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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: thy odes /
To: A, JV, SLJ Date: 1/5/98 :27pm
Subject:
Allegation RI-97-A-0145 Susquehanna ,
The alleger called to inquire as to a letter we owe him. After speaking with Dave Vito and Cliff Anderson, we will be sending the alleger a status letter- trying to tell him everything we can tell. I told this to the alleger and he was very upset. He said that PP&L are using us. The report that supposedly won't be done until February 1998 is actually comple':ed, but if PP&L released it now -it would destroy their arbitration case i against the alleger (i.e., the alleger would win his 1 % year battle). The alleger said that :
PP&L doesn't have anything more to investigate -it is only a delay tactic. I told the !
alleger that I would inform the Branch Chief of this information. the alleger asked to speak with Cliff Anderson and Hub Miller...I transferred him to Cliffs voice mail.
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Briefing Notes l As part of an investigation conducted by Corporate Audidng into allegations raised by a former Nuclear Plant Operator,a PCO voluntaared certain information to the auditors and lator subrnitted a written statement to Nuclear Dept. Management.
While we appreciate the individual's candor and encourage all employees to be truthful during such an investigation, Supervision and Management must take appropriate action on the basis of information we learn.
l The PCO will not be returned to licensed duties AT THIS TIME. He continues his current assignment to the Training Center pending completion of an assessment into '
his ability to perform work as a licensed operator, l' .
l The PCO admitted two Instances of human error where he failed to perform ticensed {
) duties in accordance with station procedures and programs while signing
- documentation that he had done so.
The PCO self corrected the eerors on the following day by performing the' required action, he did not Inform his immediate' supervisor or management of this error. The failure to do so doeir not meet the standards and expectations of the licensed operator.
Supervision and management have a responsibility to assess human performance
' errors and determine the significance of these errors. Without the knowledge, the ability to operate the facility safely may be jeopardized. .
1 The responsible behavior program has been applied for this ovent. The bases for this action is as stated above.
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' NUCLEAR REGULATORY COMMISSION ResidentInspector O. Dice
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December 31,1997 Mr. Robert G. Byram I
Senior Vice President - Nuclear Pennsylvania Power & Light Company 2 North Ninth Street Allentown, Pennsylvania 18101 :
SUBJECT:
NRC INTEGRATED INSPECTION REPORT 50-387/97-09,50-388/97-09 AND NOTICE OF VIOLATION.
Dear Mr.' Byram:
On December 8,1997, the NRC completed a routine resident inspection at your Susquehanna Steam Electric Station facility. The enclosed report presents the results of that inspection. In addition, this report contains the results of a physical security 2 inspection conducted by inspectors from the NRC Region i office.
l Your conduct of activities at the facility during this period was characterized by safe operation and generally conservative decision making. The physical security inspection j concluded that you have maintained an effective security program and that your provisions '
for lar?d vehicle control satisfy regulatory requirements and previous PP&L commitments. l Several issues identified during this inspection regarding PP&L's strategy for resolving deficiencies with the containment isolation configuration for feedwater penetrations are of concern. Although more informatior is required for the NRC to make conclusions regarding ,
potential enforcement actions, we believe these issues have not been adequately ;
communicated to the NRC or evaluated by PP&L for regulatory compliance. Based on our December 19,1997, conference call with Mr. J. Kenny of PP&L, we understand that PP&L will submit a letter in January 1998 to provide information regarding the deficiencies, compliance with applicable design requirements, and plans for corrective action. This information will be used to evaluate the unresolved items identified in the enclosed inspection report, and to determine whether further NRC action is required.
Based on the other results of this inspection, the NRC has determined that one violation of NRC requirements occurred. This violation is cited in the enclosed Notice of Violation (Notice), and the circumstances surrounding the violation are described in detailin the enclosed report. The violation concerns the adequacy of procedures used to control maintenance on a reactor coolant system valve's bonnet vent line. The procedures were inadequate to ensure that the vent line was supported in accordance with its design configuration and consequently a vent line weld failed due to cyclic fatigue while in service. 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 NRC will use your response, in part, to determine whether further enforcement action is necessary -
to ensure compliance with regulatory requirements.
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Mr. Robert G. Byram 2 l
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:
l; :Clifford J.~ Anderson, Chief L Projects Branch 4
- Division of Reactor Projects v
Docket Nos.: 50-387:50-388
. License Nos:' NPF-14, NPF-22 - ,
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Enclosures:
- 1. Inspection Report 50-387/97-09,50-388/97-09
- 2. Notice of Violation cc w/ enc!:
- - G. T. Jones, Vice President - Nuclear Operations G. Kuczynski, General Manager J. M. Kenny, Supervisor, Nuclear Licensing G. D. Miller, General Manager - Nuclear Engineering ls R. R. Wehry, Nuclear Licensing M. M. Urioste, Nuclear Services Manager, General Electric l C. D. Lopes, Manager - Nuclear Security l
A. Male, Manager, Nuclear Assessment Services
.H. D. Woodeshick, Special Assistant to'the President J. C. Tilton,111, Allegheny Electric Cooperative, Inc.
- i. Commonwealth of Pennsylvania -
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02 Operational Status of Facilities and Equipment O2.1 "E" Emeroency Diesel Generator (EDG) Alarm Panel OC577E Ooeration . -
- a. insoection Scoce (71707]
On February 13,1997, the licensee performed routine alarm testing of the OC577E control panelin the "E" EDG building. During the performance of this routine test a plant control operator (PCO) noted that an expected control room alarm panel (AR-016-F02) did not reflash. .The inspector reviewed this panel test failure and the licensee's corrective actions,
- b. Observations and Findinos Control Panel'OC577E contains local controls for certain "E" EDG support equipment and associated annuncistors. Testing this local alarm panel results in a -
common control room panel alarm, two Unit 1 computer data points and two Unit 2 4 computer data points.
Following the control panel alarm test failure, the licensee initiated a condition report (CR) 97-0289 and work authorizations (WAs) S70529 and S66261. The inspector reviewed the associated WAs and drawing FF65111. WA S70529 was initiated on February 15,1997 to determine why the control room did not get a reflash during the February 13,1997, panel test.
During this initialinvestigation PP&L determined that the input to the Unit 2 computer for point EGZ12 had been degraded since August 13,1996. WA S66261 was written to correct this problem. This review also determined that the Unit 1 computer was capable of recording point EGZ12 and that both computers were capable of recording point EGZ14.-
On February 13,1997, at the time that the failed alarm test was performed, a separate plant testing activity was being performed under test procedure (TP) TP-024-149. This TP controlled the positions of breakers OB56502A and OB56503A
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causing several alarms to be activated in the control room and locally. Because the l control room annunciator was already alarmed, the February 13,1997, test at panel i OC577E should have caused the control room annunciator to reflash. However,it l did not reflash because the reflash unit had failed. Based on review of the data, the failure of the reflash unit affected the records for computer point EGZ14 on the Unit 1 and Unit 2 computers. The record for Unit 1 computer point EGZ12 was unaffected by the reflash unit failure and provided a valid record of the OC577E panel alarm test on February 13,1997.
After completing a review of the above data, the inspector determined that the alarming /reflashing of specific control room annunciators related to OC577E panel tests were affected by activities conducted under TP-024-149in combination with
- the failure of a reflash unit. The Unit 1 and Unit 2 computer points EGZ14 were I
affected by the failure of the reflash function. Computer point EGZ12 on Unit 2 l was degraded during the February 13,1997 panel tests and did not always accurately register the panel test. Unit 1 computer point EGZ12 was operable throughout the February 13,1997 test and was unaffected. There was no -
evidence to indicate that the interaction of TP-024-149,the alarm test at control panel OC577E and the failure of the reflash unit was other than an isolated instance. Further, there is no evidence of previous repeated failures of the reflash )
units. The licensee's corrective actions and root cause determination associated with CR-97-0289 were determined to be adequate; operator response to the test failure was determined to be acceptable; and no violations of NRC requirements were identified.
- c. Conclusions l Following a February 13,1997, local control panel alarm test failure, the licensee initiated a condition report (CR) and work authorizations to determine why an associated control room annunciator did not reflash as expected. The CR i investigation determined that the annunciator reflash did not occur because of a I failed reflash unit. The Unit 1 and Unit 2 computer records for point EGZ14 were i affected by the reflash unit failure, however, there was no evidence to indicate that this condition was other that an isolated instance. Unit 1 records for computer point i EGZ12 were found to provide an accurate record of the February 13,1997 test. l The licensee's corrective actions and root cause determination associated with CR-97-0289 were determined to be adequate, as was operator response to the routine alarm panel test failure. No violations of NRC requirements were identified.
l l !
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