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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 ML20202F6101998-07-16016 July 1998 Discusses Green Package Containing,In Part Corp Auditing Rept Numbers 739459-97,dtd 971015,redacted , 739459-1-97,dtd 971201,redacted & 739459-2-98, ,redacted ML20202F6341998-04-16016 April 1998 Forwards Info from Very Vocal Alleger Caller Re RI-97-A-0145 Ltr.Allegation Disposition Record Encl ML20202F6681998-03-19019 March 1998 Dicusses Vocal Alleger Who Called Re OI Investigation on Union Guy.Nrc Conducted Insp & Need to Document Results in Insp Rept.Alleger Claims That Investigation Causing Hardships for Union Guy ML20202F6751998-03-18018 March 1998 Forwards Reply to RI-98-A-0007,RI-97-A-0145 & RI-97-A-0282 Re Plant ML20202F6921998-03-18018 March 1998 Requests to Be Informed If Review of Util Audit Will Be in Insp Rept ML20202F7191998-03-0202 March 1998 Forwards Drafts to Be Used Before Replacing Originals Re SSES A-145 Colta ML20202G4101998-02-18018 February 1998 Informs Alleger Caller That Info Requested Will Be Incorporated Into Next Insp Rept & Should Be Received by mid-March ML20202G5011998-02-0505 February 1998 Requests Status of Updating Ltr Re Alleger Caller ML20202G4871998-02-0505 February 1998 Requests Status of Updating Ltr of Alleger Caller ML20202G6291998-01-16016 January 1998 Responds to 980115 Telcon with G Jones & M Urban Re Current Status of PP&L Internal Investigation ML20202G5901998-01-11011 January 1998 Forwards Info Re Diagnostic Plant Control Operator (Pco) Interest in Radiological Waste Control Room Panel Test Computer Point ML20202G6081998-01-0909 January 1998 Forwards Info Re Diagnostic Interest in Radiological Waste Control Room Panel Test Computer Point ML20202G6411998-01-0505 January 1998 Informs That D Vito & C Anderson Will Be Sending Status Ltr to Alleger Caller ML20202G6731997-12-11011 December 1997 Responds to Telcon with G Jones Discussing Delay in Completing Corporate Audit Re Allegation ML20202H1621997-12-0505 December 1997 Partially Deleted Ltr Re Conversation with One of Two Allegers,Informing That Status Ltr Being Work on & Should Be Received by End of Month ML20202G7121997-11-20020 November 1997 Informs That on 971105 NRC Attended Meeting with PP&L Mgt Representative from PP&L Corporate Auditing to Discuss Set of Four Related Issues Involving Operator Performance & Equipment Panel Testing ML20202G8091997-09-19019 September 1997 Forwards Status Rept on 970919 Allegations 97-A-0049 & 97-A-0145 ML20202G8291997-08-21021 August 1997 Informs That Alleger Called in Reference to Topics Contained in RI-97-A-145 ML20202G8571997-07-30030 July 1997 Responds to Monthly Allegation Status Meeting ML20202H1941997-07-17017 July 1997 Partially Deleted Ltr Re Followup Calls on 970624 ML20202H2451997-06-25025 June 1997 Partially Deleted Ltr Re Summary of Info Provided by Allegers ML20202H0731997-06-25025 June 1997 Forwards Current PP&L Corporate Auditing Investigation Re Several Ongoing Investigations at SSES Site ML20202H0781997-06-20020 June 1997 Informs That Fewell Spoke to Two Individuals & Conversation Being Documented & Placed on an Allegation Receipt Form ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20136A6811996-11-25025 November 1996 Partially Withheld Memo Re Director Decision 96-18 Re Petition Filed by P Blanch on 940413 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 ML20059M6601993-11-15015 November 1993 Forwards Revised Task Action Plan for Evaluation of Loss of SFP Cooling Events & Estimate of Staff Resources Required to Complete Action Plan Tasks ML20058P5021990-08-15015 August 1990 Forwards Three Analyses of Shutdown Events Evaluated by Accident Sequence Precursor Program ML20127B5191990-07-0303 July 1990 Clarifies Region I Ofc View of Allegation RI-89-A-0072, Adjustment of Molded Case Circuit Breakers (MCCB) at Susquehanna ML20204J5841988-10-12012 October 1988 Forwards AEOD/E807, Pump Damage Due to Low Flow Cavitation, in Response to Item 5 of Actions Directed by EDO to Respond to Diagnostic Evaluation Team Rept.Nrr Issued Bulletin 88-004 Addressing Low Flow Problem ML20155C6941988-10-0505 October 1988 Advises That Review Briefing for Listed Plants Scheduled for 881013.Viewgraphs Encl ML20151D5951988-07-13013 July 1988 Advises That Plant Review Briefing for Murley & Executive Team Re PDI-2 Plants Scheduled for 880721.Viewgraphs Encl ML20151A3101988-07-0808 July 1988 Forwards Summary & Issue Identification for CRGR Meeting 141 on 880714 Re Degrees for Senior Reactor Operators.Minutes for CRGR Meeting 48 & Analysis of Public Comments Also Encl. W/O Minutes & Analysis ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20195H4441988-02-29029 February 1988 Forwards SALP Input for Plant for Period from Aug 1986 - Jan 1988 ML20245B6801987-12-0303 December 1987 Forwards AEOD Technical Rept Re Mispositioning of Reverse Acting Valve Controllers ML20237L3341987-08-26026 August 1987 Requests Review of Plant Specific & STS with Respect to Allowable Number of Safety Relief Valves Out of Svc at Bwrs. Related Matl Encl ML20207M2171987-01-0707 January 1987 Rev 1 to Notification of SALP Mgt Meeting 87-002 on 870116 W/Util in Berwick,Pa ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20215C4181986-09-30030 September 1986 Notification of License Meeting 86-115 on 861010 at Region I Ofc to Discuss SALP Board ML20210S7421986-09-25025 September 1986 Advises That Allegation RI-86-A-28 Re Auxiliary Operators Leaving Site Prior to Relief,Causing Shortage of Reactor Qualified Operators Closed Due to Lack of Safety Significance ML20204G4051986-08-0404 August 1986 Notification of 860909 Meeting W/Utils in Bethesda,Md to Discuss Nrc/Util Living Schedules,Util Performance,Legal Considerations,Tech Spec Improvements & Severe Accident Policy/Degraded Core Programs.Proposed Agenda Encl IR 05000387/19850281986-06-25025 June 1986 Forwards Util Instrument Channel Functional Testing Program, Per 851017 Notice of Violation from Insps 50-387/85-28 & 50-388/85-23,for Review,Per 860314 Mgt Meeting.Proposed Task Interface Agreement Also Encl ML20214N6491986-06-24024 June 1986 Requests That Listed Utils Be Informed of Deficiencies Re Initial Responses to IE Bulletin 85-003.Detailed Description of Programs to Assure Valve Operability Should Be Submitted by Licensees within 30 Days of Ltr Notification ML20197H5991986-05-13013 May 1986 Notification of Licensee Meeting 86-058 on 860530 in Region I Ofc to Discuss Violation of Limiting Condition for Scram Discharge Vol Level Transmitters ML20199F5081986-03-24024 March 1986 Forwards Schedule for Four Emergency Response Facility (ERF) Appraisals,Per 851003 Memo.Erf Appraisals Will Be Conducted Using Existing Procedure.Draft Ltr to Inform Licensees within 40 Days of Planned ERF Appraisal Also Encl ML20141N6651986-03-11011 March 1986 Responds to 860220 Request for Info Re Secy 85-306,including Licensees Using New Interpretations of App R to 10CFR50 & Effect of New Interpretations on Compliance Schedules in EDO 851226 Memo.List of Plants Requesting Evaluations Provided ML20206M8751986-02-20020 February 1986 Provides NRR Position on What Scope of Testing Necessary to Meet Tech Spec Definition of Channel Functional Test & Whether Util Testing Methods Acceptable,Per 851212 Request ML20141E9281985-12-26026 December 1985 Recommends Survey of Plants Re Licensee Review of Preservice Insp Rept & Submittal of Relief Requests.Relief Requests from Preservice Insp Should Be Submitted Before Issuance of OL & Plant Startup to Permit NRC Review 1999-10-30
[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 ML20202F6101998-07-16016 July 1998 Discusses Green Package Containing,In Part Corp Auditing Rept Numbers 739459-97,dtd 971015,redacted , 739459-1-97,dtd 971201,redacted & 739459-2-98, ,redacted ML20202F6341998-04-16016 April 1998 Forwards Info from Very Vocal Alleger Caller Re RI-97-A-0145 Ltr.Allegation Disposition Record Encl ML20202F6681998-03-19019 March 1998 Dicusses Vocal Alleger Who Called Re OI Investigation on Union Guy.Nrc Conducted Insp & Need to Document Results in Insp Rept.Alleger Claims That Investigation Causing Hardships for Union Guy ML20202F6751998-03-18018 March 1998 Forwards Reply to RI-98-A-0007,RI-97-A-0145 & RI-97-A-0282 Re Plant ML20202F6921998-03-18018 March 1998 Requests to Be Informed If Review of Util Audit Will Be in Insp Rept ML20202F7191998-03-0202 March 1998 Forwards Drafts to Be Used Before Replacing Originals Re SSES A-145 Colta ML20202G4101998-02-18018 February 1998 Informs Alleger Caller That Info Requested Will Be Incorporated Into Next Insp Rept & Should Be Received by mid-March ML20202G4871998-02-0505 February 1998 Requests Status of Updating Ltr of Alleger Caller ML20202G5011998-02-0505 February 1998 Requests Status of Updating Ltr Re Alleger Caller ML20202G6291998-01-16016 January 1998 Responds to 980115 Telcon with G Jones & M Urban Re Current Status of PP&L Internal Investigation ML20202G5901998-01-11011 January 1998 Forwards Info Re Diagnostic Plant Control Operator (Pco) Interest in Radiological Waste Control Room Panel Test Computer Point ML20202G6081998-01-0909 January 1998 Forwards Info Re Diagnostic Interest in Radiological Waste Control Room Panel Test Computer Point ML20202G6411998-01-0505 January 1998 Informs That D Vito & C Anderson Will Be Sending Status Ltr to Alleger Caller ML20202G6731997-12-11011 December 1997 Responds to Telcon with G Jones Discussing Delay in Completing Corporate Audit Re Allegation ML20202H1621997-12-0505 December 1997 Partially Deleted Ltr Re Conversation with One of Two Allegers,Informing That Status Ltr Being Work on & Should Be Received by End of Month ML20202G7121997-11-20020 November 1997 Informs That on 971105 NRC Attended Meeting with PP&L Mgt Representative from PP&L Corporate Auditing to Discuss Set of Four Related Issues Involving Operator Performance & Equipment Panel Testing ML20202G8091997-09-19019 September 1997 Forwards Status Rept on 970919 Allegations 97-A-0049 & 97-A-0145 ML20202G8291997-08-21021 August 1997 Informs That Alleger Called in Reference to Topics Contained in RI-97-A-145 ML20202G8571997-07-30030 July 1997 Responds to Monthly Allegation Status Meeting ML20202H1941997-07-17017 July 1997 Partially Deleted Ltr Re Followup Calls on 970624 ML20202H0731997-06-25025 June 1997 Forwards Current PP&L Corporate Auditing Investigation Re Several Ongoing Investigations at SSES Site ML20202H2451997-06-25025 June 1997 Partially Deleted Ltr Re Summary of Info Provided by Allegers ML20202H0781997-06-20020 June 1997 Informs That Fewell Spoke to Two Individuals & Conversation Being Documented & Placed on an Allegation Receipt Form ML20148F7201997-05-30030 May 1997 Forwards Semiannual Status Rept on Fire Protection Task Action Plan & plant-specific Thermo-Lag Correction Action Programs ML20136A6811996-11-25025 November 1996 Partially Withheld Memo Re Director Decision 96-18 Re Petition Filed by P Blanch on 940413 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 ML20059M6601993-11-15015 November 1993 Forwards Revised Task Action Plan for Evaluation of Loss of SFP Cooling Events & Estimate of Staff Resources Required to Complete Action Plan Tasks ML20058P5021990-08-15015 August 1990 Forwards Three Analyses of Shutdown Events Evaluated by Accident Sequence Precursor Program ML20127B5191990-07-0303 July 1990 Clarifies Region I Ofc View of Allegation RI-89-A-0072, Adjustment of Molded Case Circuit Breakers (MCCB) at Susquehanna ML20204J5841988-10-12012 October 1988 Forwards AEOD/E807, Pump Damage Due to Low Flow Cavitation, in Response to Item 5 of Actions Directed by EDO to Respond to Diagnostic Evaluation Team Rept.Nrr Issued Bulletin 88-004 Addressing Low Flow Problem ML20155C6941988-10-0505 October 1988 Advises That Review Briefing for Listed Plants Scheduled for 881013.Viewgraphs Encl ML20151D5951988-07-13013 July 1988 Advises That Plant Review Briefing for Murley & Executive Team Re PDI-2 Plants Scheduled for 880721.Viewgraphs Encl ML20151A3101988-07-0808 July 1988 Forwards Summary & Issue Identification for CRGR Meeting 141 on 880714 Re Degrees for Senior Reactor Operators.Minutes for CRGR Meeting 48 & Analysis of Public Comments Also Encl. W/O Minutes & Analysis ML20148D9491988-03-15015 March 1988 Discusses 880315 Operating Reactors Events Meeting 88-11. List of Attendees,Events Discussed & Tabulation of long-term Followup Assignments Detailed in Encls ML20195H4441988-02-29029 February 1988 Forwards SALP Input for Plant for Period from Aug 1986 - Jan 1988 ML20245B6801987-12-0303 December 1987 Forwards AEOD Technical Rept Re Mispositioning of Reverse Acting Valve Controllers ML20237L3341987-08-26026 August 1987 Requests Review of Plant Specific & STS with Respect to Allowable Number of Safety Relief Valves Out of Svc at Bwrs. Related Matl Encl ML20207M2171987-01-0707 January 1987 Rev 1 to Notification of SALP Mgt Meeting 87-002 on 870116 W/Util in Berwick,Pa ML20154A2831986-12-13013 December 1986 Forwards Assessments by Enforcement Staff of Regional Performance in Enforcement Area from Jul-Nov 1985 ML20215C4181986-09-30030 September 1986 Notification of License Meeting 86-115 on 861010 at Region I Ofc to Discuss SALP Board ML20210S7421986-09-25025 September 1986 Advises That Allegation RI-86-A-28 Re Auxiliary Operators Leaving Site Prior to Relief,Causing Shortage of Reactor Qualified Operators Closed Due to Lack of Safety Significance ML20204G4051986-08-0404 August 1986 Notification of 860909 Meeting W/Utils in Bethesda,Md to Discuss Nrc/Util Living Schedules,Util Performance,Legal Considerations,Tech Spec Improvements & Severe Accident Policy/Degraded Core Programs.Proposed Agenda Encl IR 05000387/19850281986-06-25025 June 1986 Forwards Util Instrument Channel Functional Testing Program, Per 851017 Notice of Violation from Insps 50-387/85-28 & 50-388/85-23,for Review,Per 860314 Mgt Meeting.Proposed Task Interface Agreement Also Encl ML20214N6491986-06-24024 June 1986 Requests That Listed Utils Be Informed of Deficiencies Re Initial Responses to IE Bulletin 85-003.Detailed Description of Programs to Assure Valve Operability Should Be Submitted by Licensees within 30 Days of Ltr Notification ML20197H5991986-05-13013 May 1986 Notification of Licensee Meeting 86-058 on 860530 in Region I Ofc to Discuss Violation of Limiting Condition for Scram Discharge Vol Level Transmitters ML20210J6121986-03-27027 March 1986 Staff Requirements Memo on 860320 Affirmation/Discussion & Vote in Washington,Dc Re SECY-84-4, Final Rule to Modify GDC 4 of App A,10CFR50, SECY-86-44, Review of ALAB-819, SECY-86-54,SECY-86-64 & SECY-86-80 ML20199F5081986-03-24024 March 1986 Forwards Schedule for Four Emergency Response Facility (ERF) Appraisals,Per 851003 Memo.Erf Appraisals Will Be Conducted Using Existing Procedure.Draft Ltr to Inform Licensees within 40 Days of Planned ERF Appraisal Also Encl ML20141N6651986-03-11011 March 1986 Responds to 860220 Request for Info Re Secy 85-306,including Licensees Using New Interpretations of App R to 10CFR50 & Effect of New Interpretations on Compliance Schedules in EDO 851226 Memo.List of Plants Requesting Evaluations Provided ML20206M8751986-02-20020 February 1986 Provides NRR Position on What Scope of Testing Necessary to Meet Tech Spec Definition of Channel Functional Test & Whether Util Testing Methods Acceptable,Per 851212 Request 1999-10-30
[Table view] |
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- From: F. P ul Bonnett To:
Date: 2/5/98 8:38am
Subject:
Status Ltrs for A-97-0145 (SSES)
Kathy, What is the status of the status fetters updating the status of the allegation to the allegers? (this is like writing "Dilbert" or something).
Paul pg20pg201790129 -
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.M g- UNITED STATES 8 o- NUCLEAR REGULATORY COMMISSION
,N REGloN I
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/ 475 ALLENDALE ROAD KING oF PRUSSIA. PENNSYLVANIA 19406-1415 February 4,1998
' Mr. Robert G. Byram Senior Vice President - Nuclear
- Pennsylvania Power & Ught Company 2 North Ninth Street Allentown, Pennsylvania 18101
SUBJECT:
NRC INTEGRATED INSPECTION REPORT 50-387/97-10, 50-388/97-10
Dear Mr. Byram:
1-On January 19,1998, the' NRC completed an inspection at your Susquehanna Steam
. Electric Station (SSES) 1& 2 reactor facilities. The enclosed report presents the results of that inspection. The inspectors discussed the findings of this inspection with Mr. G.
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Jones, Vice President Nuclear Operations, Mr. G. Kuczynski, General Manager SSES, and others of your staff, at the exit meeting on January 21,1998.
During the 6-week period covered by this inspection report, your conduct of activities was characterized by safe operation and generally conservative decision making. The physical security Inspection concluded that you conducted adequate fitness for duty and access authorization programs, with some minor problems.
Several issues identified d' uring this inspection are of concern. In response to NRC
' inspection findings, you issued a licensee event report that reported the potential loss of a Unit 1 standby liquid control system safety function for up to 75 days. The maximum time allowed by technical specifications (TSs) for this condition is 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />. As discussed at the exit meeting, we understand that you are re-evaluating this issue and we request you complete this evaluation within 20 days. This information will be used to evaluate the unresolved item identified in the enclosed inspection report and to determine whether further NRC action is required.
- Your actions in response to a failure of the Unit 2 rod block monitor were observed and, in general, were considered conservative and safety oriented. However, SSES management chose to enter TS 3 O.3 and did not initiate any action to shutdown the unit, as is intended by the technical specificationi The NRC questioned the appropriateness of the decision to enter TS 3.0.3 and considered managements decision to intentionally not reduce power a .
weakness in implementation of the TS. We request the SSES Plant Operation Review
. Committee formally evaluate the issue to enter TS 3.0.3 within 20 days. This information will be used to evaluate the unresolved item identified in the enclosed inspection report and to determine whether further NRC action is required.
- The NRC considers the issues identified by your independent safety engineering group, in its fall.1997 audit of Operations, to be significant. Your initial efforts in response to these
- issues are viewed as reasonable first steps at corrective action. The effectiveness of your
- corrective actions will be reviewed in future inspections.
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Mr. Robert G. Byram 2
]
In accordance with 10 CFR 2.790 of the NRC's " Rules of Practice," a copy of this letter and its enclosures will be placed in the NRC Public Document Room (PDR).
Sincerely, Original Signed By:
Clifford J. Anderson, Chief Projects Branch No. 4 Division of Reactor Projects Docket Nos.: 50-387;50-388 License Nos: NPF-14, NPF-22
Enclosures:
- 1. Inspection Report 50-387/97-10, 50-388/97-10 * ~
cc w/ encl:
G. T. Jones, Vice President - Nuclear Operations
' G. Kuczynski, General Manager J. M. Kenny, Supervisor, Nuclear Licensing G. D. Miller, General Manager - Nuclear Engineering R. R. Wehry, Nuclear Licensing P. Ray, Nuclear Services Manager, General Electric C. D. Lopes, Manager - Nuclear Security A. Male, Manager, Nuclear Assessment Services H. D. Woodeshick, Special Assistant to the President J. C. Tilton, Ill, Allegheny Electric Cooperative, Inc.
Commonwealth of Pennsylvania
. . . - . .. .. - ., . -- - - - . . _ . - . - ~ . . . - . - .- - .. .
'O s f' U. S. NUCLEAR REGULATORY COMMISSION REGION I Docket Nos: 50-387, 50-388 License Nos: NPF-14, NPF-22 Report No. 50-387/97-10, 50-388/97-10 Licensee: Pennsy!vania Power and Light Company 2 North Ninth Street Allentown, Pennsylvania 19101 Facility: Susquehanna Steam Electric Station ' ~
Location: P.O. Box 35 Berwick, PA 18603-0035
- Dates: December 9,1997 through January 19,1998 i l
inspectors: K. Jenison, Senior Resident inspector
- B. McDermott, Resident inspector J. Richmond, Resident inspector G. Smith, Senior Security Specialist Approved by: Clifford Anderson, Chief Projects Branch 4 Division of Reactor Projects i
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04 ' Operator Knowledge and Performance . L 04.1 Emcronmental Factors and Ooerator Performance
- a. Insoection Scone (71707)
Various PP&L internal reports have indicated that environmental factors have created a stressful working relationship between Operations personnel and management. The inspectors reviewed these documents and conducted interviews to evaluate PCO and Nuclear Plant Operator (NPO) performance. The inspector reviewed an Independent Safety Engineering Group (ISEG) report, dated December 19,1997, a sample of Nuclear Assessment Services (NAS)
, surveillances, and a letter from the Operations Manager to a distribution list, dated December 31,1997. The inspector discussed these issues with SSES
. Management, the ISEG Supervisor, the NAS surveillance group supervisor and selected auditors, and various representative from the Operations Department.
Further, the inspector observed a sample of operator activities.
I L b ,- Observations and Fndincs J 1
Observations I 1
The ISEG report indicated that the quality of in-plant watch standing was improved !
and that in-plant evolutions'were well done. However, the relationship between I
Operations Department Management and the rank and file of the Operations j Section needed to be improved. The NAS surveillances noted effective i communications and operator work performance. Yet some weaknesses in the !
scheduling of plant activities cause a conflict and impact on PCO ability to j
. complete some activities. The inspector determined that operator activities were !
. in general being well performed, but that there were organizational environmental ;
factors which posed challenges to SSES management. '
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During the observation of NPOs and PCOs, the inspectors found the assigned activities to be currently performed in a professional, aggressive and effective manner. Operators were able to describe the activity they were performing, the impact on other plant equipraent, and appropriate PP&L controls and procedures applicable to the performed activity. However, the inspector discerned a concern on the part of the NPOs and PCOs that managements expectations were not always clear and often affected the performance of operator's activities.
The inspectors observed US, AUS, and STA activities, which included a plant inspection, interfacing with control room staff, and providing direct supervision of the NPO and ASO shift staff. Adequate technical direction was observed to be provided to the NPOs and ASOs by the supervisors. Communications between the supervisors and the SS, STA, and the NPOs and ASOs were clear and concise.
Conduct of the supervisors appeared professional and appropriate. The inspectors discussed separately management expectations for operator performance and the lines of communications between the operators and plant management with the supervisors. The supervisors were confident the NPOs and ASOs clearly understood their expectations and stated the work performance of the NPOs and ASOs satisfied their expectations. The supervisors felt they clearly understood the expectations of their direct supervisor, the SS, and believed they met those expectations. However, the supervisor's felt the organizational environment and the lines of communications between the shift operators and management needed improvement.
The inspector discussed his observations with the Site Vice President, General Manager SSES, and Manager of Operations. During one conversation, the job performance functions issues and the ISEG report were discussed specifically.
PP&L is working to resolve issues involving the PCO, NPO and ASO job performance associated functions through a bargaining unit negotiation process.
The ISEG report is being addressed through normal management actions much the same way that a cultural survey was resolved in 1997. Operations management was observed to be sensitive to the need for a quick resolution of operator related issues and continues to communicate a safety oriented approach to the operation of the units. PP&L management stated that they are expending considerable resources trying to resolve these issues but do not find that the issues are affecting the safety of the units.
Findinas in general, the inspectors found the operations department personnel to be well aware of plant activities, their individual performance, and the overall condition of their assigned units. The US were very able to describe their actions, direct the actions of the PCO, research the resolution of technicalissues using the tools available to them in the control room, and control the release of work i authorizations. l I
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The inspectors were able to verify the conclusions made by the ISEG and the NAS concerning present operator performance. Through conversations with SSES workers the inspectors were also able to verify some individuals felt the need to improve specific organizational environmental factors, including communications between management and workers. SSES Management is establishing general approaches to the resolution of identified organizational environmental factors including bargaining unit negotiation, PP&L leadership training, increased communications between management and workers, PP&L human resources programs, PP&L employee concerns program initiatives in supervision, Operator Department Focus Group activities, and responses to the findings from the 1997 cultural survey and ISEG report. The inspectors concluded that organizational environmental factors were determined to have no current visible impact on the safe operation of the plant.
- c. - Conclusions Operator performance was reviewed by direct observations, interv.iews, and -.-
evaluations of PP&L self assessments. The inspectors verified the weaknesses, identified by the PP&L self assessments, that were described as environmental '
factors. Despite the weaknesses, the inspectors verified current operator performance was very good. PP&L management is establishing general approaches to resolve these weaknesses. The identified weaknesses currently have no apparent impact on the safe operation of SSES.
.. .