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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20210S6371999-08-13013 August 1999 Informs That Attached Info Transmitted by Facsimile on 990813 to P Duke of Pse&G to Facilitate Upcoming Conference Call in Order to Clarify Licensee Submittal ,which Provided Response to GL 98-04 ML20210P0141999-08-0505 August 1999 Forwards Licensee Response to Facility Design & Operation for NRC Staff Questions Re Individual Operator Exam Appeals ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20209G6721999-07-14014 July 1999 Forwards Draft Request for Addl Info Re Inservice Insp - Second 10 Yr Interval ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20196C5051999-06-21021 June 1999 Informs That Attached Draft Request for Addl Info Transmitted by Facimile on 990617 to G Salamon of Pse&G. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20205Q9521999-04-15015 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980223-0304 ML20205P4861999-04-15015 April 1999 Forwards NRC Operator Licensing Exam Rept 50-354/98-03OL, (Including Completed & Graded Tests) for Tests Administered on 980223-0304 ML20205N7101999-04-0909 April 1999 Forwards Info Which Was Transmitted by Facsimile on 990409 to C Manges of Pse&G,To Facilitate Conference Call in Order to Clarify Licensees Submittal ,which Provided Addl Info Re Relief Request for First 10-year ISI for Plant ML20205F9811999-03-31031 March 1999 Informs That Encl RAI Was Transmitted by Facsimile on 990331 to G Salamon of Public Svs Electric & Gas Co.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20207K3941999-03-0808 March 1999 Notification of Significant Licensee Meeting 99-13 with Util on 990322 in King of Prussia,Pa to Review Util & NRC Assessments Re Dec 1998 Licensed Operator Exam,Including Applicant Performance & Quality of Util Proposed Exam ML20203F5431999-02-12012 February 1999 Notification of 990225 Meeting with Public Service Electric & Gas Co & Asea Brown Boveri in Rockville,Md to Discuss Fuel Design Changes for Hope Creek Generating Station ML20198S3281999-01-0606 January 1999 Informs That on 981218 & 22 Telcons,J Ondish & J Priest Discussed Encl Info with R Ennis.Info Clarifies Pse&G License Change Request LCR H98-03,dtd 980625 Which Requested in Part to Revise TS 4.4.2.1.b ML20196H1441998-12-0303 December 1998 Forwards Info from J Priets of Public Service Electric & Gas to R Ennis,Nrc Hope Creek Project Manager,Transmitted to Facilitate NRC Review of License Change Request Associated with Facility Filtration,Recirculation & Ventilation Sys ML20196A6381998-11-25025 November 1998 Notification of 981207 Meeting with Util in Rockville,Md to Discuss Proposed License Change Request Re Filtration, Recirculation & Ventilation Sys for Plant ML20236S3371998-07-20020 July 1998 Notification of 980804 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Re Ush for Plant ML20249C1341998-06-17017 June 1998 Notification of Significant Licensee Meeting 98-59 W/Util on 980629 in King of Prussia,Pa to Discuss Licensed Operator Initial Training Program & Performance Problems at Plant for February 1998 Initial Exam ML20248M0371998-06-0909 June 1998 Notification of 980624 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Related to Filtration,Recirculation & Ventilation Sys for Hope Creek Generating Station ML20203B1211998-02-19019 February 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970929-1002 IR 05000354/19970081998-02-19019 February 1998 Forwards NRC Operator Licensing Exam Rept 50-354/97-08 (Including Completed & Graded Tests) for Tests Administered on 970929-1002 ML20198D1491997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-130 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Two Violations Re Performance Criteria for Sys & Components Associated W/Maint Rule Program ML20198D1421997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-129 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Violation for Failure to Follow Reactivity Manipulation Procedures for Control Rod Movements ML20149J9891997-07-22022 July 1997 Notification of Significant Licensee Meeting 97-88 W/Util on 970812 in King of Prussia,Pa to Conduct pre-decisional EC to Discuss Apparent Violations of 10CFR50.59 During Installation of Residual Heat Removal cross-tie Valve Mod ML20236M9111997-01-24024 January 1997 Describes Views on Broader Compliance Policy Concerns Associated W/River Bend Case Which Involves Complex Enforcement Policy Issues Associated W/Relationship Between Appropriate Use of Plant Administrative Controls ML20137B0781996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants IA-96-492, Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants1996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants ML20135A6391996-11-20020 November 1996 Summarizes 940602 Meeting W/Listed Individuals to Discuss Items of Mutual Interest Re Plant Performance & Improvement Plans 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 ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20135B3831996-09-13013 September 1996 Discusses 960826 Meeting W/Listed Individuals to Discuss Current Activities & Issues Involving Hope Creek & Salem Npps.Info Partially Deleted ML20135B3731996-08-23023 August 1996 Partially Deleted Memo Re 960826 Drop in Meeting ML20135B3781996-08-23023 August 1996 Partially Deleted Memo Re Courtesy Visit W/Ej Ferland & Lr Eliason on 960826 ML20236M0141996-08-0505 August 1996 Recommends That Hope Creek Modify TS 3/4.5.1 to Conform W/ Sts,Which Specifies Steam Pressure & Flow as Necessary Conditions to Perform Test,To Avoid Further Interpretation Problems ML20135B3571996-02-27027 February 1996 Discusses 960222 Visit W/Listed Individuals to Discuss Issues Re Salem & Hope Creek Generating Stations ML20134K8691996-02-0909 February 1996 Partially Deleted Ltr Requesting OGC Interpretation of 10CFR50.5 Re Situation That Occurred at Util Plant ML18101A7851995-06-13013 June 1995 Advises That Util Current Drawer I Will Be Changed to Drawer 0509,effective 950612.Ltr from Hancocks Bridge Post Ofc Encl ML20134C6501995-05-0404 May 1995 Informs That Due to Pending EAs at Both Plants Scope of 950530 Eppr Has Been Reduced.Meeting Will Be Limited to 1 H ML20135B1791994-12-13013 December 1994 Discusses Pse&G 941129 drop-in Visit W/Listed Individuals to Discuss Items of Mutual Interest Including Plant Hope Creek & Salem Generating Station Performance ML20058C7731993-11-10010 November 1993 Notification of 931220 Enforcement Conference in Region I Ofc to Discuss Violations Noted in MOV NRC Team Insp ML20059G1621993-10-27027 October 1993 Notification of Significant Licensee Meeting 93-135 W/Util on 931207 to Discuss Hope Creek Motor Operated Valve NRC Team Insp Violation ML20135A8501993-08-0202 August 1993 Discusses 930723 Pse&G Visit W/Listed Individuals to Discuss Items of Mutual Interest Re Hope Creek & Salem,Units 1 & 2 NPP ML20134C7731993-07-0707 July 1993 Forwards Security & Safeguards SALP Input for Plants Covering Period 911229-930619 ML20128K2461993-02-12012 February 1993 Notification of 930224 Meeting W/Bwrog in Rockville,Md to Discuss Hope Creek Amend Request & SE Status (Increase MSIV Leakage,Remove Leakage Control Sys & Use Ms Lines & Condenser for Treatment) ML20134C8141992-01-16016 January 1992 Forwards SALP Input Relating to Emergency Preparedness for Period 900816-911231 ML20134C6441992-01-15015 January 1992 Forwards Security & Safeguards SALP Input for Plants.Input Covers Period of 900801-911228 ML20058D3211990-10-30030 October 1990 Documents Various Observations Made During INPO 900813-24 Evaluation Process at Facility ML18095A4331990-07-24024 July 1990 Advises That NRC Initiated Formal Section 7 Consultation W/ Dept of Commerce on 900618 Re Util Preparation of Biological Assessment of Plants ML20055G4331990-06-28028 June 1990 Forwards D Kwiatkowski of FEMA Transmitting FEMA Region I Rept for 881129-1201 Full Participation Exercise at Plants.Evaluation of 881202 Medical Drill Also Included in Rept.Encls Should Be Transmitted to Licensee 1999-08-05
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217A9811999-10-30030 October 1999 Forwards Sept 1999 Performance Indicator Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Includes Data Through Aug 1999 (two-thirds of 3rd Quarter of 1999) for 13 Units at 9 Pilot Sites ML20210S6371999-08-13013 August 1999 Informs That Attached Info Transmitted by Facsimile on 990813 to P Duke of Pse&G to Facilitate Upcoming Conference Call in Order to Clarify Licensee Submittal ,which Provided Response to GL 98-04 ML20210P0141999-08-0505 August 1999 Forwards Licensee Response to Facility Design & Operation for NRC Staff Questions Re Individual Operator Exam Appeals ML20210F6981999-07-27027 July 1999 Discusses 990430 Request for Waiver of 10CFR170 Fees for Certain Insp Efforts Re NRR Pilot Regulatory Oversight Program.Determined That Thirteen Plants in Pilot Program Will Be Exempted from 10CFR170 Fees for Insp Efforts ML20209G6721999-07-14014 July 1999 Forwards Draft Request for Addl Info Re Inservice Insp - Second 10 Yr Interval ML20196H8491999-06-28028 June 1999 Forwards June 1999 Performance Indicator (PI) Data Rept for Revised Reactor Oversight Process Pilot Program.Rept Constitutes Second Monthly PI Data Submittal from Pilot Plant Licensees,Which Includes Data Through May 1999 ML20196C5051999-06-21021 June 1999 Informs That Attached Draft Request for Addl Info Transmitted by Facimile on 990617 to G Salamon of Pse&G. Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20210F7021999-04-30030 April 1999 Requests Waiver of Fees for Thirteen Dockets That Compromise Plant Population for NRR Pilot Regulatory Oversight Program. Purposes of Pilot Program Described in Commission Papers SECY-99-007 & SECY-99-007A ML20205Q9521999-04-15015 April 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980223-0304 ML20205P4861999-04-15015 April 1999 Forwards NRC Operator Licensing Exam Rept 50-354/98-03OL, (Including Completed & Graded Tests) for Tests Administered on 980223-0304 ML20205N7101999-04-0909 April 1999 Forwards Info Which Was Transmitted by Facsimile on 990409 to C Manges of Pse&G,To Facilitate Conference Call in Order to Clarify Licensees Submittal ,which Provided Addl Info Re Relief Request for First 10-year ISI for Plant ML20205F9811999-03-31031 March 1999 Informs That Encl RAI Was Transmitted by Facsimile on 990331 to G Salamon of Public Svs Electric & Gas Co.Review of RAI Would Allow Licensee to Determine & Agree Upon Schedule to Respond to RAI ML20207K3941999-03-0808 March 1999 Notification of Significant Licensee Meeting 99-13 with Util on 990322 in King of Prussia,Pa to Review Util & NRC Assessments Re Dec 1998 Licensed Operator Exam,Including Applicant Performance & Quality of Util Proposed Exam ML20203F5431999-02-12012 February 1999 Notification of 990225 Meeting with Public Service Electric & Gas Co & Asea Brown Boveri in Rockville,Md to Discuss Fuel Design Changes for Hope Creek Generating Station ML20198S3281999-01-0606 January 1999 Informs That on 981218 & 22 Telcons,J Ondish & J Priest Discussed Encl Info with R Ennis.Info Clarifies Pse&G License Change Request LCR H98-03,dtd 980625 Which Requested in Part to Revise TS 4.4.2.1.b ML20196H1441998-12-0303 December 1998 Forwards Info from J Priets of Public Service Electric & Gas to R Ennis,Nrc Hope Creek Project Manager,Transmitted to Facilitate NRC Review of License Change Request Associated with Facility Filtration,Recirculation & Ventilation Sys ML20196A6381998-11-25025 November 1998 Notification of 981207 Meeting with Util in Rockville,Md to Discuss Proposed License Change Request Re Filtration, Recirculation & Ventilation Sys for Plant ML20236S3371998-07-20020 July 1998 Notification of 980804 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Re Ush for Plant ML20249C1341998-06-17017 June 1998 Notification of Significant Licensee Meeting 98-59 W/Util on 980629 in King of Prussia,Pa to Discuss Licensed Operator Initial Training Program & Performance Problems at Plant for February 1998 Initial Exam ML20248M0371998-06-0909 June 1998 Notification of 980624 Meeting W/Util in Rockville,Md to Discuss Technical Issues Associated W/Pse&G Proposed License Change Request Related to Filtration,Recirculation & Ventilation Sys for Hope Creek Generating Station IR 05000354/19970081998-02-19019 February 1998 Forwards NRC Operator Licensing Exam Rept 50-354/97-08 (Including Completed & Graded Tests) for Tests Administered on 970929-1002 ML20203B1211998-02-19019 February 1998 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970929-1002 ML20198D1421997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-129 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Violation for Failure to Follow Reactivity Manipulation Procedures for Control Rod Movements ML20198D1491997-12-24024 December 1997 Notification of Significant Licensee Meeting 97-130 W/Util on 980114 to Conduct pre-decisional Enforcement Conference to Discuss Two Violations Re Performance Criteria for Sys & Components Associated W/Maint Rule Program ML20149J9891997-07-22022 July 1997 Notification of Significant Licensee Meeting 97-88 W/Util on 970812 in King of Prussia,Pa to Conduct pre-decisional EC to Discuss Apparent Violations of 10CFR50.59 During Installation of Residual Heat Removal cross-tie Valve Mod ML20236M9111997-01-24024 January 1997 Describes Views on Broader Compliance Policy Concerns Associated W/River Bend Case Which Involves Complex Enforcement Policy Issues Associated W/Relationship Between Appropriate Use of Plant Administrative Controls IA-96-492, Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants1996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants ML20137B0781996-11-25025 November 1996 Forwards Proposed Notice of Violation & Proposed Imposition of Civil Penalities Based on Six Violations of Security Program at Mentioned Plants ML20135A6391996-11-20020 November 1996 Summarizes 940602 Meeting W/Listed Individuals to Discuss Items of Mutual Interest Re Plant Performance & Improvement Plans 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 ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20135B3831996-09-13013 September 1996 Discusses 960826 Meeting W/Listed Individuals to Discuss Current Activities & Issues Involving Hope Creek & Salem Npps.Info Partially Deleted ML20135B3731996-08-23023 August 1996 Partially Deleted Memo Re 960826 Drop in Meeting ML20135B3781996-08-23023 August 1996 Partially Deleted Memo Re Courtesy Visit W/Ej Ferland & Lr Eliason on 960826 ML20236M0141996-08-0505 August 1996 Recommends That Hope Creek Modify TS 3/4.5.1 to Conform W/ Sts,Which Specifies Steam Pressure & Flow as Necessary Conditions to Perform Test,To Avoid Further Interpretation Problems ML20135B3571996-02-27027 February 1996 Discusses 960222 Visit W/Listed Individuals to Discuss Issues Re Salem & Hope Creek Generating Stations ML20134K8691996-02-0909 February 1996 Partially Deleted Ltr Requesting OGC Interpretation of 10CFR50.5 Re Situation That Occurred at Util Plant ML18101A7851995-06-13013 June 1995 Advises That Util Current Drawer I Will Be Changed to Drawer 0509,effective 950612.Ltr from Hancocks Bridge Post Ofc Encl ML20134C6501995-05-0404 May 1995 Informs That Due to Pending EAs at Both Plants Scope of 950530 Eppr Has Been Reduced.Meeting Will Be Limited to 1 H ML20135B1791994-12-13013 December 1994 Discusses Pse&G 941129 drop-in Visit W/Listed Individuals to Discuss Items of Mutual Interest Including Plant Hope Creek & Salem Generating Station Performance ML20058C7731993-11-10010 November 1993 Notification of 931220 Enforcement Conference in Region I Ofc to Discuss Violations Noted in MOV NRC Team Insp ML20059G1621993-10-27027 October 1993 Notification of Significant Licensee Meeting 93-135 W/Util on 931207 to Discuss Hope Creek Motor Operated Valve NRC Team Insp Violation ML20135A8501993-08-0202 August 1993 Discusses 930723 Pse&G Visit W/Listed Individuals to Discuss Items of Mutual Interest Re Hope Creek & Salem,Units 1 & 2 NPP ML20134C7731993-07-0707 July 1993 Forwards Security & Safeguards SALP Input for Plants Covering Period 911229-930619 ML20128K2461993-02-12012 February 1993 Notification of 930224 Meeting W/Bwrog in Rockville,Md to Discuss Hope Creek Amend Request & SE Status (Increase MSIV Leakage,Remove Leakage Control Sys & Use Ms Lines & Condenser for Treatment) ML20134C8141992-01-16016 January 1992 Forwards SALP Input Relating to Emergency Preparedness for Period 900816-911231 ML20134C6441992-01-15015 January 1992 Forwards Security & Safeguards SALP Input for Plants.Input Covers Period of 900801-911228 ML20058D3211990-10-30030 October 1990 Documents Various Observations Made During INPO 900813-24 Evaluation Process at Facility ML18095A4331990-07-24024 July 1990 Advises That NRC Initiated Formal Section 7 Consultation W/ Dept of Commerce on 900618 Re Util Preparation of Biological Assessment of Plants ML20055G4331990-06-28028 June 1990 Forwards D Kwiatkowski of FEMA Transmitting FEMA Region I Rept for 881129-1201 Full Participation Exercise at Plants.Evaluation of 881202 Medical Drill Also Included in Rept.Encls Should Be Transmitted to Licensee 1999-08-05
[Table view] |
Text
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, h/ 4 3 May 26, 1989) m L.
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MEMORANDUM FOR:- Paul Swetland, Chief
, Projects Section 1B -
Division of Reactor' Projects Region I b ' 'FROM: Walter R. Butler, Director. '
Project Directorate'I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation' '
SUBJECT:
SALP INPUT FOR HOPE CREEK, SAFETY ASSESSMENT / QUALITY VERIFICATION. ~
- Enclosed 11s the SALP input for Hope Creek in the' functional area of Safety
- Assessment / Quality Verification.. Input was received from the NRR technical staff, and'the senior resident at Hope Creek. For additional information,.
cont'act'Clyde Shiraki at 492-1445..
/s/
- Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear. Reactor Regulation
Enclosure:
SALP. .. Input-
- cc w/ enclosure:
E. Wenzinger, RI G. Meyer, SRI, Hope Creek
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%, . . . . * ,e# May 26, 1989 MEMORANDUM FOR: Paul-Swetland, Chief i Projects Section 28 Division of Reactor Projects Region I FROM: Walter R. Butler, Director Project Directorate I-2 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
SUBJECT:
SALP INPUT FOR HOPE CREEK, SAFETY ASSESSMENT / QUALITY VERIFICATION .
Enclosed is the SALP input for Hope Creek in the functional area of Safety Assessment / Quality Verification.
Input was received from the NRR technical !
staff, and the senior resident at Hope Creek. For additional information, contact Clyde Shiraki at 492-1445.
I L
Walter R. Butler, Director ,
Project Directorate I-2
' Division of Reactor Projects I/II Office of Nuclear Reactor Regulation
Enclosure:
SALP Input cc w/ enclosure:
E. Wenzinger, RI G. Meyer, SRI, Hope Creek i
l i
E_NCLOSURE__
s.
T
_ HOPE CREEK GENERATING STATION SALP INPUT SAFETY ASSESSMENT / QUALITY VERIFICATION I
_ ANALYSIS:
1 This new functional area combines the previous functional areas Activities and Assurance of Quality and assesses the effectiveness of the licensee's programs in assuring the safety and quality of plant opera!
activities.
i i
l Category 2 and noted the inconsistent quality of lice regarding technical content and timeliness. .;
functional area was rated as a Category 2 with an improvinThe Assurance of Qu noted that PSE8G had established the programs, procedures,g The report trend.
and working attention to weak areas such as the engineering departme Since licensingit is a relatively actions as mostnew facility, HCGS does not have the same volume facilities.
During the assessment period sixteen actions (amendments, relief requests, exemptions, etc) were processe,d. The quality of the technical evaluations was generally go participates in industry groups, and uses acceptable approaches to problem l solutions.
necessary corrections were usually prompt and well handled.T Ventilation System. dealt with a license change request to the , and Filtration, Recir additional information, and it was April 1989 before There it was rece was one instance of supplemental information being req Specification reactor protection surveillance system. test intervals and :llowable outage times for the promptly and correctly. The supplemental information was submitted Eulletins) has been timely and complete.The licensee's response t Frequent communications indicate ethat they commence work on their responses sufficiently in advance that
'are able to meet commitment dates without requesting extensions.
operation; for example, all fourteen safety relief valves tested at power following replacement, not just the required five SRVs , and the acceptance criteria for High Pressure Coolant Injection (HPCI) System response time testing were reduced for low pressure conditions. After an acceptable acceptability. HPCI overspeed test, the test was repeated to confirm When a test engineer raised concerns regardin of isolation valves in primary containment ventilation lines,g the concern was the orientation expeditiously initiated. raised to the plant management level and corrective actions were
- - _ _ - _ _ - _ _. _ - _ - _ _ .__- -=- . _ - . ____-
.- V ,
u PSE&G's' adherence to the concept of personal accountability when observing the Senior Nuclear Shift Supervisors (the "y is most noticeable licensed operators held accountable for plantSeniors") operations the on each o shift. The Seniors ensure that they concur with decisions, such as tech specification to interpretations, service, and courses of action. the acceptability of equipment being. returne Each morning, the department mana attend a meeting run by the Senior to discuss plant status and whichplans,gers reinforces the Senior's responsibility and pro have department managers address his concerns.vides the opportunity for him to The meeting provides ready as well as being a vehicle that quickly involves engine operational problems.
During the evaluation of the feedwater flow mea staff displayed a willingness and ability to analyze data and events Independent of the vendor representatives. .
calculations were correct.not accept General Electric (GE) Company error. GE subsequently acknowledged they had made an Problem identification organizational element. occurred both from within and from outside resolve plant problems and off-normal events and for tracking actions to completion. . Hope Creek had 170 Incident Reports in Ahich were reportable to the NRC. 1988, 36 of PerformanceEvaluationSystem(HPES),adetailedanalysismethodforP Determining root causes in incidents involving personnel errors. This analysis of personnel errors. analysis technique has the potential for pro this technique to the personnel errors that occurred during this as period such as those briefly described below.
The facility violated Technical Specifications by operating at nominally 101.2%, worst case 102.2%. Root cause was personnel error in that the established using calculations that were not compen pressure compression.
was not in accordance with NSSS vendor specifications.The omissio (LER88-24)
An isolation of the High Pressure Coolant Injection (HPCI) System occurred during performance of a steam leak detection system surveillance I procedure.
The I&C technician who performed the surveillance failed to place a bypass switch in the BYPASS position per procedure and when terminal leads were lifted during the course of the surveillance, an isolation of the HPCI primary containment outboard steam supply valve occurred.
procedure. Root cause was personnel error in not following an approved (LER88-33)
d,,
v 1
.( n The control room differential pressure was less than technical' specification required values. An engineering review determined that Control Room Emergency Filtration (CREF) system operability had hot been demonstrated. Two root causes were identified: 1) an inadequate surveillance procedure, and 2) inadequate interface testing following an HVAC design change in the area adjacent to'the control room. (LER88-25)
A Nuclear Steam Supply System Shutoff Channel "0" a fuse was blown on a portion of the Channel isolation occurred when-
"D" isolation logic. The t fuse blew during performance of a Maintenance Department I&C surveillance procedure when a meter lead was inadvertently dislodged from test equipment and came in contact with a ground bus-inside the Division 1 Reactor Protection System Lo ReactorWaterCleanup(RWCU)gicCabinet. System outboard The suction isolationisolation causedvalve the to auto close, the "A" and "B" RWCU pumps to trip, and isolated Main Steam Line drain valves and a Reactor Recirculation sample valve. -Root Cause-was the lack of accessibility to testing points inside the subject cabinet, which directly led to the meter lead becoming dislodged. A contributing factor might have been poor work practice or skill. (LER 88-35)
During the performance of an I&C surveillance test procedure, RHR shutdown cooling was isoi-ted because the procedure did not call for lifting a lead to prevent a valve from closing. (LER89-04)
Primary Containment Isolation Yalves were declared inoperable due to a missed' surveillance test that resulted from a personnel error. (LER 88-02)
(
{' A missed surveillance test of the refueling floor exhaust process l radiation monitor Channel "8" caused by a personnel error resulted in a technical specification violation. (LER88-04).
A Design Change Package (DCP) inatequacy resulted in the inputs to the primary containment isolation system being inoperable. (LER88-05) '
An isolation of the reactor water clean up system (ESF actuation) resulted from misuse of test equipment, which caused a blown fuse and ESF actuation. (LER88-18) ,
A power reduction and ESF actuation (RWCU isolation) were caused by loose l terminations on a cabinet internal power supply. (LER88-34)
L i AninadequateDesignChangePackage(DCP)causedanoscillationin L drywell average air temperature measurements. The DCP was inadequately reviewed to determine the impact of its implementation upon the drywell average air temperature measurement. Abnormally oscillating drywell average air temperatures existed for over a month without being detected by operations or engineering personnel, although this parameter is i
recorded daily to ensure compliance with Technical Specifications.
(InspectionReport88-24)
.- ~.
v i
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An uncontrolled electrician jumper was installed in the control circuit of the drywell equipment drain pumps and remained undetected for ten months.
(Inspection Report 89-02)
These items were variously caused by technician error, inadequate procedure review, poor work practices, or a loss of control of equipment. They further i affect the areas of post maintenance testing, workmanship, and management oversight. In some way, they deal primarily with the I & C area. Since the responsibility of QA is to work toward quality operation of the facility, and '
these items are clearly nonsupportive of this goal, QA should be heavily involved trying to determine the causes and recommending solutions. If QA is already involved, their participation is evidently ineffectual.
The Quality Assurance Department, the Onsite Safety Review Group, and the Offsite Safety Review Group are responsible for providing effective, independent review of plant activities. The station quality assurance (QA)..
organization should be providing day-to-day review in the quality control and in-process review areas and should be integrated into the station's resolution of problems. In light of the problems experienced in the I & C area, these 1 groups need to reassess their level of involvement and determine if there is more they can do to be of assistance.
The Station Operations Review Committee (SORC) was composed of department !
managers and provided consistent, effective review of significant plant issues, including design changes, post-trip reviews, reportable events, and station-wide procedures. During the optical isolator failure, the SORC met during the night to review the course of action before its implementation, a good indicatien of the 50RC's role.
Three areas of the QA program were assessed during this assessment period, procurement, receipt inspection, and audits. The three areas continue to be effectively documented and administrative 1y controlled and implemented by trained and qualified personnel. 1 i
Station QA involvement in ISI and startup testing was apparent. In the ISI area OA performed surveillance of in-progress ISI contractor activities, l in-house reviews of contractor ISI procedures and audits at the contractor l
facilities. QA performed many surveillance activities during the post
( refueling startup testing program. However, QA has not devoted the same level of attention to IST as evident by the NRC review and supported by the NRC identified weaknesses noted in the Maintenance / Surveillance Area. In addition, a missed surveillance test and an inoperable valve resulted in a technical specification violation. (LER88-02)
In summary, the performance of the various quality assurance groups has been '
inconsistent. Their involvement in solving the problems of personnel errors, inadequate procedure review, and missed surveillance tests is either nonexistent or ineffcetual. High level management attention is necessary to
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bring the quality of the responsibilities assurance groups together to clearly define or reempha each group.
responsible managers held accountable for the results. Commitments should be Although the licensee's licensing action submittais were generally of go quality, .in the functional area of Safety Assessment / Quality Verification lack of safety effective resulted quality verification in a downward and its corresponding effects on pla trend in this area. An improvement was indicated over the last few months of.the assessment period but close attention is required to determine if'this is a coincidental or significant change, i
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