #3 Division of Licensing l
Enclosure:
As stated cc w/ enclosure -
l L. S. Rubenstein ORB #$:DL ORB #3:DL ORB #3 OR I e6tzer PSears:dd EJBu4her GC ainas l PVg/c/85 ly 19/ 4 /85 10/b/85 10/f/85 l
Enclosure 1 Detailed Review - Licensing Activities i
Facility Name: Maine Yankee Atomic Power Plant .
i Licensee: Maine Yankee Atomic Power Company Evaluation Period: July 1, 1984 to October 31, 1985 i NRR Project Manager: Patrick Sears I. INTRODUCTION This report represents the results of an evaluation of the licensee in the functional area of " Licensing Activities." It is intended to provide NRR's input to the SALP review process as described in NRR Office Letter No. 44
- dated January 3,1984, and NRC Manual Chapter 0516.
II.
SUMMARY
OF RESULTS i NRC Manual Chapter 0516 specifies that each functional area evaluated will be assigned a performance category (category 1, 2, or 3) based on a composite of a number of attributes. The performance of Maine Yankee Atomic Power Company is rated category 2.
III. CRITERIA The evaluation criteria used in this assessment are given in NRC Manual Chapter 1
0516 Appendix, Table 1, Evaluation Criteria with Attributes for Assessment of Licensee Perfomance.
IV. METHODOLOGY This evaluation represents the integrated inputs of the Operating Reactor Project Manager (ORPM) and those technical reviewers who expended significant amounts l of effort on Maine Yankee Atomic Power Plant licensing actions during the current rating period. Using the guidelines of NRC Manual Chapter 0516, the l ORPM and each reviewer applied specific evaluations to the relevant licensee
. perforinance criteria, as delineated in Chapter 0516, and assigned an overall rating category (1, 2 or 3) to each criterion. The reviewers included this inforination as part of each Safety Evaluation Report transmitted to the Division of Licensing. The ORPM, after reviewing inputs of the technical reviewers, com-bined this infomation with his own assessment of the licensee performance and, using appropriate weighting factors, arrived at a composite rating for the licensee. This rating alsc reflected the coments of the NRR Senior Executive assigned to the Maine Yankee Atomic Power Plant SALP assessment. A written evaluation was then prepared by the ORPM and circulated to NRR management for coments.
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The basis for this appraisal was the licensee's performance in support of licensing actions that were completed during the current rating period.
These actions consisted of amendment requests, exemption requests, responses to generic letters, TMI items and other actions and are as follows:
Licensing Action TAC Number Seismic & Other Qualifications 52173 on 8" Vent / Purge Valve Emergency Exercise Exemption Request 54431 Appendix I Tech Spec Implement Review 07752 Environmental Qualification of Safety 42490 Related Electric Equipment Seismic Qualification of AFW System 43653 Fire Protection 48582 Appendix J Tech Spec Change 48632 Detailed Control Room Design 51173 Review Program 2nd ISI Interval 52011 Control of Heavy Loads 52241 Post Trip Review Program 52277 Description & Procedures ,
Preventive Maintenance Program 52130 Reactor Trip Breakers Fire Protection-Extra 53408 Exemption Requests Revised Definition of 53449 Containment Integrity Tech Specs Covered By 54543
, Generic Letters 83-36 & 83-37 (0737)
Thermal Shield Inspection 54958 and Repair
Licensing Action TAC Number LTOP 54959 Neutron Source Data for 55044 Flux Reduction Verification Cask In Spent Fuel Pool 55092 Proposed Change 105 55296 Power Supplies For Safe Shutdown 56099 CEA Ejection Analysis 56775 Revised Confirmatory Order 56818 Backfit Determination 58016
- 'For AFWS Turbine Driven Pump -
Backfit Determination - Testing 58017 Frequency of Auto Initiation Logic Emergency Feedwater Pump Cycle 9 Core Performance 58031 Tech Specs V. ASSESSMENT OF PERFORMANCE The licensee's performance evaluation is based on a consideration of five of the seven criteria specified in NRC Manual Chapter 0516. These are: ;
Management Involvement and Control in Assuring Quality
- Approach to Resolution of Technical Issues from a Safety Standpoint
- Responsiveness to NRC Initiatives
- Staffing Reportable Events In addition to the above, Housekeeping and Control Room Behavior are also discussed.
Fortheremainingtwocriteria(enforcementandtraining),nobasisexists for an NRR evaluation for the functional area of Licensing Activities for Maine Yankee. Conversations with the Resident Inspector at Maine Yankee indicate an overall rating of Category 2 for these two criteria.
l A. Management Involvement and Control in Assuring Quality During the present rating period the licensee's management demonstrated active participation in licensing activities and kept abreast of all current and anticipated actions. During the review of Item II.B.3.2 of NUREG-0737, " Post Accident Sampling Modification," there was consistent evidence of prior planning and assignment of priorities. Certain other submittals, for example " Steam Tube Surveillance", submittals were not complete in the original and as a con-sequence time was lost unnecessarily. In general, submittals reflect good quality and proper management control to assure quality. The timeliness of however fails to receive proper prioritization and quite often such submittals are late. In particular responses to staff questions should receive more management control to assure timely submittals. The technical reviewers, overall, have rated the licensee close to 2 in this category for reviews com-pleted during this SALP period.
On the basis of these observations and reviewer input, a rating of Category 2 is
- assigned to this criterion.
B. Approach to Resolution of Technical Issues from a Safety Standpoint The licensee's management and its staff have demonstrated technical understanding of issues involving licensing actions. For the majority of licensing actions, the licensee's submittals are technically sound, thorough, and well referenced.
They generally exhibit conservatism when considering safety significance, how-ever resolutions are quite often delayed. During the review of the Cycle 9 Core Perfonnance Technical Specification changes, the licensee was very responsive to questions posed by the reviewer. The reviewers, overall, have rated the licensee very close to 2 in this category for reviews completed during this SALP period.
On the basis of these observations and reviewer input, a rating of Category 2 is I assigned to this criterion.
C. Responsiveness to NRC Initiatives The licensee's responsiveness appears to vary widely on different technical issues. For example, the submittal concerning the technical specification change on snubbers was significantly delayed by the licensee. The resubmittal concerning Technical Specifications for Limiting Overtime is approximately four months over-due because of staffing problems. Other actions such as Environmental Qualifica-tion of Safety Related Electrical Equipment, Detailed Control Room Design Review and Main Steam Line Break Report had no timeliness problems.
The technical reviewers have rated the licensee close to an overall 2 in this category.
Based on the above observations and reviewer input, a rating of Category 2 is assigned to this criterion.
i :
j D. Reporting and Analysis of Reportable Events I
i The licensee has been prompt and open in reporting reportable events. For example, several Rosemont Transmitters were found not to have been installed in complete agreement with the equipment qualification test configuration.
The licensee promptly reported the condition, searched for like conditions and j brought the installation of the transmitters into agreement with the equipment
- qualification test configuration. In remedying the installation, however, the licensee did ask the question "what would have been the consequences of this l
situation had it gone undiscovered and a design accident occurred." Thus the
! analysis was left to much later when the imediate circumstances were not repro-
! ducible.
Based on the above, a rating of Category 2 is assigned this criterion.
E. Staffing
! During the appraisal period the licensee rotated two licensing staff personnel l who were directly involved with Maine Yankee. In the NRC project manager's j -- judgement it was the perturbation caused by these losses which caused some of -
the delay in responding to NRC. The licensee's current level of staff appears j to be adequate and the caliber of personnel is excellent. i i
Based on the above considerations only, the rating of Category 2 is assigned j to this criterion.
F. Housekeeping and Control Room Behavior ;
I Housekeeping and Control Room Behavior is a functional area that is dicusssed i elsewhere in the NRC evaluation. However NRR has continuing interest in this area since good housekeeping practices and formal behaviors within the control
! room indicate that the licensee and its employees take pride in their facilities
- and in their jobs. During site visits, it has been observed that an orderly and
+
clean working environment is maintained, which indicates good housekeeping practices. Operations personnel have exhibited professional behavior with the
, control room clean and orderly. During a fueling outage, it appeared that the usual construction / modification clutter was being kept to a minimum.
t l Overall rating for this criterion is Category 1.
! V. Conclusion In general, the licensing functions for Maine Yankee are carried out in an adequate manner. Better coordination of licensing activities to avoid late i responses should be pursued. While there were delays in getting responses l to some licensing actions, the licensee exhibits a willingness to be respon-l sive and to improve perfonnance.
The time (3 months) allowed for fuel reload submittals is critical. Any '
j staff concerns must be resolved in a pressure type atmosphere. Because
of this it is strongly recomended that reload submittals be filed at least 5 months prior to projected restart after a reload outage.
A complete performance rating of Category 2 has been assigned by the NRR SALP ~
j evaluational effort for the current rating period.
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Enclosure 2 SALP EVALUATION FOR .
MAINE YANKEE AYUMTC POWER STATION .
SUPPORTING DATA AND
SUMMARY
- 1. NRR LICENSEE MEETINGS November 28, 1984 Reactor Coolant Pump Trip Discussion February 5,1985 Seismic Design Review February 6,1985 Briefing for Incoming Director of Division of Licensing on Status of Maine Yankee February 7, 1985 Discussion of Radiological Effluent Technical Specifications (RETS)
~~
February 12, 1985 Discussion of Emergency Operating Procedures February 14, 1985 Discussion of Small Break LOCA and RCP Trip Modeling March 11, 1985 Discussion of Fire Protection Issues at Maine Yankee March 11, 1985 Discussion of Low Level Waste Management at Maine Yankee March 14, 1985 Further Discussion of RETS March 18, 1985 Meeting with Florida Public Counsel Concerning Thernal Shield at Maine Yankee May 8, 1985 Discussions Concerning Offsite Power Supplies August 12, 1985 Maine Yankee Generic Fuel Load Presentation August 22, 1985 Management Meeting Concerning Maine Yankee Turbine Driven Auxiliary Feedwater Pump Backfit Claim
(
~
t s > 1 September 20, 1985 Maine Yankee Presentation Concerning Two Common Mode Problems with Steam Generator Pressure Indication
- 2. NRR SITE VISITS .
October 30 31, 1984 Management Meeting November 9, 1984 SALP Meeting With Licensee January 16-17, 1985 RETS Meeting March 13-14, 1985 Final RETS Meeting June 7-8, 1985 Plant Familiarization September 18-19, 1985 Concrete Block Wall Inspection
- 3. COMMISSION BRIEFINGS
- None 1 -
- 4. SCHEDULAR EXTENSIONS GRANTED None 5.
RELIEFS GRANTED None
- 6. EXEMPTIONS GRANTED None .
- 7. LICENSE AMENDMENTS ISSUED License Amendment No. 79 Technical Specifications (TS) Modification concerning Manning of Shift and License Event Reporting License Amendment No. 80 TS Modification to Ensure Containment Integrity License Amendment No. 81 TS Modificatita Concerning Operational Safety Instrumentation, Control Systems, and Accident Monitoring Systems License Amendment No. 82 TS Modification Concerning Reactor Containment Integrity l
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License Amendment No. 83 TS Changes concerning Modifications to add a Variable Setpoint to the Low Temparature Overpressure Protection System. -
License Amendment No. 84 TS Changes to require more extensive-inspection of Steam Generator Tubes in Critical Areas.
License Amendment No. 85 TS Changes to Reflect Power Distributions, Insertion Limits, Peaking Factors, and other characteristics for Cycle 9 Fuel Reload.
- 8. EMERGENCY TECHNICAL SPECIFICATIONS ISSUED None
- 9. ORDERS ISSUED Order Confirming revisions to Licensee commitments to implement Post TMI related items set forth in NUREG-0737 Supplement 1.
- 10. Exemptions Granted Exemption granted for compliance to a certain requirenent of Subsection III.G.2 of Appendix R to 10 CFR 50 concerning separation in the Reactor Containment Incore Instrumentation Area & Lower Pressurizer Cubicle.
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