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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20216E9871997-09-0808 September 1997 Notification of 970910 Meeting W/Util in Rockville,Md to Discuss Potential Dose Consequences from Postulated Steam Line Break & Postulated Accident Sys Leakage Limits ML20149D8881997-07-11011 July 1997 Notification of Significant Licensee Meeting 97-86 W/Util on 970725 in King of Prussia,Pa to Discuss Apparent Violations Re Failure to Recognize General Emergency Condition During 970305 Exercise ML20140G6231997-06-0505 June 1997 Notification of 970716 Meeting W/Gpun in King of Prussia, Pennsylvania for Presentation & Discussion Re Root Cause Determination for Recent QC Issues Performed by Gpun Per NRC CAL ML20151U4191997-05-23023 May 1997 Discusses Review of Two Addl Concerns Identified in 970407 Memo to Recipient from Special Insp Branch Re Addl Open Items Associated W/Dec 1996 Design Insp Rept 50-289/96-201 ML20148D9851997-05-21021 May 1997 Notification of Significant Licensee Meeting 97-57 W/Util on 970528 to Discuss Formal Exit Meeting for Licensee Remedial Emergency Preparedness Exercise on 970513 & Licensee Discussion Re NRC CAL ML20141E5381997-05-15015 May 1997 Notification of 970530 Meeting W/Representatives of Gpu Nuclear Corp in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 ML20138D3161997-04-21021 April 1997 Notification of Significant Licensee Meeting 97-47 W/Util on 970430 to Discuss Root Cause Analysis of 970305 Emergency Preparedness Drill Weaknesses ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20135F8801997-03-0404 March 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970317 to Discuss Emergency Preparedness Insp Exit Meeting ML20138M3111997-02-20020 February 1997 Notification of 970306 Meeting W/Gpu in Rockville,Md to Discuss Three Mile Island,Unit 1 Reactor Pressure Vessel pressure-temp Limit Curves ML20147D8391997-02-12012 February 1997 Notification of 970220 Meeting W/Util Representatives in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 Facility ML20133Q3031997-01-16016 January 1997 Notification of Significant Licensee Meeting 97-08 W/Util on 970131 in Middletown,Pa Re Safety Sys Functional Insp Exit Meeting ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20129K3731996-11-21021 November 1996 Notification of 961126 Meeting W/Gpun in North Bethesda,Md to Discuss TMI-1 SG Issues ML20135B0871996-11-15015 November 1996 Notification of Significant Licensee Meeting 96-118 W/Util on 961122 to Discuss Plant Motor Operated Valve Testing Program self-assessment 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 ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months ML20134E9191996-10-29029 October 1996 Forwards Rationale for Inital Plants Selected for Design Insps & for Plants Considered for Second Quarter FY97 Design Insps ML20128G1661996-10-0303 October 1996 Summarizes 960924 Meeting W/Gpu Nuclear Corp in Rockville,Md Re Preliminary Responses to Staff RAI Concerning Request to Change EALs for TMI-1.List of Participants & Copy of Preliminary Response to RAI Encl 1999-09-29
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217C5311999-10-0808 October 1999 Notification of 991027 Meeting with Representatives of Gpu in Rockville,Md to Discuss Recent Control Rod Surveillance Performance Issues at TMI-1.Proprietary Portions of Meeting Will Be Closed to Public ML20217F0841999-10-0808 October 1999 Informs That During 466th Meeting of ACRS on 990930-1002, CEOG Proposal to Eliminate PASS from Plant Design & Licensing Bases for CEOG Plants,Were Reviewed.Discussion & Recommendations,Listed ML20212K8901999-10-0505 October 1999 Notification of 991027 Meeting with Util in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TM1-1 ML20216J0151999-09-29029 September 1999 Notification of 991020 Meeting in Forked River,Nj to Discuss Licensee 990922,response to NRC & Other Info Addressing Sale of Portion of Land That Is Part of Plant Site ML20216G3671999-09-10010 September 1999 Forwards CNWRA Program Manager Periodic Rept (Pmpr) for Period 990731-0827 ML20210U7571999-08-20020 August 1999 Forwards Info Received from Gpu Nuclear,Inc on 990820 in Preparation for 990823.Requests Info Be Docketed ML20210C9991999-07-22022 July 1999 Revised Notification of 990813 Meeting with Gpu Nuclear,Inc Rockville,Maryland to Discuss TMI-1 Licensing Action Status. Meeting Date Changed ML20210E9511999-07-12012 July 1999 Notification of 990805 Meeting with Representative of Gpu Nuclear,Inc in Rockville,Md Re Plant,Unit 1 Licensing Action Status ML20212H9621999-06-23023 June 1999 Revised Notification of Meeting with Gpu Nuclear,Inc to Discuss Proposed Mods to RBS Sys Procedures & HPI Cross Connect Lineup.Meeting Rescheduled to 10 A.M. on 990713 ML20195H8521999-06-18018 June 1999 Requests That Encl Questions,Faxed to Gpu Nuclear,Inc on 990616,be Docketed,In Preparation for Forthcoming Conference Call Re TS Change Request 248, Remote Shutdown Sys, ML20195H9911999-06-15015 June 1999 Notification of 990707 Meeting with Util to Discuss Licensee Proposed Mods to Reactor Bldg Spray Procedures & High Pressure Injection Cross Connection Lineup ML20206F2921999-05-0505 May 1999 Forwards Draft Questions Which Were Faxed to Licensee for TMI Unit 1,GPUN on 990505 in Preparation for 990506 Conference Call on TS Change Request 279 ML20206D1291999-04-28028 April 1999 Notification of 990507 Meeting with Gpu Nuclear,Inc in Rockville,Maryland to Discuss Three Mile Island,Unit 1 Licensing Action Status ML20205N3161999-04-0909 April 1999 Notification of Significant Licensee Meeting 99-19 with Util on 990423 to Discuss Emergency Feedwater Flow Discrepancies ML20203E0321999-02-11011 February 1999 Staff Requirements Memo Re 990211 Affirmation Session in Rockville,Md (Open to Public Attendance) Re Secys 99-044 & 99-045 ML20197G6381998-12-0707 December 1998 Forwards Program Manager Period Rept (Pmpr) for Period 981024-1120 ML20196E2801998-11-30030 November 1998 Discusses Closeout of TAC MA1607 Re Cross Potential for common-cause High Pressure Injection Pump Failure IR 05000289/19983011998-11-0404 November 1998 Forwards NRC Operator Licensing Exam Rept 50-289/98-301 with as Given Written Exam for Tests Administered on 980824-27 at Facility ML20154G3451998-10-0101 October 1998 Rev 2 to Notification of Significant Licensee Meeting 97-73 on 981023 in King of Prussia,Pa to Discuss Actions Taken Re Engineering Corrective Action Performance Assessment Team Findings ML20153D9681998-09-24024 September 1998 Notification of 981006 Meeting W/Gpu Nuclear,Inc in Rockville,Md to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20237E8381998-08-28028 August 1998 Notification of 980917 Meeting W/Gpu Nuclear,Inc & Amergen in Rockville,Md to Discuss Sale & Transfer of TMI-1 from Gpu Nuclear,Inc to Amergen ML20237E4591998-08-20020 August 1998 Submits Rev 1 to Notification of Significant Licensee Meeting 98-73 W/Util in Middletown,Pa to Discuss Actions Taken Re Engineering Corrective Action PA Team Findings. Meeting Postponed ML20237C9401998-08-14014 August 1998 Notification of Significant Licensee Meeting 98-73 on 980828 W/Gpu Nuclear,Inc in Middletown,Pa to Discuss Actions Taken Re Engineering C/A Performance Assessment Team Findings ML20248H7001998-05-20020 May 1998 Staff Requirements Memo Re SECY-98-071,exemption to 10CFR72.102(f)(1) Seismic Design Requirement for TMI-2 ISFSI ML20247M2191998-05-19019 May 1998 Notification of 980604 Meeting W/Gpu Nuclear Inc in Royalton,Pa to Discuss Status of Licensing Actions Proposed & Currently Under Review by NRC for TMI-1 ML20216B6871998-05-0808 May 1998 Notification of 980527 Meeting W/Representative of Gpu Nuclear,Inc in Rockville,Md to Discuss Licensee 980324 Submittal Re Control Room Habitability at TMI-1 IR 05000289/19980991998-02-26026 February 1998 Notification of Significant Licensee Meeting 98-22 W/Util on 980318 to Discuss SALP for Period Covering 960805-980124,as Documented in SALP Rept 50-289/98-99 ML20154B7931998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 IA-98-345, Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 11998-02-0606 February 1998 Discusses Licensing Basis for Letdown Line Break Outside Containment for Plant,Unit 1 ML20199H6701997-11-20020 November 1997 Notifies of 971212 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability at Unit 1 ML20199E7071997-11-14014 November 1997 Revised Notification of 971119 Meeting W/Gpu Nuclear Corp,In Rockville,Md to Discuss Control Room Habitability at TMI-1 Nuclear Facility.Meeting Cancelled Until Further Notice ML20199B3111997-11-0606 November 1997 Notifies of 971119 Meeting W/Gpu in Rockville,Md to Discuss Control Room Habitability ML20212G9531997-11-0505 November 1997 Forwards Gpu SE Re Review of AP600 Shutdowm Ts.Section B.3.9.4 of STS Cites Gpu Nuclear SE 0002000-001 Rev 0,880520 as Ref E Temporary Containment Penetration Closure Devices Equivalent to Valve or Blind Flange ML20216E9871997-09-0808 September 1997 Notification of 970910 Meeting W/Util in Rockville,Md to Discuss Potential Dose Consequences from Postulated Steam Line Break & Postulated Accident Sys Leakage Limits ML20149D8881997-07-11011 July 1997 Notification of Significant Licensee Meeting 97-86 W/Util on 970725 in King of Prussia,Pa to Discuss Apparent Violations Re Failure to Recognize General Emergency Condition During 970305 Exercise ML20140G6231997-06-0505 June 1997 Notification of 970716 Meeting W/Gpun in King of Prussia, Pennsylvania for Presentation & Discussion Re Root Cause Determination for Recent QC Issues Performed by Gpun Per NRC CAL ML20151U4191997-05-23023 May 1997 Discusses Review of Two Addl Concerns Identified in 970407 Memo to Recipient from Special Insp Branch Re Addl Open Items Associated W/Dec 1996 Design Insp Rept 50-289/96-201 ML20148D9851997-05-21021 May 1997 Notification of Significant Licensee Meeting 97-57 W/Util on 970528 to Discuss Formal Exit Meeting for Licensee Remedial Emergency Preparedness Exercise on 970513 & Licensee Discussion Re NRC CAL ML20141E5381997-05-15015 May 1997 Notification of 970530 Meeting W/Representatives of Gpu Nuclear Corp in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 ML20138D3161997-04-21021 April 1997 Notification of Significant Licensee Meeting 97-47 W/Util on 970430 to Discuss Root Cause Analysis of 970305 Emergency Preparedness Drill Weaknesses ML20140D5251997-04-18018 April 1997 Notification of 970502 Meeting W/Util in Rockville,Md to Discuss Schedules & Resolution of Issues Relating to Thermo-Lag Fire Barriers ML20135F8801997-03-0404 March 1997 Notification of Significant Licensee Meeting 97-27 W/Util on 970317 to Discuss Emergency Preparedness Insp Exit Meeting ML20138M3111997-02-20020 February 1997 Notification of 970306 Meeting W/Gpu in Rockville,Md to Discuss Three Mile Island,Unit 1 Reactor Pressure Vessel pressure-temp Limit Curves ML20147D8391997-02-12012 February 1997 Notification of 970220 Meeting W/Util Representatives in Rockville,Md to Discuss Status of Licensing Activities Associated W/Plant,Unit 1 Facility ML20133Q3031997-01-16016 January 1997 Notification of Significant Licensee Meeting 97-08 W/Util on 970131 in Middletown,Pa Re Safety Sys Functional Insp Exit Meeting ML20149M0471996-12-10010 December 1996 Forwards Internet Mail Received from PM Blanch ML20129K3731996-11-21021 November 1996 Notification of 961126 Meeting W/Gpun in North Bethesda,Md to Discuss TMI-1 SG Issues ML20135B0871996-11-15015 November 1996 Notification of Significant Licensee Meeting 96-118 W/Util on 961122 to Discuss Plant Motor Operated Valve Testing Program self-assessment 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 ML20136E3011996-10-31031 October 1996 Forwards Schedule for Activities at Plant for Next Few Months 1999-09-29
[Table view] |
Text
n. Octcber 28,1%5 C -
, , j;, ) ., .
MEMORANDUM FOR:
Richard W. StarostIcki, Director
(, $
Division of Reactor Projects g .
Region I P FROM:
James G. Partlow, Director Division of Inspection Programs j4 4[9 Office of Inspection and Enforcement
SUBJECT:
V 90 ,M PERFORMANCE FOLLOWING RESTART APPRAISAL TEAM (PAT) INSPECTION f ,,
The Executive Director for Operations, in his memorandum to the Conrnissioners c r '
of June 5,1985, comitted to performing two PAT inspections after TMI-I / /
restart, one at the six-month point and another at 12 months. In addition, ff f/
PAT report be issued at the conclusion of each inspection.theT m require considerable coordination between Region I and Headquarters.This effort 3 For this will purpose, of how toI bestpropose an initialthis accomplish meeting effort.in December 1985 to work out the details suggest the following guidelines for the conduct of these inspections:As a s 1.
It is assumed that the six- and twelve-month time periods will begin after initial startup of the unit. This would result in the two inspections being conducted in March 1986 and October 1986.
2.
It is assumed that Headquarters and Regional inspectors will be involved in both inspections. The enclosure suggests an inspection scheme that proposes how these inspection responsi-bilities might be divided between Headquarters and the Region.
3.
It is assumed that in each case the PAT report will provide input to the SALP evaluation. This will require that the SALP be r accomplished following completion of the PAT reports - two months after completion of the inspection.
Phil McKee or a member of his staff will be in contact with you to make arrangements for the meeting on this topic.
thoughts or comments please contact me or Phil.If Original you have any preliminary staned by:
James G. Partlett James G. Partlow, Director Division of Inspection Programs Office of Inspection and Enforcement
Enclosure:
As stated Distribution:
DCS ORP8 reading P. F. McKee, IE DI reading R. L. Spessard IE D. J. Sullivan, IE J. G. Partlow, IE L. J. Callan, IE R. H. Vollmer, IE J. M. Taylor, IE h IE: A :0R IE:PkbORPB IE DJSullivan:jj LJCd11an PFMcKee RPB IE:DI:DD IE:b D 10/22/85 RLSpsssard JGPa low 10/22/85 10/yv85 10/ /85 10/g85 n / p
/ J 0 o3/0 "
( M _ _ -
er
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1 TMI Restart PAT Inspections
. Areas Inspector 6-month . 12-month
- Plant Operations HQ RI
- Maintenance HQ HQ
' L. censed and non-licensed HQ RI Operator Training J
' Quality Assurance RI HQ Radiological Controls HQ RI
- Security and Safeguards RI RI
- Design Engineering and HQ HQ Plant Modifications i
. *These areas have not historically been inspected during a PAT inspection.
9 l
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Enclosure i
!8 a
f i
Rev. 0 2/7/86 1
l l INSPECTION PLAN FOR TMI-I
! Inspection Obfective:
7 The objective of the IE team inspection at TMILI is to assess the operational
- readiness of the auxiliary feedwater (AFW) sistem and the integrated control i system (ICS). This assessment is to be comprehensive, including, but not j limited to, a determination of the following:
the capability of the system to perform all of the safety functions i
required of it by its design basis and safety analysis; whether the system has been adequately tested to demonstrate that it will perfom all of the safety functions required of it; l
! g [)
g#y,a o whether the system's components (with emphasis on pumps and valves) have been adequately maintained to ensure their operability under all i g l postulated conditions; - p 5 --
whether operator / maintenance technician training is adequate to
)
ensure proper operation and maintenance of the system; l whether the system initiating and control functions are effective and reliable.
1 whether the human factors considerations relative to the system j (e.g., accessibility and labeling of valves) and the supporting
! procedures are adequate to ensure proper operation under all i
accident conditions. *
Background:
i One of the major conclusions from the NRC investigative team that reviewed the June 9,1985 loss of all feedwater event at Davis-Besse (discussed in detail in NUREG-1154) was the extreme importance of adequate attention to detail by licensees with regard to care of plant equipment. Specifically, the opera-tional readiness of safety systems was found to be highly dependent on the
, quality of the maintenance, engineering design, testing of equipment, and evaluation of operating experience provided for system components. Many of 1
the specific safety system weaknesses that led to the June 9,1985 ' event at Davis-Besse had gone undetected by the NRC despite the aggressive implementa-j tion of the MC 2515 Program by NRC Region III.
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- An innovative inspection method may prove to be more effecti.ve in identifying the type of problems that can degrade the operational readiness of safety systems. This type of inspection has been termed a Safety Systems Func-tional Inspection (SSFI) and has been performed at Turkey Point, Pilgrim and ANO-I. These inspections emphasized the combining of detailed programmatic and technical inspection expertise into one inspection team. The results have been encouraging. Specific safety concerns were identified that probably would not have been found by separate programmatic and technical inspection efforts. The TMI-I inspection will be based on the same basic approach as previous SSFI inspections.
Inspection Methodology: g
- 1. Review the design basis requirements for the selected system (s) and determine the operating function under accident conditions under which each or abnormal conditions.
vNi a
- a. For valves: What permissive interlocks are involved? What differential pressures will exist when the valve strokes? Will the valve be repositioned during the course of the event? What is the source of control / indication power? What control logic
_ is involved?
- b. For pumps: What are the various flow paths the pump will experience during accident scenarios? Do the flow paths change?
What permissive interlocks / control logic apply? How is the pump controlled during accident conditions? What suction / discharge pressures can the pump be expected to experience during accident conditions? What is the motive power for the pump during all conditions?
- c. For instrumentation: Is the instrumentation of adequate range and accessibility for operations to control the system under normal and abnormal conditions? Do initiation and control systems function as designed?
- 2. Review the design of the selected system (s) as installed in the -
plant.
- a. Determine if the as-built design of system modifications matches the current design basis requirements (e.g., are fuses and thermal overloads properly sized? are current D.C. loads within the design capacity of the station batteries?, etc.),
- b. Determine if system modifications implemented subsequent to initial licensing have introduced any unreviewed safety questions.
- 3. Review the maintenance and test records for the selected system (s),
- a. Determine if the system components have been adequately tested to demonstrate that they can perform their safety function under all conditions they might experience in an accident situation.
- ----- ~ - - ----
- b. Determine if the system components are being adequately maintained to ensure their operability under all accident conditions (e.g., are limit and torque switch settings proper?
is the instrument air system adequately maintained to ensure the reliability of pneumatic valves? are fuse and thennal overload l sizes correct?, etc.).
T
- 4. Perform walkdown of selected systems.
I
- a. Determine if components are labeled and accessible (can the components be operated locally / manually if required?
)9P AA i HP/ security interference?, etc.). is there j 4 j ( ,w,Md.
v~ ~
- b. Determine if MOV operators and check valves (particularly plug- b@ @g '
type) are installed in the orientation required by the manufacturer.
i
- c. Determine if system lineup is consistent with design basis weel 4 requirements. Included in this lineup should be considerations W > "" ~4 of the nonnal and backup power supplies, control circuitry, Gs o indication and annunciation status, and sensing lines for 7, . y
- 5. Review abnormal, emergency, and normal operating procedures; maintenance
- procedures; and surveillance procedures for the selected system (s).
l a. Determine the technical adequacy of the procedures.
- b. Determine if the procedural steps for normal, abnormal, and emergency conditions are consistent with the design basis,
- c. Determine if operations and maintenance personnel receive adequate
- training pertaining to the selected system (s) and if the degree of
- training provided is consistent with the amount of technical detail j included in procedures.
- 6. Review the operational experience of the selected system (s) (LERs, NPRDS, 50.72 reports, enforcement, maintenance work requests, etc.).
- j a. Determine the historical reliability of the system and its !
components.
l
! b. Determine if the licensee has aggressively pursued, identified.
and corrected root cause problems. l
]
- c. Determine the extent of the maintenance backlog and ascertain if t
the licensee has a program to ensure that priority safety-
- related maintenance is perfonned in a timely manner.
4 Inspection Team Composition and Assignments: Coverage of Items
\ Joe Callan - Team Leader l Tom Martin - Maintenance 3. b. S.a 6.c l George Morris - Design Changes and Modifications 1, 2 l Gary Overbeck - Design Changes and Modifications 1, 2 l
'. Al Saunders - Design Changes and Modifications 1, 2
- E. T. Dunlap - Design changes and Modifications 1, 2 Jim Smith - Training 5.c Don Caphton - Operations 5.a. b Dave Trimble - Surveillance 3.a. 5.a Dennis Sullivan - Quality Programs 6.a. b Art Howell - System Walkdown 4 Jeff Sharkey - System Walkdown 4 Dates of Principal Inspection Activities March 3-7 (Saunders, Dunlap, Morris, and Overbeck only), March 10-14, March 20-21, Mar 24-27.
Inspection Routine and Policy Working hours will start at 7:30 am daily with one hour for lunch.
Team meetings are expected to be held each Mon., Tues., Wed., and Thurs.
from 4:30 to 6:00 pm.
A double spaced typed draft of each inspection area must be submitted to the Team Leader by April 3. The finished report must be out by April 30.
Logistics Reservations for team members listed in this inspection plan have been made at Americana Host Inn, Harrisburg.
Travel wf11 be POV throughout the inspection, doubling-up from motel to site, as appropriate.
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