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Category:LICENSEE EVENT REPORT (SEE ALSO AO RO)
MONTHYEARNPL-97-0565, LER 97-S02-00:on 970815,perimeter Zones,Doors & Cameras Were Lost.Caused by Inadequate Compensatory Measures Taken for Failed Multiplexer.Repaired Mux for e-field Zone 81997-09-15015 September 1997 LER 97-S02-00:on 970815,perimeter Zones,Doors & Cameras Were Lost.Caused by Inadequate Compensatory Measures Taken for Failed Multiplexer.Repaired Mux for e-field Zone 8 NPL-97-0061, LER 97-S01-00:on 970204,compensatory Measures for Microwave Zones Had Not Been Implemented.Caused by Mgt Oversight of CAS & SAS Activities Was Inadequated.Addl Mgt Oversight of CAS & SAS Operations Has Been Implemented1997-03-0404 March 1997 LER 97-S01-00:on 970204,compensatory Measures for Microwave Zones Had Not Been Implemented.Caused by Mgt Oversight of CAS & SAS Activities Was Inadequated.Addl Mgt Oversight of CAS & SAS Operations Has Been Implemented 05000266/LER-1993-0071993-08-25025 August 1993 LER 93-007-00:on 930726,EDG Inadvertently Started and Station Battery Tripped Off Due to Undervoltage Signal. Caused by Blown Fuse as Result of Human Error During Calibr of 1A-06 Voltmeter.Fuse replaced.W/930825 Ltr 05000266/LER-1993-001, Revised LER 93-001-00:on 930107,all 4,160 Volt Degraded Grid Voltage Protection Channels Declared Inoperable Due to Discovery That Settings for Relays on Subj Channels Being Too Low.Plant Mods Will Be Made1993-02-16016 February 1993 Revised LER 93-001-00:on 930107,all 4,160 Volt Degraded Grid Voltage Protection Channels Declared Inoperable Due to Discovery That Settings for Relays on Subj Channels Being Too Low.Plant Mods Will Be Made 05000266/LER-1992-004, Corrected LER 92-004-00:on 920515,determined That One Svc Water Pump & One Containment Ventilation Fan Sequenced Onto EDG More Times than Listed in Fsar,Section 8.2.3.Caused by Time Delay Relay Out of Tolerence.Evaluation Under1992-07-0909 July 1992 Corrected LER 92-004-00:on 920515,determined That One Svc Water Pump & One Containment Ventilation Fan Sequenced Onto EDG More Times than Listed in Fsar,Section 8.2.3.Caused by Time Delay Relay Out of Tolerence.Evaluation Underway ML20077R5181991-08-14014 August 1991 LER 91-S01-00:on 910715,informed of Inadequate Preemployment Screening Process.Caused by Contractor Failure to Inform Util Employees Had Been Denied Access at Facility.Release & Authorization Form Revised 05000266/LER-1990-0061990-07-18018 July 1990 LER 90-006-00:on 900619,nuclear Instrumentation Turbine Runback Occurred.Caused by Spurious Signal Believed to Have Been Negative Spike.Voltage Spike Considered Spurious. W/900718 Ltr 05000266/LER-1985-002, Forwards LER 85-002-01 Re Details of Fuel Damage Found on Fuel Assembly H14,which Spent Last Cycle in Core Position D12.Rept Suppls Original Rept1986-05-19019 May 1986 Forwards LER 85-002-01 Re Details of Fuel Damage Found on Fuel Assembly H14,which Spent Last Cycle in Core Position D12.Rept Suppls Original Rept ML20203L0281986-04-25025 April 1986 Informs of Planned Site Visit to Obtain Info Supporting Implementation of Emergency Response Data Sys,Including Availability of PWR or BWR Parameters in Digital Form & Characterization of Available Data Feed Points 05000266/LER-1982-009, Telecopy Message of LER 82-009/01T-0:on 821030,tubes in Steam Generators a & B Found W/More than 40% Degradation.On 821025,insp Revealed 5 Wet or Dripping Explosive Plugs.No Cause Stated.Tubes Plugged1982-11-0101 November 1982 Telecopy Message of LER 82-009/01T-0:on 821030,tubes in Steam Generators a & B Found W/More than 40% Degradation.On 821025,insp Revealed 5 Wet or Dripping Explosive Plugs.No Cause Stated.Tubes Plugged 05000301/LER-1982-005, Updated LER 82-005/01T-1:on 820727,discovered 2 of 3 Level Instruments on C Boric Acid Storage Tank Powered from Common Source.Cause Not Determined Due to Poor Early Maint of Documents.Wiring Corrected1982-09-28028 September 1982 Updated LER 82-005/01T-1:on 820727,discovered 2 of 3 Level Instruments on C Boric Acid Storage Tank Powered from Common Source.Cause Not Determined Due to Poor Early Maint of Documents.Wiring Corrected ML20147C2781978-12-11011 December 1978 /03L on 781121:failure to Submit RO 50-366/78-55 W/In 30 Days.Caused by Deviation Rept 2-78-79 Not Received by Responsible Dept Head Nor Superintendent of Plant Engr Svcs.Personnel Were Reminded of Procedures ML20062E6581978-11-17017 November 1978 /01T-0 on 781106:turbine Runback Resulted from Safeguards Bus Tie Breaker Trip.Westinghouse Model CV-7 Undervoltage Relay on Tie Breaker Tripped Causing Breaker to Open.No Line Voltage Surges Detected ML20064E8621978-10-23023 October 1978 /01T-0 on 781009:snubber on Pressurizer Relief Line Was Found Inoperable.Grinnel Model HS-17,21/2 Inch X 5 Inch Bore & Stroke Snubber Failed for Undetermined Cause. Snubber Replaced & Surveillance Prog Expanded ML20062D4531978-10-13013 October 1978 /03L-0 on 780913:on 2 occasions,2 of 3 Charging Pumps Were isolated.2 3/4 Crosby Relief Valves Leaked Through Causing Temporary Loss of Charging Flow.Charging Pump Relief Valve Replaced & a Pump Returned to Svc ML20062D4671978-10-12012 October 1978 /01T-0 on 780928:reactor Coolant Sys Pressure Began Dropping at 25 Psi Per Minute;Pressurizer Spray Value 431B Found Partially Open Despite Shut Signal Due to 0 Set Point Drift Caused by Heat Degradation in Transducer ML20062D3201978-09-29029 September 1978 /1T-0 on 780928:reactor Coolant Sys Pressure; Dropped.Rate in Decrease Reached 25 Psig Per Minute. Pressure Decrease Caused by Failed elec-to-air Signal Converter 1997-09-15
[Table view] Category:TEXT-SAFETY REPORT
MONTHYEARNPL-99-0569, Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with1999-09-30030 September 1999 Monthly Operating Repts for Sept 1999 for Pbnp,Units 1 & 2. with ML20212D5961999-09-15015 September 1999 Safety Evaluation Supporting Licensee IPEEE Process.Plant Has Met Intent of Suppl 4 to GL 88-20 NPL-99-0051, Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with1999-08-31031 August 1999 Monthly Operating Repts for Aug 1999 for Pbnp,Units 1 & 2. with NPL-99-0449, Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with1999-07-31031 July 1999 Monthly Operating Repts for July 1999 for Pbnp,Units 1 & 2. with ML20196J4251999-06-30030 June 1999 Safety Evaluation Authorizing Proposed Alternatives Described in Relief Requests VRR-01,ROJ-16,PRR-01 & VRR-02 ML20209D2691999-06-30030 June 1999 Monthly Operating Repts for June 1999 for Pbnps,Units 1 & 2 ML20196F3341999-06-22022 June 1999 Safety Evaluation for Implementation of 422V+ Fuel Assemblies at Pbnp Units 1 & 2 ML20195F9781999-06-10010 June 1999 Unit 2 Refueling 23 Inservice Insp Summary Rept for Form NIS-1 ML20209D2751999-05-31031 May 1999 Revised MORs for May 1999 for Pbnps,Units 1 & 2 NPL-99-0328, Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with1999-05-31031 May 1999 Monthly Operating Repts for May 1999 for Pbnp,Units 1 & 2. with NPL-99-0273, Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With1999-04-30030 April 1999 Monthly Operating Repts for Apr 1999 for Point Beach Nuclear Plant,Units 1 & 2.With ML20196F3521999-04-30030 April 1999 Non-proprietary WCAP-14788, W Revised Thermal Design Procedure Instrument Uncertainty Methodology for Wepc Point Beach Units 1 & 2 (Fuel Upgrade & Uprate to 1656 Mwt - NSSS Power) NPL-99-0193, Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with1999-03-31031 March 1999 Monthly Operating Repts for Mar 1999 for Pbnp,Units 1 & 2. with NPL-99-0134, Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with1999-02-28028 February 1999 Monthly Operating Repts for Feb 1999 for Pbnp,Units 1 & 2. with ML20207D6751999-02-22022 February 1999 Assessment of Design Info on Piping Restraints for Point Beach Nuclear Plant,Units 1 & 2.Staff Concludes That Licensee Unable to Retrieve Original Analyses That May Have Been Performed to Justify Removal of Shim Collars ML20206R9001999-01-13013 January 1999 SER Accepting Nuclear Quality Assurance Program Changes for Point Beach Nuclear Plant,Units 1 & 2 NPL-99-0008, Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with1998-12-31031 December 1998 Monthly Operating Repts for Dec 1998 for Pbnp,Units 1 & 2. with NPL-99-0091, 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with1998-12-31031 December 1998 1998 Annual Results & Data Rept for Pbnps,Units 1 & 2. with ML20198C7671998-12-10010 December 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME BPV Code,1986 Edition,Section XI Requirement IWA-2232, to Use Performance Demonstration Initiative Program During RPV Third 10-yr ISI for Plant,Unit 2 NPL-98-1006, Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-11-30030 November 1998 Monthly Operating Repts for Nov 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20195J5101998-11-16016 November 1998 Proposed Revs to Section 1.3 of FSAR for Pbnp QA Program ML20198J5941998-11-0303 November 1998 1998 Graded Exercise,Conducted on 981103 NPL-98-0948, Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-10-31031 October 1998 Monthly Operating Repts for Oct 1998 for Point Beach Nuclear Plant,Units 1 & 2.With NPL-98-0880, Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored1998-10-21021 October 1998 Special Rept:On 980913,fire Alarm Control Panels Inoperable for More That Fourteen Days.Troubleshooting of D-401 Panel Following Installation of Replacement Batteries Revealed No Apparent Cause for Spurious Alarms.Panel D-401 Restored ML20154M9121998-10-14014 October 1998 Unit 1 Refueling 24 Repair/Replacement Summary Rept for Form NIS-2 ML20154L6751998-10-14014 October 1998 Unit 1 Refueling 24 ISI Summary Rept for Form NIS-1 NPL-98-0826, Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With1998-09-30030 September 1998 Monthly Operating Repts for Sept 1998 for Point Beach Nuclear Plant,Units 1 & 2.With ML20151W3851998-08-31031 August 1998 Monthly Operating Repts for Aug 1998 for Pbnp Units 1 & 2 NPL-98-0653, Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 21998-07-31031 July 1998 Monthly Operating Repts for July 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4471998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 2 ML20151W4541998-07-31031 July 1998 Corrected Page to MOR for July 1998 for Pbnp Unit 1 ML20236Q3161998-07-10010 July 1998 Safety Evaluation Accepting Licensee Proposed Alternative to ASME Code Requirements PTP-3-01 & PTP-3-02 ML20236L6771998-07-0707 July 1998 Safety Evaluation Approving Wepco Implementation Program to Resolve USI A-46 at Point Beach NPP Units 1 & 2 NPL-98-0558, Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 21998-06-30030 June 1998 Monthly Operating Repts for June 1998 for Pbnp,Units 1 & 2 ML20151W4261998-06-30030 June 1998 Corrected Page to MOR for June 1998 for Pbnp Unit 2 ML20151W4221998-05-31031 May 1998 Corrected Page to MOR for May 1998 for Pbnp Unit 2 NPL-98-0481, Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 21998-05-31031 May 1998 Monthly Operating Repts for May 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W4011998-04-30030 April 1998 Corrected Page to MOR for April 1998 for Pbnp Unit 2 NPL-98-0356, Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 21998-04-30030 April 1998 Monthly Operating Repts for April 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20217F3131998-04-17017 April 1998 Safety Evaluation Accepting Proposed Alternative to ASME Code for Surface Exam of Nonstructural Seal Welds,For Plant, Unit 1 ML20216D7071998-03-31031 March 1998 Monthly Operating Repts for Mar 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3981998-03-31031 March 1998 Corrected Page to MOR for March for Pbnp Unit 2 NPL-98-0209, Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable1998-03-30030 March 1998 Special Rept Re Fire Barrier Inoperable for Greater than Seven Days.Compensatory Measures Implemented in Accordance W/Fire Protection Program Requirements During Time That Barriers Were Inoperable ML20217A8501998-03-19019 March 1998 SER Accepting Proposed Changes Submitted on 980226 by Wiep to Pbnp Final SAR Section 1.8 Which Will Impact Commitments Made in Pbnp QA Program Description.Changes Concern Approval Authority for Procedures & Interviewing Authority ML20216J0101998-03-17017 March 1998 Safety Evaluation Accepting Third 10-yr Inservice Insp Interval Relief Request RR-1-18 for Plant NPL-98-0159, Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 21998-02-28028 February 1998 Monthly Operating Repts for Feb 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20151W3891998-02-28028 February 1998 Corrected Page to MOR for Feb 1998 for Pbnp Unit 2 ML20216D7121998-02-28028 February 1998 Revised Corrected MOR for Feb 1998 for Point Beach Nuclear Plant,Unit 2 NPL-98-0084, Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 21998-01-31031 January 1998 Monthly Operating Repts for Jan 1998 for Point Beach Nuclear Plant,Units 1 & 2 ML20198L1151998-01-0808 January 1998 SER Accepting Licensee Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, for Point Beach Nuclear Plant,Units 1 & 2 1999-09-30
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. Wisconsin Electnc POWER COMPANY Point Beach Nuclear Plant (414) 755-2321 6610 Nuclear Rd.. Two Rivers. WI 54241 NPL-97-006i March 4,1997 Document Control Desk l U.S. NUCLEAR REGULATORY COMMISSION Mail Station Pl-137 l Washington, DC 20555 Ladies / Gentlemen:
DOCKETS 50-266 AND 50-301 SECURITY REPORTABLE EVENT 97-S01-00 POINT BEACH NUCLEAR PLANT. UNITS 1 AND 2 Enclosed is Security Event Report 97-S01-00 for Point Beach Nuclear Plant, Units 1 and 2. This i
report is provided in accordance with 10 CFR 73.71(b)(1), which requires a 30-day written report to be submitted for safeguards events defined in 10 CFR 73 Appendix G.I.c, "Any failure, degradation, or discovered vulnerability in a safeguards system that could allow unauthorized or undetected access to a protected area, material access area, controlled access area, vital area, or transport for which compensatory measures have not been employed."
If yoa require additional information, please contact us.
Sincerely,
&Q .fh - -
Douglas F. Johnson f Manager, ,
Regulatory Services and Licensing g FAF/
eg(?
Enclosure .
1
\ l cc: NRC Resident Inspector NRC Regional Administrator bec: Flentje, Johnson, Malanowski, McCullum, Patulski, 9703110188 970304 "'
PDR ADOCK 05000266~
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NRC FORM 388 U.S. NUCLEAR REOULATORY COMMISSION APPRaVED SY OMS LQ. 31804104
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(4-95) EXPIRES 04/30/98 ESTIMATED BURDEN PER RESPONSE TO COMPLY WITH THIS INFORMATION COLLECTION REQUEST: 50.0 HRS.
LICENSEE EVENT REPORT (LER) REPORTED LESSONS LEARNED ARE INCORPORATED INTO THE LICENSING PROCESS AND FED BACK TO INDUSTRY.
4 FORWARD COMMENTS REGARDING BURDEN ESilMATE (See reverse for required nurnber of TO THE INFORMATION AND RECORDS MANAOEMENT digits / characters for each block) BRANCH (T-6 F33), U.S. NUCLEAR REOULATORY COMMIS$10N, WASHINGTON, DC 20555-0001, AND TO THE PAPERWORK REDUCTION PROJFCT FACILITY NAME (1) DOCKET NUMSER (2) PAGE (3)
Point Beach Nuclear Plant, Unit 1 05000266 1 OF 3 TITLE (4)
Uncompensated PA Alarm Zone EVENT OATE (S) LER NUMSER (S) REPORT DATE (7) OTHER FACILITIES INVOLVED IS) l SEQUENTIAL REVISION FACILITY NAME DOCKET NUMBER MONTH DAY YEAR IYEAR NUMBER NUMBER MONTH DAY YEAR Unit 2 05000301 l l FACILITY NAME DOCKET NUMBER 02 04 l 97 l 97 - S01 - 00 03 04 97 05000 OPERATING l THIS REPORT IS SUSMITTED PURSUANT TO THE REQUIREMENTS OF 10 CFR S: (Check one or more) (11)
MODE (t) 20 220 % 20.2203(aH2)M 50.73<ai(2Ho 50.73(aH2)(viii)
Nl POWER l 20.2203(aH1) 20.2203(a)(3Hi) 50.73(aH2Hii) 50.73(aH2)(x)
LEVEL (10) 0 20.2203(aH2Hij 20.2203t H3Hii) 50.73(aH2)(ia) X 73 71 20.2203(aH2)(ii) 20.2203(a)(4) 50.73(eH2Hivl OTHER 20.2203(s}{2)(in) 50.36(c)(1) 50.73(aH2)(v) Specify in Abstract below 20.2203(aH2H6v) 50.36(c)(2) 50.73(aH2)(vli) or wt NRC Form 3e8A LICENSEE CONTACT FOR THIS LER (12)
NAME TELEPHONE NUMBER (Include Area Code)
Joan E. McCullum, Security Supervisor (414) 755-6221 COMPLETE ONE LINE FOR EACH COMPONENT FAILURE DESCRISED IN THis REPORT (13)
CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE CAUSE SYSTEM COMPONENT MANUFACTURER REPORTABLE TO NPRDS TO NPRDS SUPPL NTAL REPORT EXPECTED (14) XPECTED YEAR YES SUSMISSION (If yes complete EXPECTED SUBMISSION DATE). X NO DATE (15)
ABSTRACT (Limit to 1400 spaces, i.e., approxirr.ately 15 single-spaced typewritten lines) (16) on February 4, 1997, during the early to mid-morning, PBNP and the surrounding area experienced severe weather conditions (high winds and snow). This resulted in numerous alarms being received on intrusion detection devices from both the strong winds and the weight of the snow.
This requirad posting of additior.a1 personnel. At 1329 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.056845e-4 months <br />, the CAS operator initiated compensatory measures for loss of multiple e-fields and microwave zones. At 1342 it was discovered that compensatory measures were not implemented for one alarmed microwave zone (M10) for approximately 16 minutes; 6 mimites longer than the required 10-minutes allowed for establishment of compensatory measures. Compensatory measures were established at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />. The root cause of this event was personnel failure to follow compensatory measures procedures and checklists and to adhere to communications standards. Contributing factors were weak management oversight of CAS/SAS activities in that adherence to established procedures, use of checklists and standards was not being enforced; corrective actions from previous events were not fully completed; and long-term security hardware issues have not been fully resolved.
NRC FORM 3G6 (4-95)
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NRC FERM 35SA U.S. NUCLEAR REGULATORY C&MMISSION le 95)'
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LICENSEE EVENT REPORT (LER)
TEXT CONTINUATION FACILITY NAME til DOCKET NUMBER (2) LER NUMBER (6) PAGE 13)
YEAR SEQUENTIAL REVISION Point Beach Nuclear Plant, Unit 1 05000266 NUMBER NUMBER 2 OF 3 97 -
S01 00 TEXT ttf more space is required, use additenalcopies of NRC Form 366A) (17)
! Event Start: February 4, 1997, at 1329 htars i
Event End February 4, 1997, at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br /> Location: Protected Area Operations: Unit 1 at 90% power Unit 2 in refueling shutdown with reactor defueled l Security Force: Contract i
Number & Type of Personnel Involved: 2 contractor personnel i Event
Description:
! On February 4, 1997, severe weather conditions were being experienced
- during the early and mid-morning hours. Posting of dedicated observers was performed on a number of occasions throughout the morning. At i 1329 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.056845e-4 months <br />, the CAS operator initiater
- the compensatory procedure for
, loss of multiple intrusion detection zones. It was discovered at 1342-hours that compensatory measures for microwave zones M9, M10 and M22 had not been implemented. Of these three microwave zones, only M10 was in an alarmed status.
l i Immediate Corrective Action: Upon identification at 1342 hours0.0155 days <br />0.373 hours <br />0.00222 weeks <br />5.10631e-4 months <br /> that the microwave M10 had not been compensated, compensatory measures were
.. established at 1345 hours0.0156 days <br />0.374 hours <br />0.00222 weeks <br />5.117725e-4 months <br />. Approximately 16 minutes had elapsed from initiation of compensatory measures to full implementation.
Cause:
j.
- 1. The CAS and SAS operators failed to implement procedural guidance and associated checklists for the implementation of severe weather
- - compensatory measures.
- 2. The CAS and SAS operators failed to adhere to accepted communications standards including use of the intercom, public address systems and i repeatbacks.
- 3. Management oversight of CAS and SAS activities was inadequate.
- 4. Corrective actions identified during previous events have not been fully implemented.
- 5. A contributing factor was the condition of the security hardware systems. There are a number of upgrades that have been planned, but they have not yet been implemented.
3 NRC FORM 366A (4 95) l 1
NHC FORtf 3%43 U.S. NUCLEAR REOULATORY COMMlSC40N (4WJ)
- iLICENSEE EVENT REPORT (LER)
TEXT CONTINUATION l FACILITY NAME til DOCKET NUMBER (2) LER NUM8ER (8'i PAGE 13)
YEAR SEQUENTIAL REVISION l Point Beach Nuclear Plant, Unit 1 05000266 NUMMR NUMMR 3OF3 l 97 -
S01 00 TEX 1 lit more space is required, use additional copies of NRC Fo,m 366A) (11)
Corrective Action:
- 1. Senior security supervision has implemented additional management ,
oversight of CAS and SAS operations by senior contractor supervision. l
- 2. An administrative po'sition is being added to the security force to relieve senior security supervision of tasks that inhibit their ability to provide an appropriate level of management oversight for security operations.
- 3. The security supervisor met with all members of the security force on February 12, 1997, and February 19, 1997. During these meetings, the security supervisor informed the security force of the licensee's .
performance standards and expectations, as well as identifying the l methods to be used for monitoring and enforcement of these standards and expectations. l
- 4. The SAS operator involved in the event received additional training in areas of identified performance deficiencies prior to being rescheduled to perform CAS or SAS duties. l
- 5. The CAS operator was relieved of CAS/SAS duties.
- 6. A report delineating the deficiencies and current status of the physical condition of the security hardware system was prepared and presented to senior site management on February 14, 1997. An evaluation of this report on March 3, 1997, by licensee senior engineering management representatives determined there were three areas of the physical security system which required an in-depth engineering evaluation to be performed. These were the security computer, the closed circuit television network, and the perimeter intrusion detection system. By September 1, 1997, engineering evaluations will be completed, decisions will be made, and project plans will be formalized, as appropriate, to address these three areas.
Notifications:
The NRC resident inspector was notified of this event at 1422 hours0.0165 days <br />0.395 hours <br />0.00235 weeks <br />5.41071e-4 months <br /> on February 4, 1997. The event was reported via ENS to the NRC Operations Center at 1413 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.376465e-4 months <br /> on February 4, 1996.
Similar Occurrences:
LER 266/94-S01-00 LER 266/95-S03-00 LER 266/95-SO4-00 LER 266/96-S01-00 NRC FORM 366A (4-95)