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Line 27: |
Line 27: |
| Miller to R.G. Byram, " Notice of Violation and Proposed Imposition of Civil Penalties - $210,00," dated June 20, 1997. As a courtesy, I faxed a copy of the PP&L response dated July 30, 1997, to the alleger's home, rather than send him to the FOIA process. | | Miller to R.G. Byram, " Notice of Violation and Proposed Imposition of Civil Penalties - $210,00," dated June 20, 1997. As a courtesy, I faxed a copy of the PP&L response dated July 30, 1997, to the alleger's home, rather than send him to the FOIA process. |
| - The alleger stated that he had a telephone call from Mr. Martin Urban, Manager of PP&L Corporate Auditing. Mr. Urban told the alleger that he was currently , | | - The alleger stated that he had a telephone call from Mr. Martin Urban, Manager of PP&L Corporate Auditing. Mr. Urban told the alleger that he was currently , |
| investigation the "who knew what and when" of the April 9,1997 letter from PP&L ) | | investigation the "who knew what and when" of the {{letter dated|date=April 9, 1997|text=April 9,1997 letter}} from PP&L ) |
| to the NRC. Based on this statement the alleger concluded that Corporate ; | | to the NRC. Based on this statement the alleger concluded that Corporate ; |
| Audittng knows that the April 9,1997 letter was not accurate. The alleger wanted to know if the NRC had received a recent letter from PP&L stating the April 9,1997, letter was inaccurate. I told the alleger that no such letter had -- - | | Audittng knows that the {{letter dated|date=April 9, 1997|text=April 9,1997 letter}} was not accurate. The alleger wanted to know if the NRC had received a recent letter from PP&L stating the {{letter dated|date=April 9, 1997|text=April 9,1997, letter}} was inaccurate. I told the alleger that no such letter had -- - |
| been received by the Resident Office and that PP&L correspondence are typically : | | been received by the Resident Office and that PP&L correspondence are typically : |
| CC'd to our office. | | CC'd to our office. |
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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] |
Text
.. . - -. --.... - . - - - - _ . = - . - - - -. .-- - - . - - - - - _.-.__. - -
AUG-21-1997 15:13 US NRC SUSQ RES OFR cE 717 542 4573 P.02 MEMO T0: Allegation File RI-97-A-145 CC: Paul Swetland, David Vito <
FROM: Brian McDermott, Resident Inspector - Susquehan DATE: August 21, 1997, 11:30 a.m.
SUBJECT:
FOLLOWUP CALL FROM ALLEGER The alleger called in reference to the topics contained in RI-97-A-145.
- The alleger requested a copy of the PP&L response to the NRC letter, H.J. ,
Miller to R.G. Byram, " Notice of Violation and Proposed Imposition of Civil Penalties - $210,00," dated June 20, 1997. As a courtesy, I faxed a copy of the PP&L response dated July 30, 1997, to the alleger's home, rather than send him to the FOIA process.
- The alleger stated that he had a telephone call from Mr. Martin Urban, Manager of PP&L Corporate Auditing. Mr. Urban told the alleger that he was currently ,
investigation the "who knew what and when" of the April 9,1997 letter from PP&L )
to the NRC. Based on this statement the alleger concluded that Corporate ;
Audittng knows that the April 9,1997 letter was not accurate. The alleger wanted to know if the NRC had received a recent letter from PP&L stating the April 9,1997, letter was inaccurate. I told the alleger that no such letter had -- -
been received by the Resident Office and that PP&L correspondence are typically :
CC'd to our office.
- I asked the alleger if there was anything else he needed from me at this time !
and he said "no." The alleger stated that he would keep in touch.
- To followup on the alleger's conclusion, and in accordance the Allegation Panel Decision, I telephoned Mr. Urban for an update on the progress of his i investigation. I asked Mr. Urban if he had information showing that alarm tests
- other than the 'E' DG local panel OC577 - were not tested when required. He said "no." He told me that he was still investigating if other alarms panels had ;
not been tested and in parallel, he is investigating who provided the data for the April 9,1997, PP&L letter, where the information came from, and what was j done to validate it. He stated that the computer records and circumstances 4 surrounding the alarms being. investigated are not as clear cut as the OC577 alarm panel test. He closed by saying that he would notify me as soon as he had evidence to show that other alarms weret not being tested.
l l l
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l August 5,1997
- Mr. Robert G. Byram
{
Senior Vice President Nuclear -
Pennsylvania Power & Light Company
. 2 North Ninth Street Allentown, Pennsylvania 18101
SUBJECT:
.NRC INTEGRATED li4SPECTION REPORT 50-387/97-04, 50-388/97-04; NOTICE OF VIOLATION
Dear Mr. Byram:
. On June 30,1997, the NRC completed an inspection at your Susquehanna Steam Electric Station Units.1 & 2 reactor facilities. The enclosed report presents the results of that inspection. I l
During the 6-week period covered by this inspection, the conduct of activities at the -i facility was characterized generally by safe operation and conservative decision making. In
. . one instance, a Shift Supervisor made good decisions involving the potential for a dual unit shutdown and was deliberate in the communication of this situation to each unit operator.
In a second case, a Unit Supervisor responded, coached 'and coordinated an excellent
^
response to a minor test failure. We noted that operations department management involvement in both issues was aggressive and safety oriented. Of special note was the
- direction and control supplied by the Operations Supervisor in response to charcoal testing operability questions, and the ensuing Notice of Enforcement Discretion.
Based on the results of this inspection the NRC has determined that violations of NRC
. requirements occurred. These violations are cited in the enclosed Notice of Violation (Notice), and the circumstances surrounding the violations are described in detail in the -
enclosed report. Please note that you are required to respond to this letter and should follow the instructions specified in the_ enclosed Notice when preparing your response. The
' violations concerni (1) the failure to adequately test the standby gas treatment system charcoal beds; (2) two examples of a failure to initiate adequate corrective action
. concerning an operability determination for a degraded emergency diesel generator ventilation damper, and the post accident sampling system; (3) failure to get prior NRC approval for an organization change that affected the Quality Assurance Program; and,
-(4) failure to revise the Final Safety Analysis Report after emergency service water (ESW) pump start times were changed by a modification.
The NRClalso determined that violations occurred concerning the staffing of the
'Susquehanna Nuclear Safety Assessment Group (NSAG). These concerns involve the reduction of the dedicated staff size and the qualification of one of the safety engineers.
The latter example is included in the Notice even though it was licensee-identified because 7
- ,w m. " '
, 8W3 0
l.'.
Mr. Robert G. Byram 2 your corrective action did not include measures to prevent recurrence of the problem. ,
Further, several instances of weak management control and oversight of NSAG were j identified including organization changes that could compromise the independence of the l NSAG function, and inadequate planning for implementation of required NSAG functions.
Consequently, in your response to these violations, please address your planned corrective l actions to review and reconcile the activities performed by NSAG and the current licensing i
basis requirements.
In addition, we note that this is the third recent example in which PP&L has been found to ,
l be in violation of NRC requirements because you reasoned that meeting the intent of a l
! technical specification was equivalent to following the requirement as written. The other examples include a blocked open containment isolation valve, previously cited, and the inadequate charcoal filter testing discussed in this report. Therefore, in your response to this letter, please include those additional actions you deem appropriate to assure that all l requirements are strictly adhered to and that appropriate changes wi!I be requested prior to implementing new methods of conformance. The NRC will use your response, in part, to
' determine whether further enforcement action is necessary to ensure compliance with. -
regulatory requirements.
Also of concern during this period was an instance that could have resulted in serious i personnel injury. An activity was identified by the Resident inspector in which your safety i requirements for rigging of heavy loads were not met. Even though there were no ,
violations of NRC requirements, this activities could have resulted in damaged equipment or serious personnel injury. It was noted that Susquehanna plant management and plant safety representatives responded well from a corrective action and investigation standpoint.
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. The responses directed by this letter and the enclosed Notice are not subject to the clearance procedures of the Office of Management and Budget as required by the Paperwork Reduction Act of 1980, Public Law No. 96.511.
Sincerely, Original Signed By:
Charles W. Hehl, Director Division of Reactor Projects Docket Nos.: 50-387;50-388 License Nos: NPF-14, NPF-22 l
Enclosures:
l 1. Notice of Violation l 2. Inspection Report 50-387/97-04,50-388/97-04 1
I-i
a
.,y
{A~
5 21
- c. Conclusigna !
Personnel performance errors, procedural problems and equipment deficiencies were identified during a functional test of the post accident sampling system. During a
- subsequent test, licensee actions were effective in correcting the personnel l performance and procedure issues. However, the licensee's failure to initiate a I
condition report and to repair a non-functional sample holder since August'1994 is cited as a violation of 10 CFR 50 Appendix B, Criterion XVI.
V. Manaaement Meetings X1 - Exit Meeting Summary The inspectors presented the inspection results to members of licensee management at the conclusion of the inspection on June 30,1996. The licensee acknowledged the findings presented.
l X3 Management Meeting Summary i On June 12, the inspector attended a management meeting in the NRC Region I !
l offices between NRC Region i management and representatives of PP&L. The meeting was held to discuss weaknesses noted by NRC in PP&L's approach to the investiga+ ion of technical issues referred to them, and to the lack of comprehensive assessment and corrective measures in response to those investigations. PP&L's presentation materials are attached. During this meeting, PP&L related that a task l
group had been formed to review PP&L's investigation and NRC response practices.
Also, a safety culture assessment had been initiated to measure the climate for
]
safety concerns processing at Susquehanna. The licensee committed to: (1) amend l a prior written response on these issues to more specifically address the scope of l the intended actions, and (2) update the NRC staff with the results of the task i group and safety culture assessments. ;
1 1
I il _ _