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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 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 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 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 ML20207K6711999-03-12012 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980626 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 ML20237E3131998-08-26026 August 1998 Forwards for Public Release,Info Re NRC SMM Held on 980714-15.Summary of January 1998 NRC SMM & Watch List Removal Evaluation Factors Also Encl 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 ML20155J7241998-03-10010 March 1998 Expresses Appreciation for Support in Preparation for & Actual Execution of Full Emergency Exercise for Salem Nuclear Power Plant ML20249C8191998-02-25025 February 1998 Responds to 980224 Memo Re Comnjd 98-002 -- Reduction of Vulnerabilities in Emergency Preparedness ML20249C7961998-02-23023 February 1998 Expresses Disagreement W/Chairman Intent to Replace Commission Diaz on Salem Nuclear Plant Emergency Exercise at Last Minute After Months of Preparation,As Well as Interpretation of Authority in Matter 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 ML20249C7891998-02-0303 February 1998 Expresses Surprise & Confusion by Chairman 980130 Memo Re Invitations to Foreign Officials to Participate as Observers for Salem Nuclear Power Plant Emergency Response Exercise on 980303 ML20249C7831998-01-27027 January 1998 Informs That Argentinians Accepted Invitation to Observe 980303 Salem NPP Exercise ML20249C7771998-01-26026 January 1998 Discusses Visit of Intl Respresentatives to Observe 980303 Salem NPP Emergency Planning Exercise 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 ML20216G5681997-09-0303 September 1997 Notification of 970909 Meeting W/Util in North Bethesda,Md to Discuss Analysis of Plant Spent Fuel Pool Liner ML20141H9671997-07-31031 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970106-10 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 ML20199L6951997-04-0303 April 1997 Forwards OI Rept of Investigation Concerning Plant,Unit 1 Intentionally Operated Outside Design Basis & Failed to Make Timely Notification to NRC of Unanalyzed Condition Re Salem Pressure over-pressure Protection Sys (Case 1-95-013) ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20147B8451997-01-27027 January 1997 Discusses 950524 Drop in Visit Between Pse&G & Nrc. Improvement Efforts at Salem Units 1 & 2 Discussed. Press Releases Encl 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 ML20133G3721997-01-13013 January 1997 Fowards Summary of Common Root Causes of Recent Significant Events at Plant 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 ML20137A9501996-10-29029 October 1996 Informs That G Kenna Travelled to Hancocks Bridge Nj to Assist Insp Closure Re A1-96-029 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 ML20137A9931996-10-0202 October 1996 Requests Answer Re Plants Closure ML20135B3831996-09-13013 September 1996 Discusses 960826 Meeting W/Listed Individuals to Discuss Current Activities & Issues Involving Hope Creek & Salem Npps.Info Partially Deleted ML20135B3781996-08-23023 August 1996 Partially Deleted Memo Re Courtesy Visit W/Ej Ferland & Lr Eliason on 960826 ML20135B3731996-08-23023 August 1996 Partially Deleted Memo Re 960826 Drop in Meeting 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 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 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 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 ML20207K6711999-03-12012 March 1999 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 980626 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 ML20237E3131998-08-26026 August 1998 Forwards for Public Release,Info Re NRC SMM Held on 980714-15.Summary of January 1998 NRC SMM & Watch List Removal Evaluation Factors Also Encl 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 ML20155J7241998-03-10010 March 1998 Expresses Appreciation for Support in Preparation for & Actual Execution of Full Emergency Exercise for Salem Nuclear Power Plant ML20249C8191998-02-25025 February 1998 Responds to 980224 Memo Re Comnjd 98-002 -- Reduction of Vulnerabilities in Emergency Preparedness ML20249C7961998-02-23023 February 1998 Expresses Disagreement W/Chairman Intent to Replace Commission Diaz on Salem Nuclear Plant Emergency Exercise at Last Minute After Months of Preparation,As Well as Interpretation of Authority in Matter 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 ML20249C7891998-02-0303 February 1998 Expresses Surprise & Confusion by Chairman 980130 Memo Re Invitations to Foreign Officials to Participate as Observers for Salem Nuclear Power Plant Emergency Response Exercise on 980303 ML20249C7831998-01-27027 January 1998 Informs That Argentinians Accepted Invitation to Observe 980303 Salem NPP Exercise ML20249C7771998-01-26026 January 1998 Discusses Visit of Intl Respresentatives to Observe 980303 Salem NPP Emergency Planning Exercise 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 ML20216G5681997-09-0303 September 1997 Notification of 970909 Meeting W/Util in North Bethesda,Md to Discuss Analysis of Plant Spent Fuel Pool Liner ML20141H9671997-07-31031 July 1997 Forwards NRC Approved Operator Licensing Exam (Facility Outline & Initial Exam Submittal & as-given Operating Exam) for Tests Administered on 970106-10 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 ML20141E6721997-06-27027 June 1997 Staff Requirements Memo Re Commission Briefing by Licensee, State of Nj & NRC Staff on Status of Restart Activities at Salem.No Requirements Identified for Staff Action ML20199L6951997-04-0303 April 1997 Forwards OI Rept of Investigation Concerning Plant,Unit 1 Intentionally Operated Outside Design Basis & Failed to Make Timely Notification to NRC of Unanalyzed Condition Re Salem Pressure over-pressure Protection Sys (Case 1-95-013) ML20136C1031997-03-0606 March 1997 Forwards Correspondence Transmitted Via Internet to J Zwolinski from P Blanch During 970102-31.Requests Correspondence Be Placed in PDR ML20147B8451997-01-27027 January 1997 Discusses 950524 Drop in Visit Between Pse&G & Nrc. Improvement Efforts at Salem Units 1 & 2 Discussed. Press Releases Encl 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 ML20133G3721997-01-13013 January 1997 Fowards Summary of Common Root Causes of Recent Significant Events at Plant 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 ML20137A9501996-10-29029 October 1996 Informs That G Kenna Travelled to Hancocks Bridge Nj to Assist Insp Closure Re A1-96-029 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 ML20137A9931996-10-0202 October 1996 Requests Answer Re Plants Closure ML20135B3831996-09-13013 September 1996 Discusses 960826 Meeting W/Listed Individuals to Discuss Current Activities & Issues Involving Hope Creek & Salem Npps.Info Partially Deleted ML20135B3781996-08-23023 August 1996 Partially Deleted Memo Re Courtesy Visit W/Ej Ferland & Lr Eliason on 960826 1999-08-05
[Table view] |
Text
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MEMORANDUM FOR: A. R. Blough, Chief i Projects Branch No. 2 Division of Reactor Projects FROM: J. H. Joyner, Chief, Facilities Radiological Safety and Safeguards Branch Division of Radiation Safety and Safeguards
SUBJECT:
EMERGENCY PREPAREDNESS SALP INPUT FOR ARTIFICIAL ISLAND Attached for your information is the subject SALP input relating to emergency preparedness at Artificial Island for the SALP period August 16,1990 through December 31,1991.
Ori;inal Signed gy; lames H. Joyner James H. Joyner, Chief Facilities Radiological Safety l I.
and Safeguards Branch i Division of Radiation Safety !
and Safeguards
Attachment:
As stated l l
.I cc w/ encl:
W. Hehl T. Johnson J. White M. Knapp E. McCabe J. Laughlin !
C. Gordon l i
CW 0 ?
Gy>r ion McCabe J yner l 1/S /92 1/lb/92 1//G/92 j 0 )
OFFICIAL RECORD COPY y l l
l 9702040063 970116 :*
PDR FOIA h!l 0'NEILL96-351- PDR( ;
e .-
l r .- ,
I
\
s Emergency Preparedness (EP)
- 1. Analysis During the previous SALP, EP was rated Category 1. That rating was based on strong management involvement, a highly qualified EP staff, prompt resolution of technical issues, and excellent training. PSE&G was very effective in exercise performance and '
in response to actual events requiring emergency classification.
During this SALP period, the operational status of PSE&G's emergency preparedness program was found superior by NRC review. Management was directly involved in the daily operation of the EP program. Three levels of management provided oversight. Managers at each level were qualified as members of the emergency response organization (ERO), reviewed all changes to the Emergency Plan and Procedures, reviewed drill scenarios, and regularly participated in drills. A thorough audit of the EP program by two independent groups from the Quality Assurance Department identified no deficient program areas. Management also fostered an i excellent relationship with State, county, and local governments through numerous meetings and training sessions, and in support of resolving FEMA-identified concerns.
PSE&G was aggressive in handling technical issues. The EP Department effectively maintained emergency response facilities and implemented a number of significant facility improvements. These included the installation of a new callback system for ERO members, completion of the simulator Safety Parameter Display System (SPDS) links to the Technical Support Center (TSC) and Emergency Operations Facility (EOF). Emergency Response Data System (ERDS) installation is in progress. The new emergency news / community center, which is under construction, also represents a significant off-site PSE&G commitment. The Public Alerting System throughout the Emergency Planning Zone (EPZ) was maintained at 98.8% siren availability, exceeding Federal Emergency Management Agency (FEMA) standards.
Operators at Salem and Hope Creek responded to several actual Unusual Events and ,
one Alert during this assessment period. Operators consistently displayed good knowledge and familiarity with emergency action levels contained in the Event Classification Guide (ECG). Events were correctly classified, and timely notification was made to the States and the NRC. All response actions were consistent with Emergency Plan requirements. During the Alert at Salem Unit 2, PSE&G activated the Salem OSC, providing good in-plant support and assistance in response to the turbine-generator failure.
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' Staffing of the EP program remained strong. The program was maintained by a full time, fully qualified staff of fourteen individuals. The well balanced mix of disciplines included five senior reactor operators, experienced health physicists, and additional staff with experience in radiological contrals and equipment operations. The ERO was also fully staffed, with key managerial positions filled three deep.
EP training was comprehensive, innovative, and thoroughly implemented. Operations and EP personnel training continued to be significantly enhanced through drills on the cor. trol room simulator. Training drills for shift operators were conducted weekly at both facilities. The nine additional extensive training exercises conducted during the period tested major portions of the Emergency Plan. Changes and innovations to EP training methodology were constructive in gralifying ERO staff. ERO qualification was kept at a high level, as demonstrtted in walkthrough training sessions with ERO members. Off-site training was also a strength, with well-developed training and quality information provided to the States and counties.
Training effectiveness was demonstrated by the excellent performance of the ERO during two NRC-observed annual exercises. Both scenarios were very challenging, particularly the 1990 full-participation exercise which involved both plume (10 mile) and ingestion (50 mile) exposure pathways. No weaknesses were identified during this exercise, and only minor areas for improvement were noted. During the 1991 exercise, ERO performance was also effective. An Event Classification Guide
( inadequacy did, however, cause an exercise weakness involving tardy declaration of a Site Area Emergency.
In summary, PSE&G has maintained a sound and effective EP program with clear management commitment to maintaining a highly professional and qualified staff.The EP site staff was proficient in ensuring readiness for implementation of emergency response activities. The training program was thoroughly defined and effectively implemented with different innovative performance-based techniques. The ERO was well qualified as evidenced by exercise performance. Facilities and equipment were well maintained and upgraded in cases where improvements were needed. Licensee support for local governmental and support organizations was strong.
- 2. Conclusion
- 3. Board Recommendation (v
y e . ..
o
- m Artificial Island (Hope Creek and Salem Generating Stations) Proposed SALP Input
( )
SALP PERIOD: May 1,1989 through July 31,1990 Emergencyfrecaredness ( hours; %)
- 1. Analysis The Emergency Plan for Artificial Island covers both Hope Creek and Salem Nuclear Generating Stations, therefore the assessmeni of emergency preparedness is a combined evaluation of both facilities' emergency response capabilities.
During the previous SALP period, this area was rated Category 2. This rating was based on weaknesses identified during a Salem based full-participation exercise, some actual event classification problems, and delays in ensuring that the Salem Technical Support Center could meet NRC design requirements. Strengths noted included a high level of management involvement in emergency preparedness activities, responsiveness to NRC concerns, and an effective emergency preparedness training program.
During this SALP period, two inspections of emergency preparedness activities were conducted, a routine evaluation of the emergency preparedness program, and evaluation of a partial-participation emergency exercise.
( Management involvement in emergency preparedness continues to be effective and extensive. Executives and plant managers maintain emergency response organization position qualification, review and approve plan and procedure changes, participate in drills and exercises, resolve audit noncompliance issues, exercise oversight functions, and interface with Delaware and New Jersey State and County government personnel.
Management oversight includes a review of call-in test results and emergency preparedness training rescheduling. Management has identified emergency preparedness as a key area of reactor safety. Staff play during drills and exercises is considered a management tool which enables managers to evaluate overall staff ,
I attitudes, competency and morale.
Resolution of technical issues continues to be very good and demonstrates a commitment to quality. For example, as a result of an NRC concern, the licensee completed a review of default iodine to noble gas ratios as a function of release pathway, and determined the values were consistent with accident data and emergency off-gas system design and specifications. A four hour, default release duration time has been developed and accepted by the States. User friendly personal computer software has been developed for the back-up dose assessment program. The Technical Support Center ventilation system has been upgraded to meet NRC requirements.
Innovative program activities include development of site Emergency Action Levels (EALs) for natural phenomena and security events to replace individual station EALs, a single Event Classification Guide for all three units, and a simplified EAL (s; description for use in the initial contact message sent to the States, p
A I/
b 3
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P ne licensee has generally been responsive to resolving NRC concerns and has '
committed to using the Hope Creek and Salem simulators to enhance training effectiveness during emergency exercises beginning in 1990. To enhance the training l effectiveness of these facilities, emergency communication systems duplicating those !
in the control rooms were installed in each simulator. Another example of resolving ;
NRC concerns was apparent in review of the licensee's corrective actions following '
loss of the NRC Emergency Notification System (ENS) when it was accidentally disconnected from an uninterruptable power supply (UPS) in May 1990. The
?
licensee's communications staff has aggressively pursued upgrading the Salem j
Telephone Switch Room (location of the ENS UPS connection) and discussed this with NRC's Telecommunication Section. One area not resolved involves the licensee's i
plans to replace the existing Emergency News Center (ENC) in Salem City, New Jersey with an enlarged, dedicated facility. Although this location is about 8 miles from the site, it is the' policy of NRC and FEMA that when new ENCs are !
constructed they should be located outside the emergency planning zone to lessen {
concerns of requiring the ENC to be evscuated during an emergency. The hcensee is aware of this position, but have not changed the proposed location.
. Staffing in the emergency preparedness area is stable with a well-qualified staff available to maintain an effective emergency preparedness program. Personnel with !
operations backgrounds are on staff who develop demanding operations based scenarios for drills and exercises. i
[m}
Management's attention to quality was demonstrated by licensee audits and reviews.
Independent reviews and audits for each unit were completed by independent audit groups. These audits were carried out in keeping with the licensee's Quality Assurance Procedures which are traceable to the requirements of Appendix B to 10 CFR 50. Among other things, drills were observed and the State / County / licensee interface adequacy was determined. There were no significant findings and the licensee /off-site interface was determined to be adequate. Emergency Department personnel with licensee executives and managers attended almost 100 meetings with State and County personnel. The public alerting system is tested daily, and is well maintained with availability at 99.5%, a value which exceeds Federal Emergency Management Agency standards. Independent and redundant siren activating systems are installed and maintained in each State.
Responsibility for emergency preparedness training has been assigned to the Emergency Preparedness Department. Two qualified emergency preparedness trainers have been transferred from the Nuclear Training Center to the Emergency Preparedness Department to support this effort. Weekly, on-the-job, mini training drills for each site have resumed and nine day long drills are also scheduled. Over 1,000 licensee personnel have been trained for Emergency Response Organization (ERO) positions. Here are at least three personnel qualified for each key ERO decision-making and management position. A dedicated emergency preparedness training facility has been placed in service. Engineers assigned to the Technical Support Center and the Emergency Operations Facility are given an overview of s ,
. r 1
3
'S Emergency Plan Implementing Procedures and Core Damage Assessment Procedures.
i However, Emergency Openting Procedures are not covered and severe accident analysis training is not given. The NRC has noted tie absence of severe accident -
analysis training of several consecutive years; trairdng in this area would strengthen licensee performance.
The effectiveness of the training program was demonstrated by response to twelve actual conditions requiring classification, and the strong exercise performance.
Observations of training drills indicated active involvement from licensed senior reactor operators dedicated to drill scenario development. Operations Support Center and Technical Support Center personnel were observed to implement effective problem identification and resolution.
In summary, the licensee maintains a strong and effective emergency preparedness l program. Management remains involved with a demonstrated commitment to quality.
Technical issues are generally promptly resolved and appropriate response is given to NRC initiatives. 7he Emergency Preparedness Program staff is stable and well-qualified to maintain an effective program. Training is well developed and is effective j
as demonstrated by exercise performance and response to actual conditions requiring classification. A good working relationship is maintained with the States and Counties
- with regular meetings, and frequent drills.
- 2. Conclusions i(
s
- 3. Board Recommendations i
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