|
---|
Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20211A4361999-08-18018 August 1999 Notification of Significant Licensee Meeting 99-47 with Entergy Nuclear,Inc on 990831 to Discuss Results of NRC Plant Performance Review of Pilgrim Nuclear Power Station Issued on 990409 ML20212H7621999-06-22022 June 1999 Notification of 990701 Meeting with NEI & Entergy in Rockville,Md to Discuss Price-Anderson Issues Re Transfer of Pilgrim License from Beco to Entergy ML20205L0301999-04-0909 April 1999 Notification of 990413 Meeting with Boston Edison Co & Entergy Nuclear Generation Co in Rockville,Md to Discuss Sale & Transfer of Pilgrim Station from Boston Edison Co to Entergy Nuclear Generation Co ML20196J5801998-12-0707 December 1998 Notification of 981209 Meeting with Representatives of Beco & Entergy in Rockville,Md to Discuss Sale of Pilgrim Plant ML20196F3461998-12-0202 December 1998 Forwards Info Re Operator Licensing Exam Administered on 981016-23 at Pilgrim Station,For Distribution Under Rids Code IE42 ML20196F5611998-12-0202 December 1998 Forwards Info Re OL Exam Administered on 981016-23 at Pilgrim Station,For Distribution Under Rids A070 ML20154D5091998-10-0202 October 1998 Notification of Meeting W/Beco on 981008 in Rockville,Md to Discuss Core Spray Piping Integrity ML20154G5141998-10-0202 October 1998 Notification of 981008 Meeting W/Beco in Rockville,Md to Discuss Core Spray Piping Integrity.Meeting Has Been Rescheduled to 981015 ML20247G2441998-04-15015 April 1998 Notification of Significant Licensee Meeting 98-34 W/Util on 980427 to Discuss Weaknesses in Licensee Alarm Assessment Program (EA 98-191) ML20203E2781998-02-19019 February 1998 Notification of Significant Licensee Meeting 98-18 W/Util in King of Prussia,Pa on 980310 Re Plant Design Basis Project Discussion ML20199C7581997-10-31031 October 1997 Notification of Significant Licensee Meeting 97-112 W/Util on 971113 to Discuss NRC SALP ML20212D6201997-10-28028 October 1997 Notification of Licensee Meeting on 971121 W/Util in King of Prussia,Pa to Discuss Apparent Violations Identified During NRC Insp 50-293/97-05 ML20140F6151997-06-11011 June 1997 Notification of 970612 Meeting W/Util in Rockville,Md to Discuss Net Positive Suction Head for ECCS Pumps ML20137Q9761997-03-31031 March 1997 Informs That as-found LOCA & Life Testing & Analysis Does Not Provide Acceptable Approach for Demonstrating Qualification at Accident Temp Higher than 340F,per 970110 TAR ML20137B4781997-03-14014 March 1997 Undated Memo Discussing Beco Reorganization ML20141A7361997-03-12012 March 1997 Rcommends That Key RES Staff Attend Subcommittee Meetings to Address Any Questions,Arise in Discussions Among Members & to Answer Any Key Questions Posed in Advance by Subcommittee Chairmen ML20149M3291996-11-12012 November 1996 Forwards Input Re TIA on Plant Licensing Basis & Subsequent Mod Under 10CFR50.59 for Two Safety Significant Problems ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20129D8331996-09-19019 September 1996 Notification of 961003 Predecisional Enforcement Conference 96-98 W/Util to Discuss Containment Penetration Protection. Meeting Closed to Public ML20134J7301996-07-26026 July 1996 Forwards Resolution of Spent Fuel Storage Pool Action Plan Issues Re Response to Two Postulated Event Sequences Involving SFP NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl IR 05000293/19930291993-11-23023 November 1993 Notification of Significant Licensee Meeting 93-156 W/Util on 931202 Re Three Recently Reported Design Issues in Insp Rept 50-293/93-29 ML20058C9711993-11-22022 November 1993 Notification of Significant Licensee Meeting 93-150 W/Util on 931217 Re Hpci/Rcic Reliability & Switchyard Betterment Status ML20059L9721993-11-12012 November 1993 Licensing Board Memorandum & Order Terminating Proceeding .* Informs That Time Provided by NRC Regulation to Review Decision of ASLB Terminating Proceeding in Docket Has Expired.W/Certificate of Svc.Served on 931112 ML20056C4721993-06-17017 June 1993 Discusses Util Assessment of Low Pressure Turbine Analysis. Licensee Retained Structural Integrity Assocs,Inc (SIA) to Evaluate Flaw Indications in 7GA Disk.Sia Anaylsis Reduce Some Obvious Conservatisms Used in GE Analysis ML20128F3911993-02-0303 February 1993 Requests Listed Instructions to Ensure That P Blanch of Northeast Utils & E Hadley of We the People Kept Promptly Informed of NRC Activities on BWR Water Level Indicators & Rosemount Transmitters ML20128E2181993-01-26026 January 1993 Notice of Significant Licensee Meeting 93-11 W/Licensee on 930225 in King of Prussia,Pa to Discuss Util Reorganization ML20059C1171992-11-20020 November 1992 Submits Status Rept on Reactor Water Level Spiking That Occurred on 921024.Related Info Encl ML20125D1161992-10-0707 October 1992 Notification of Significant Licensee Meeting 92-177 W/Util on 921217 to Discuss tie-in of New Security Computer ML20082B1581991-02-20020 February 1991 Summarizes Telcon W/R Murphy Re Mobilization Time for State of Ma Natl Guard Personnel Assigned to Respond to Wellesley, Ma Reception Ctr & State of Ma Civil Defense Agency Area II Headquarters in Event of Emergency at Facility ML20062H5361990-11-23023 November 1990 Forwards Info from Pilgrim Citizens Radiological Monitoring Network,Covering Rept Periods 900910-1017 ML20059P0861990-10-0101 October 1990 Notification of Significant Licensee Meeting 90-118 W/Util on 901016 to Discuss SALP ML20059L1541990-09-0707 September 1990 Notification of Significant Licensee Meeting 90-114 on 900912 at Region I Ofc to Discuss Corrective Actions & Restart Planning Re 900902 Manual Reactor Scram ML20059G4681990-08-0606 August 1990 Forwards Citizens Radiological Monitoring Network Weather Data Rept for Apr-Jul 1990 for Processing Through Nudocs Sys ML20127B4901990-08-0303 August 1990 Responds to 900726 Request for Recommendations for Appropriate Actions in Response to Inspector General Rept 90N-02 ML20127B4961990-08-0101 August 1990 Advises That Staff Did Not Conduct Thorough Review of Offsite Emergency Preparedness Which Resulted in Inaccurate Info Being Provided to Commission ML20058B4501990-06-28028 June 1990 Provides Status Rept Re Progress of off-site Emergency Preparedness Activities at Facility ML20055C2661990-02-0505 February 1990 Forwards Draft Ltr to Util Re Completion of Plant Power Ascension Program.Ltr Will Be Issued on 900209 Which Will Accept Util Completion of Power Ascension Program & Close Out Confirmatory Action Ltr CAL-86-10 ML20248C5841989-09-26026 September 1989 Notification of Significant Licensee Meeting 89-154 W/Util on 891006 in Plymouth,Ma to Discuss SALP Mgt ML20247N0121989-09-12012 September 1989 Forwards Plant Status Rept for 890826-0908.On 890830,reactor Automatically Scrammed Due to Fault on Main Generator Voltage Regulation Circuitry.On 890905,inadvertent Actuation LPCI Loop Select Logic Experienced ML20246N5751989-08-30030 August 1989 Forwards Plant Biweekly Status Rept for 890812-25 ML20245F6401989-08-0101 August 1989 Forwards Facility Biweekly Status Rept for 890715-28.NRC Restart Staff in Place & Onsite Monitoring Licensee Activities on Extended day-shift Basis During Reporting Period ML20247C0631989-07-19019 July 1989 Forwards Biweekly Status Rept for 890701-14.NRC Restart Staff in Place & Onsite & Monitoring Licensee Activities on around-the-clock Basis During Plant Startup & Power Ascension.Part 21 Related ML20247C1611989-07-14014 July 1989 Notification of Significant Licensee Meeting 89-112 W/Util on 890816 in King of Prussia,Pa to Discuss SALP ML20247E4531989-07-10010 July 1989 Forwards Plant Status Rept for 890617-30 Period.Rept Intended to Provide NRC Mgt & Public W/Overview of Plant Activities & NRC Restart Insp Activities ML20246K1141989-07-0303 July 1989 Notification of Significant Licensee Meeting 89-105/suppl Enforcement Conference Re Augmented Insp Team Findings Concerning 890412 Reactor Core Isolation Cooling Sys Overpressurization ML20245E6561989-06-22022 June 1989 Forwards Plant Biweekly Status Rept for 890603-16.On 890616, Reactor Operating at Approx 25% Power w/turbine-generator Synchronized to Grid.On 890612,util Commenced Controlled Reactor Shutdown to Perform Minor Mods,Maint & Testing ML20245F9581989-06-16016 June 1989 Notification of Significant Licensee Meeting 89-096 W/Util on 890619 in King of Prussia,Pa Re 890412 RCIC Sys ML20245A3311989-06-0909 June 1989 Notification of Significant Licensee Meeting 89-90 on 890627 W/Util in King of Prussia,Pa for Mgt Meeting to Discuss Status of Licensee Radiation Control Program ML20244E5081989-06-0707 June 1989 Forwards Biweekly Status Rept for 890520-0602.Rept Provides Overview of Plant Activities & NRC Restart Insp Activities. Part 21 Related 1999-08-18
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20211A4361999-08-18018 August 1999 Notification of Significant Licensee Meeting 99-47 with Entergy Nuclear,Inc on 990831 to Discuss Results of NRC Plant Performance Review of Pilgrim Nuclear Power Station Issued on 990409 ML20212H7621999-06-22022 June 1999 Notification of 990701 Meeting with NEI & Entergy in Rockville,Md to Discuss Price-Anderson Issues Re Transfer of Pilgrim License from Beco to Entergy ML20205L0301999-04-0909 April 1999 Notification of 990413 Meeting with Boston Edison Co & Entergy Nuclear Generation Co in Rockville,Md to Discuss Sale & Transfer of Pilgrim Station from Boston Edison Co to Entergy Nuclear Generation Co ML20196J5801998-12-0707 December 1998 Notification of 981209 Meeting with Representatives of Beco & Entergy in Rockville,Md to Discuss Sale of Pilgrim Plant ML20196F3461998-12-0202 December 1998 Forwards Info Re Operator Licensing Exam Administered on 981016-23 at Pilgrim Station,For Distribution Under Rids Code IE42 ML20196F5611998-12-0202 December 1998 Forwards Info Re OL Exam Administered on 981016-23 at Pilgrim Station,For Distribution Under Rids A070 ML20154G5141998-10-0202 October 1998 Notification of 981008 Meeting W/Beco in Rockville,Md to Discuss Core Spray Piping Integrity.Meeting Has Been Rescheduled to 981015 ML20154D5091998-10-0202 October 1998 Notification of Meeting W/Beco on 981008 in Rockville,Md to Discuss Core Spray Piping Integrity ML20247G2441998-04-15015 April 1998 Notification of Significant Licensee Meeting 98-34 W/Util on 980427 to Discuss Weaknesses in Licensee Alarm Assessment Program (EA 98-191) ML20203E2781998-02-19019 February 1998 Notification of Significant Licensee Meeting 98-18 W/Util in King of Prussia,Pa on 980310 Re Plant Design Basis Project Discussion ML20199C7581997-10-31031 October 1997 Notification of Significant Licensee Meeting 97-112 W/Util on 971113 to Discuss NRC SALP ML20212D6201997-10-28028 October 1997 Notification of Licensee Meeting on 971121 W/Util in King of Prussia,Pa to Discuss Apparent Violations Identified During NRC Insp 50-293/97-05 ML20140F6151997-06-11011 June 1997 Notification of 970612 Meeting W/Util in Rockville,Md to Discuss Net Positive Suction Head for ECCS Pumps ML20137Q9761997-03-31031 March 1997 Informs That as-found LOCA & Life Testing & Analysis Does Not Provide Acceptable Approach for Demonstrating Qualification at Accident Temp Higher than 340F,per 970110 TAR ML20137B4781997-03-14014 March 1997 Undated Memo Discussing Beco Reorganization ML20141A7361997-03-12012 March 1997 Rcommends That Key RES Staff Attend Subcommittee Meetings to Address Any Questions,Arise in Discussions Among Members & to Answer Any Key Questions Posed in Advance by Subcommittee Chairmen ML20149M3291996-11-12012 November 1996 Forwards Input Re TIA on Plant Licensing Basis & Subsequent Mod Under 10CFR50.59 for Two Safety Significant Problems ML20129K2561996-11-0505 November 1996 Notification of Significant Licensee Meeting 96-109 W/Listed Attendees on 961202-03 in Philadelphia,Pa to Provide Training,Resolve Interagency Exercise Scheduling Conflicts & Discuss Current Issues in Emergency Preparedness ML20129D8331996-09-19019 September 1996 Notification of 961003 Predecisional Enforcement Conference 96-98 W/Util to Discuss Containment Penetration Protection. Meeting Closed to Public ML20134J7301996-07-26026 July 1996 Forwards Resolution of Spent Fuel Storage Pool Action Plan Issues Re Response to Two Postulated Event Sequences Involving SFP NUREG-1299, Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl1994-06-29029 June 1994 Forwards Continuation of Curtiss Papers to Be Filed Under Commission Correspondence in Pdr.Advanced Copy Sent to Pdr. List of Documents Included in Four Boxes Encl IR 05000293/19930291993-11-23023 November 1993 Notification of Significant Licensee Meeting 93-156 W/Util on 931202 Re Three Recently Reported Design Issues in Insp Rept 50-293/93-29 ML20058C9711993-11-22022 November 1993 Notification of Significant Licensee Meeting 93-150 W/Util on 931217 Re Hpci/Rcic Reliability & Switchyard Betterment Status ML20059L9721993-11-12012 November 1993 Licensing Board Memorandum & Order Terminating Proceeding .* Informs That Time Provided by NRC Regulation to Review Decision of ASLB Terminating Proceeding in Docket Has Expired.W/Certificate of Svc.Served on 931112 ML20056C4721993-06-17017 June 1993 Discusses Util Assessment of Low Pressure Turbine Analysis. Licensee Retained Structural Integrity Assocs,Inc (SIA) to Evaluate Flaw Indications in 7GA Disk.Sia Anaylsis Reduce Some Obvious Conservatisms Used in GE Analysis ML20128F3911993-02-0303 February 1993 Requests Listed Instructions to Ensure That P Blanch of Northeast Utils & E Hadley of We the People Kept Promptly Informed of NRC Activities on BWR Water Level Indicators & Rosemount Transmitters ML20128E2181993-01-26026 January 1993 Notice of Significant Licensee Meeting 93-11 W/Licensee on 930225 in King of Prussia,Pa to Discuss Util Reorganization ML20059C1171992-11-20020 November 1992 Submits Status Rept on Reactor Water Level Spiking That Occurred on 921024.Related Info Encl ML20125D1161992-10-0707 October 1992 Notification of Significant Licensee Meeting 92-177 W/Util on 921217 to Discuss tie-in of New Security Computer ML20082B1581991-02-20020 February 1991 Summarizes Telcon W/R Murphy Re Mobilization Time for State of Ma Natl Guard Personnel Assigned to Respond to Wellesley, Ma Reception Ctr & State of Ma Civil Defense Agency Area II Headquarters in Event of Emergency at Facility ML20062H5361990-11-23023 November 1990 Forwards Info from Pilgrim Citizens Radiological Monitoring Network,Covering Rept Periods 900910-1017 ML20059P0861990-10-0101 October 1990 Notification of Significant Licensee Meeting 90-118 W/Util on 901016 to Discuss SALP ML20059L1541990-09-0707 September 1990 Notification of Significant Licensee Meeting 90-114 on 900912 at Region I Ofc to Discuss Corrective Actions & Restart Planning Re 900902 Manual Reactor Scram ML20059G4681990-08-0606 August 1990 Forwards Citizens Radiological Monitoring Network Weather Data Rept for Apr-Jul 1990 for Processing Through Nudocs Sys ML20127B4901990-08-0303 August 1990 Responds to 900726 Request for Recommendations for Appropriate Actions in Response to Inspector General Rept 90N-02 ML20127B4961990-08-0101 August 1990 Advises That Staff Did Not Conduct Thorough Review of Offsite Emergency Preparedness Which Resulted in Inaccurate Info Being Provided to Commission ML20058B4501990-06-28028 June 1990 Provides Status Rept Re Progress of off-site Emergency Preparedness Activities at Facility ML20055C2661990-02-0505 February 1990 Forwards Draft Ltr to Util Re Completion of Plant Power Ascension Program.Ltr Will Be Issued on 900209 Which Will Accept Util Completion of Power Ascension Program & Close Out Confirmatory Action Ltr CAL-86-10 ML20248C5841989-09-26026 September 1989 Notification of Significant Licensee Meeting 89-154 W/Util on 891006 in Plymouth,Ma to Discuss SALP Mgt ML20247N0121989-09-12012 September 1989 Forwards Plant Status Rept for 890826-0908.On 890830,reactor Automatically Scrammed Due to Fault on Main Generator Voltage Regulation Circuitry.On 890905,inadvertent Actuation LPCI Loop Select Logic Experienced ML20246N5751989-08-30030 August 1989 Forwards Plant Biweekly Status Rept for 890812-25 ML20245F6401989-08-0101 August 1989 Forwards Facility Biweekly Status Rept for 890715-28.NRC Restart Staff in Place & Onsite Monitoring Licensee Activities on Extended day-shift Basis During Reporting Period ML20247C0631989-07-19019 July 1989 Forwards Biweekly Status Rept for 890701-14.NRC Restart Staff in Place & Onsite & Monitoring Licensee Activities on around-the-clock Basis During Plant Startup & Power Ascension.Part 21 Related ML20247C1611989-07-14014 July 1989 Notification of Significant Licensee Meeting 89-112 W/Util on 890816 in King of Prussia,Pa to Discuss SALP ML20247E4531989-07-10010 July 1989 Forwards Plant Status Rept for 890617-30 Period.Rept Intended to Provide NRC Mgt & Public W/Overview of Plant Activities & NRC Restart Insp Activities ML20246K1141989-07-0303 July 1989 Notification of Significant Licensee Meeting 89-105/suppl Enforcement Conference Re Augmented Insp Team Findings Concerning 890412 Reactor Core Isolation Cooling Sys Overpressurization ML20245E6561989-06-22022 June 1989 Forwards Plant Biweekly Status Rept for 890603-16.On 890616, Reactor Operating at Approx 25% Power w/turbine-generator Synchronized to Grid.On 890612,util Commenced Controlled Reactor Shutdown to Perform Minor Mods,Maint & Testing ML20245F9581989-06-16016 June 1989 Notification of Significant Licensee Meeting 89-096 W/Util on 890619 in King of Prussia,Pa Re 890412 RCIC Sys ML20245A3311989-06-0909 June 1989 Notification of Significant Licensee Meeting 89-90 on 890627 W/Util in King of Prussia,Pa for Mgt Meeting to Discuss Status of Licensee Radiation Control Program ML20244E5081989-06-0707 June 1989 Forwards Biweekly Status Rept for 890520-0602.Rept Provides Overview of Plant Activities & NRC Restart Insp Activities. Part 21 Related 1999-08-18
[Table view] |
Text
.
ha nse
./ g
/ NUCLEAR RECULATCRY COMMISSION ADVISORY COMMITTEE ON REACTOR SAFEGUARD 4
- ,, WASHINGTON,o,c.aossa November 6, 1985 Mr. Raymond F. Fraley Executive Director Advisory Corrnittee for Reactor Safeguards t Washington, DC 20555
Dear Ray:
As you know, I spent last week serving as an observer on an INPO Team that was conducting an evaluation of the operations of the Pilgrim Nuclear Power Station in Plymouth, Mass.
Enclosed for your information is a report summarizing some of the results of this experience. I continue to be impressed by the quality and thoroughness of the INPO Team evaluations and highly recumend that other ACRS members consider joining such an exercise at some future date.
Sincerely yours.
Dade W. Moeller Ar,RS Member
Enclosure:
Report l
l l
I 8811160242 001010 P Og_g9B PDR NG L--
Dade W. Mceller November 2, 1985
$UMMARY REPORT Participation in !NPO Evaluation of the .
Pilgrim Nuclear Power Station October 28 - November 1,1985
!. Introduction Through arrant?ments made by Mr. William R. Kindley, Deputy Director, Radiological Protection and Emergency Preparedness Division, Institute of Nuclear Power Operations, I participated as an observer during the second week (October 28-November 1,1985) of their evaluation of the Pilgrim Nuclear Power Station in Plymouth, Mass. The Pilgrim Station is a single unit Boiling Water Reactor, and has a net electric generating capacity of 655 MW. The Station was operating at 100-percent power during our visit.
!!. The Evaluation Team The INPO Evaluation Team consisted of 16 numbers, plus the Team Leader, two observers (a representative from TVA at Browns Ferry and myself), and 3R0s from two other utilities (Quad Cities and Big Rock Point). Included among the Team Members was a vendor (GE) repre-sentative on assignment as a loanee to INPO. The average age of the Team members was 35 years and they had an average of 8 years of civilian nuclear power plant experience, plus 4 years of Nuclear Navy experience.
Half of the Team members had either an RO or SRO license at at least one connercial nuclear plant. Essentially every Team member had a bachelor's degree; sore had advanced degrees.
!!!. Conduct of the Evaluation Specific subject areas covered during the evaluation are shown in Table !. As is customary, the Team members had full access to the plant, with individual members being assigned specific subject areas to cover. Overhalfofthememberssuitedupinprotectiveclothing(some
2 wearing respirators) at least one time during the two weeks to ent /
contaminated areas for specific evaluations. -
At the end of each day, observations and concerns were shared among Team members during briefing sessions. This led in many cases to the coordination of observations by different Team members. If after subsequent discussion with the Station contact for the specific subject area (andafterthecontacthadhadanopportunityforrebuttal)the concerns were shown to be well substantiated, they were elevated to the level of preliminary "findings" and ma r art of the dreft Team report.
On Friday. November 1,1985, these "findings" and recomendations for action were oiscussed with the Station Manager and his Staff, again with 6n opportunity for rebattal, as appropriate. On the afternoon prior to this presentation, each finding was discussed on a preifminary and confimatory basis with Kenneth Strahm, Vice President end Director.
Training and Education Division, and with Will!am Wigley, Manager, Training Assistance Department, INPO, to assure that each was well founded and could be su'stantiated.
IV. Observations and Coments Sumarized below are my coments and observations on the Team evaluation. My coments are general since ! prefer to leave to the INPO Team the decisions on the assignments of ratings as to the performance of the Plant staff. In this regard, it is important to note that Team members based their evaluations both on observations of the Plant st&f?
in their work capacities, and on the written records maintained at the Station. Tasks underway, and the specific procedures perfot1ned at the request of the evaluation Team, were carefully reviewed and critiqued.
Throughout the visit, the Plant staff provided their full and complete cooperation.
i
]
1 3
1 My impressions of the pe;fonnance of the INPO evaluation Team wm very favorable. The Team members proved to be a spirited, hardworking. .
enthusiastic group. Departure from the hotel was routinely scheduled at 6:30 a.m., discussions at the Station extended beyond 6:00 p.m., and ,
I follow-up sessions continued at the hotel beyond 10:00 p.m. t l
1 In the way of specific connencs, I offer the following: ;
i l 1. The INPO objective of seeking excellence in plant perfonnance is clearly a guiding factor in their evaluations. Although I compliance with regulatory sta.1dards is clearly required, this is definitely below the ultimate quality b. Sought. I l
- 2. Although the objective is a thorough evaluation of plant '
performance, the INPO Team appeared tn 9nderstand the necessity to try to avoid overjhelming the Station staff with more l
recorrrendations than they could handle. In some cases this was handled by grouping several recoernendations under broad headings.
- 3. The INPO Team appeared clearly to recognize potential limitations on their findings and recomendations. Since the Team spent only two weeks at the plant, at best their observations were :
only a "snapshot" of total plant perfonnance. At the same time, I however, there is no reason to believe that conditions during the l two weeks would have been significantly different from those at i other periods of time.
L
- 4. The mechanisms for feedback of operating experience were f carefully reviewed and assessed. This included, for example, a l detailed check to assure that the plant staff had implemented each l l reconsnendation contained in recently issued INPO Significant l l Operating Experience Reports. A key part of this evaluation was a l l
l
0 3
My impressions of the performance of the INP0 evaluation Team were very favorable. The Team members proved to be a spirited, hardworking, ,
entnusiastic group. Departure from the hotel was routinely scheduled at 6:30 a.m., discussions at the Station extended beyond 6:00 p.m., and !
follow-up sessions continued at the hotel beyond 10:00 p.m. ;
In the way of specific comments, I offer the following: r
- 1. The INPO objective of seeking excellence in plant performance '
is clearly a guiding factor in their evaluations. Although compliance with regulatory standards is clearly required, this is definitely below the ultimate quality being tought. '
- 2. Although the objective is a thorough evaluation of plant performance, the INPO Team appeared to understand the necessity to try to avoid overwhelming the Station staff with more recomendations than they could handle. In some cases this was handled by grouping several recomendations under broad headings.
4
- 3. The INPO Team appeared clearly to recognize potential limitations on their findings and recomendations. Since the Team spent only two weeks at the plant, at best their observations were only a "snapshot" of total plant performance. At the saine time, however, there is no reason tc believe that conditions during the i two weeks would have been significantly different from those at f other periods of time. !
- 4. The mechanisms for feedback of operating experience were l
- arefully reviewed and assessed. This included, for example, a detailed check to assure that the plant staff had toplemented each !
recomendation contained in recently issued INP0 Significant :
Operating Experience Reports. A key part of this evaluation was a ,
't i
i
O O
4 review of training courses to assure that they include coverage of such events and provide proper inform 3 tion to the plant staff. .
- 5. The plant staff was actively working to assure that their training program will soon be qualified for accreditation by INP0.
This was an obvious stimulating effect on full implementation of the program. This included closa correlation of course content with the needs of the intended trainees. Although plant policy confirred a desire for most staff members to attend courses one week in every six, it was observed that this goal could be ,
attained, at best only about 50% of the time. This was due to the interferenceofvacationschedules(9drefuelingoutages(whenthe demands on support personnel negate allotting time for training).
- 6. Radiation protection and the implemente*, ion of the ALARA criterion are considered an important part of the Team evaluetion. !
In this regard, it was interesting to note the wide range of ,
activities currently considered as potentially significant I contributors to better implementation of this criterion. These
, included a sound training program, prewentive maintenance, and the !
upcoming implementation of a hydrogen chemistry program. It was universally agreed that, since a good ALARA program leads to greater effectiveness and efficiency in the conduct of the work at ,
aplant(andacorrespondingincreaseinproducvivity), itis [
definitely cost effective. l l
- 7. One personal observation of this evaluation was the importance !
of good personnel management practices in plant cperations. It l would appear useful to add to future Evaluation teams people who (
have specific expertise in this area. l l
- 8. As in th: past, the question was raised whether INP0 !
evaluations result in safer operation of a plant. Since the INP0 i
f
goals include better management of the piant, improved on-line perform.nce of individual systems, reduced occupational doses, and ;
~
enhanced feedback of operating experience, there is little doubt in my mind that the answer to this question is anything but "yes." An added benefit is the tremendous opportunity that the review provides for training not only the plant staff but also the participants and observers from the vendors, other utilities, and [
other organizations. ,
- 9. Near the end of my visit. I had an opportunity to met for several hours with Dr. Martin McBride, the NRC Senior Resident inspector. This oroved to be a most helpful exercise. Dr. McBride proved to be thoroughly familiar with operations at the Pilgrim Station and provided me with background infomation and insights that were valuable in helping me gain a u'etter understanding of the reasons behind some of the events and practices that we had l observed.
- 10. As a final coment. I believe that for ACRS membe's interested in detailed knowledge of main'enance and operational practices at nuclear power plants, participation as an observer in an INPO eva19. tion would be an extremely valuable source of information.
l l
l i l
6... ,
y?
6 l
l l l
l :
TABLE ! ,
PROGRAM AREAS COVERED IN THE INPO EVALUATION 0F THE PILGRIM NUCLEAR POWER STATION L
- 1. Organization and Administration !
- 2. Operations f
- 3. Maintenance l 4 Technical Support !
- 5. Radiation Protection f
- 6. Chemistry l
- 7. Operating Experience ,
- 8. Training -
I, Note: Emergency planning, which is normally one of the Program Areas, was not covered in this evaluation. r
[
t i
I i
I L
i t
l i
I t
l
l
'APR 15 '87 13:39 NRC KING OF PRUSSIA P02 4
T
$ W :
O R. cn L' H ;
O 2
h g
t2d e
n M O l Z
O :
O !
. N 8 %- l
.m ;
ElE i
I
J SAFETY ENHANCEMENT PROGRAM BOSTON EDISON GOALS
- Identify and Inird-wne Plant kaprovearnts Desponsive to Bernaro's Dran Felicy Prior to i
r> .' E- for l g- Startup. Revise Pr7cedures and Train Operasers to Improve Opermeiocas it l
FEevtive Managesnent of Severe Accident Ek g ,
&) J U) a OI Q. J
- Performa Cornprehensive Safety w Seppested by Deterministicand Probab7maic LL ~ Analym of Severe a ccidents to enaere that:
o ;
c) ~:
- - f. "Ihc Pilgrim Specific Response to Severe Accidents is Well Understood x -
b* 2. 'Ibese fnsights are FEcctively Used Within Besten Edison to Reduce the
[$ e Damage Accidens by Improving Design, Z Probability and Conset:wnces of a
} ProcederesandTraininf, co r
'tf" +
- 3. nese Imiahs are Availabic in Support of Emergency Preparedness Planning r- 5 c0
=
, a.
1 - - -
G. ._ _
l I
SAFET'I ENHANCEMENT PROGRAM .
i i
I t
t t
i Proeram Bements e
Q iQ.
Safety Analyses - Both Prnhahaidie And Delmaimistic G
'M -
."lant Equipment Modifications e !
m r
,o ;
E -
OperationsProcedureImpromnents
- u. ,
o -
Training 9
Managernent System Improvenients G
o
.% i I@ f
,t Tw 1(O k
Q. ._ . - .
~~ -- _ . - _ . _ ,- - .,w -
SAFETY ENHANCEMENT IPRf0GR A NI Approach Assemble The Most Experienced Techn~ c alTeam Avaiele g -
Pursue A Parallel EfTort to Identify Possible heprovements a.
a .' -
Prepare Conceptual Design Based On Expert Judgensent E'
v>
a ff -
Analyze Plant Capabilitics Both As Built And With Possible Improvements O
E -
Maintain Active Involvement In The Industry Programs o
E -
Information Exch:m,%
TatnologyTransfer 5
IB M
E ..
h O
e I
t
( '
/[1 FETY (Ett H ANCEMENT ,P.OGRAM V U Recchs V Station Blackoir
- Addisica OfA Third Died Gesurator -
Suppresa3on Poot VanTo Main hrk -Simed ForDecay Hems Reesva!
{ -
I i
! - Fue Water laser-Tie so RHR - Ma&==a Source Of RFV Makaup ,
G
~ \ t 3
- Addition Of Batteries With AC byerters.PowerTo Critical Va!ves and Inaruneses '
E
"- - Cross Connecion From The TSC Emugwy Diesel Generator To Recharge Entnaf o MO e ,
Z - heprm ed teer,: Term . Nitrogen Supply m
M l 0 - Set Feint And logic Changcs To Extend The Ikraskm Of HPCI And MICI Orwentien Z ,
l
- Addition Of Second Diesel Fire Puenp I
1 y)
, Fire Water hder/G ta Conden S:orage Tank t
t
(% i G) b Q.
Gl ..
I.
I l
SAFETY ENEANCRMRNT PROGRAM I
ECOUlTC i
- Contminment Perfwm Ei a.
Opdrairation Of Drywett Spray D4-.. Nezzle Change And Fknr Reduction
's -
Fire Water Inc-Tie To RHR - Additional Source Of Drywett Spray E
- a. .
Supression Poof Vent To Main Stack - Cordsinet Overpresure Centrol u.
o
, Improved Longterm Nitrogen Supply 5
x O
Z N
2 r-CD M
--w-
I SAFETY ENFIANCEWRNT PROGitAM Result
.o
- a. Anticinated Transient WM.e.t SO,m 2O
.u -
- a. Enriched Boron ForSELCSystem La c3 -
-e TRAC C Anahsis For ATWS l5 -
x RECIRC MG Field Breaker Reliability Irnprovements
- z Automatic Depressurization Syssem Iaqic Changes
- n Feedwater Ibmp Trip On Iligh Reactor Pressure
- MSIV Iteactor Low Water Levd Isolation Signal Manual Bypass l10
- e ,
e G
O