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| {{#Wiki_filter:UNITED STATESNUCLEAR REGULATORY COMMISSIONOFFICE OF NUCLEAR REACTOR REGULATION-WASHINGTON, DC 20555-0001December 27, 1996NRC INFORMATION NOTICE NO. 96-71: LICENSEE RESPONSE TO INDICATIONS OFTAMPERING, VANDALISM, OR MALICIOUSMISCHIEF | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY |
| | |
| | COMMISSION |
| | |
| | OFFICE OF NUCLEAR REACTOR REGULATION- |
| | WASHINGTON, DC 20555-0001 December 27, 1996 NRC INFORMATION |
| | |
| | NOTICE NO. 96-71: LICENSEE RESPONSE TO INDICATIONS |
| | |
| | OF TAMPERING, VANDALISM, OR MALICIOUS MISCHIEF |
|
| |
|
| ==Addressees== | | ==Addressees== |
| All holders of operating licenses or construction permits for nuclear power reactors. | | All holders of operating |
| | |
| | licenses or construction |
| | |
| | permits for nuclear power reactors. |
|
| |
|
| ==Purpose== | | ==Purpose== |
| This information notice is being issued to alert licensees to the benefits of planning aresponse to indications of tampering, vandalism, or malicious mischief. It is expected thatrecipients will review the information for applicability to their facilities and consider actions,as appropriate. However, suggestions contained in this information notice are not NRCrequirements; therefore, no specific action or written response is required. | | This information |
| | |
| | notice is being issued to alert licensees |
| | |
| | to the benefits of planning a response to indications |
| | |
| | of tampering, vandalism, or malicious |
| | |
| | mischief. |
| | |
| | It is expected that recipients |
| | |
| | will review the information |
| | |
| | for applicability |
| | |
| | to their facilities |
| | |
| | and consider actions, as appropriate. |
| | |
| | However, suggestions |
| | |
| | contained |
| | |
| | in this information |
| | |
| | notice are not NRC requirements; |
| | therefore, no specific action or written response is required.Description |
| | |
| | of Circumstances |
| | |
| | Recent events at operating |
| | |
| | reactors indicate that some licensee personnel |
| | |
| | may not recognize |
| | |
| | the potential |
| | |
| | significance |
| | |
| | of early indications |
| | |
| | of potential |
| | |
| | tampering, vandalism, or malicious |
| | |
| | mischief. |
| | |
| | As a result, licensee response may be untimely and of limited scope and depth. Failure to promptly question, resolve the significance |
| | |
| | and implement |
| | |
| | an appropriate |
| | |
| | strategy to mitigate the consequence |
| | |
| | of a potential |
| | |
| | tampering, vandalism, or malicious |
| | |
| | mischief situation, could leave the plant in a vulnerable |
| | |
| | state for a significant |
| | |
| | period of time. Lack of detailed planning, procedures, and training frequently |
| | |
| | plays a role in the quality of response to these events. Brief accounts of two events illustrate |
| | |
| | the issue: Improperly |
| | |
| | Positioned |
| | |
| | Valve at Beaver Valley During the conduct of a quarterly |
| | |
| | surveillance |
| | |
| | on Friday, July 14, 1995, to verify the position of certain safety-related |
| | |
| | locked valves; the licensee determined |
| | |
| | that the service water cross-connect |
| | |
| | valve at the discharge |
| | |
| | of the recirculation |
| | |
| | spray heat exchanger |
| | |
| | was in the incorrect |
| | |
| | position (shut in lieu of open), that the chain used to secure the valve in the proper position had been cut, and that the lock appeared to have been placed back on the chain in a manner that made it difficult |
| | |
| | to detect the condition. |
| | |
| | The licensee's |
| | |
| | staff initially |
| | |
| | assumed the valve had been inadvertently |
| | |
| | mispositioned |
| | |
| | during earlier operational |
| | |
| | evolutions, but subsequent |
| | |
| | interviews |
| | |
| | and analysis were unable to confirm this assumption. |
| | |
| | 2 I1.1 r?Pfs ITE 0i-1tttt S%-071Z 9017-21 ai 41 -A,- _ -[,A_ ,a 0 S QAI 912flfA1--v----60do |
| | |
| | 'I 11 I T2D4t ICG |
| | |
| | IN 96-71 December 27, 1996 Licensee management |
| | |
| | first learned of the event on Tuesday, July 18, 1995. Consequ-ently, licensee management |
| | |
| | was not able to oversee the licensee evaluation |
| | |
| | of the event until considerable |
| | |
| | time had elapsed. The licensee's |
| | |
| | determination |
| | |
| | that potential |
| | |
| | tampering could not be ruled out was not made until six days after the incorrect |
| | |
| | valve position was identified. |
| | |
| | Thorough valve lineup checks and locked valve surveillances |
| | |
| | were not completed |
| | |
| | for both Beaver Valley units until after the plant staff made an emergency notification |
| | |
| | system (ENS) call on Thursday evening, July 20, 1995. The similarity |
| | |
| | of this event to an event in the early 1 980s heightened |
| | |
| | the concern of both licensee and NRC personnel |
| | |
| | who knew of the previous events.Misadjusted |
| | |
| | Valves and Disabled Locks at St. Lucie In May 1996, St. Lucie personnel |
| | |
| | identified |
| | |
| | two pressure-relief |
| | |
| | valves which, when tested, were found to have pressure setpoints |
| | |
| | 55 percent and 9 percent above their design values.These valves also had broken wire seals. The root cause could not be determined. |
| | |
| | Although tampering |
| | |
| | could not be ruled out, it was concluded |
| | |
| | that the more likely cause for the misadjusted |
| | |
| | valves was poor maintenance. |
| | |
| | Licensee management |
| | |
| | decided to alert the Security force; however, site Security was not notified. |
| | |
| | The failure to follow through on alerting site Security precluded |
| | |
| | coordinated |
| | |
| | actions of Operations |
| | |
| | and Security staffs to enhance awareness |
| | |
| | to other possible tampering |
| | |
| | events.On July 26, 1996, St. Lucie staff identified |
| | |
| | nine padlocks and two door locks in vital areas that were intentionally |
| | |
| | damaged to inhibit opening the locks. These locks controlled |
| | |
| | personnel |
| | |
| | access to various pieces of plant equipment. |
| | |
| | The licensee did not identify keylock switches as needing to be checked; consequently, these switches were not checked until August 1996. Although the tampering |
| | |
| | of components |
| | |
| | within a vital area indicated |
| | |
| | the need to be alert to additional |
| | |
| | tampering, other than alerting Security, the licensee failed to consider additional |
| | |
| | measures to detect tampering. |
| | |
| | On August 14, 1996, St. Lucie staff identified |
| | |
| | three additional |
| | |
| | examples of tampering |
| | |
| | in vital areas that inhibited the opening of locks associated |
| | |
| | with safety-related |
| | |
| | equipment. |
| | |
| | Discussion |
| | |
| | The following |
| | |
| | factors may have contributed |
| | |
| | to these events: (1) The licensees' |
| | contingency |
| | |
| | plans required by 10 CFR 73.55(h)(1) |
| | and the implementing |
| | |
| | procedures |
| | |
| | required by Appendix C to Part 73 did not adequately |
| | |
| | address tampering, vandalism, and malicious |
| | |
| | mischief. |
| | |
| | ===Other licensee procedures=== |
| | touched some aspects of these situations; |
| | however, no plan or process was used to evaluate the potential |
| | |
| | malevolent |
| | |
| | event and determine |
| | |
| | its importance. |
| | |
| | Factors such as safety significance, overtness, intent, sophistication |
| | |
| | of method, and the history of similar incidents |
| | |
| | were not considered. |
| | |
| | Information |
| | |
| | Notice 83-27, "Operational |
| | |
| | Response to Events Concerning |
| | |
| | Deliberate |
| | |
| | Acts Directed Against Plant Equipment," described |
| | |
| | events in which licensees |
| | |
| | were not prepared to assess the situation |
| | |
| | and take necessary |
| | |
| | steps to ensure the operability |
| | |
| | of systems important |
| | |
| | to safety or make decisions |
| | |
| | concerning |
| | |
| | continued |
| | |
| | operation. |
| | |
| | The information |
| | |
| | notice indicated that guidelines |
| | |
| | or procedures |
| | |
| | prepared by the licensee outlining |
| | |
| | a process of |
| | |
| | i IN 96-71 December 27, 1996 following |
| | |
| | up on both deliberate |
| | |
| | and inadvertent |
| | |
| | acts with respect to plant operation should be available. |
| | |
| | (2) The licensees' |
| | actions were limited in scope and depth, at least initially, in pursuing the events.(3) The licensees' |
| | Operations |
| | |
| | staff were not sensitive |
| | |
| | to abnormalities |
| | |
| | identified |
| | |
| | earlier and apparently |
| | |
| | assumed no malice. Since the Operations |
| | |
| | staff may be the first to encounter |
| | |
| | signs of tampering, vandalism, or malicious |
| | |
| | mischief during its tours and surveillance |
| | |
| | activities, sensitivity |
| | |
| | to precursors |
| | |
| | plays a key role in timely response to events of this nature. Therefore, licensees |
| | |
| | may wish to periodically |
| | |
| | refresh their Operations |
| | |
| | staff's sensitivity |
| | |
| | to and awareness |
| | |
| | of the evaluation |
| | |
| | process to ensure effective |
| | |
| | response to these acts.(4) The licensee's |
| | |
| | Security staff was not told about these problems until well into the sequence of events at St. Lucie. Security's |
| | |
| | ability to identify the perpetrators |
| | |
| | and institute |
| | |
| | other protective |
| | |
| | measures diminishes |
| | |
| | severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to the NRC Operations |
| | |
| | Center within one hour of discovery. |
| | |
| | This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | project manager.Thomas T. Martin, Director Division of Reactor Program Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: |
| | Loren Bush, NRR (301) 415-2944 E-mail: llb(nrc.gov |
| | |
| | David Skeen, NRR (301) 415-1174 E-mail: dls@nrc.gov |
| | |
| | Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices AM -chrobL~A |
| | |
| | 4?f-r S |
| | |
| | W-Attachment |
| | |
| | IN 96-71 December 27, 1996 LIST OF RECENTLY ISSUED NRC INFORMATION |
| | |
| | NOTICES Information |
| | |
| | Date of Notice No. Subject Issuance Issued to 96-70 96-69 96-68 96-67 Year 2000 Effect on Computer System Software Operator Actions Affecting Reactivity |
| | |
| | Incorrect |
| | |
| | Effective |
| | |
| | Diaphragm Area Values in Vendor Manual Result in Potential |
| | |
| | Failure of Pneumatic |
| | |
| | Diaphragm Actuators Vulnerability |
| | |
| | of Emergency Diesel Generators |
| | |
| | to Fuel Oil/Lubricating |
| | |
| | Oil Incom-patibility |
| | |
| | ===Recent Misadministrations=== |
| | Caused by Incorrect |
| | |
| | Cali-brations of Strontium-90 |
| | |
| | ===Eye Applicators=== |
| | Undetected |
| | |
| | ===Accumulation=== |
| | of Gas in Reactor Coolant System and Inaccurate |
| | |
| | Reactor Water Level Indication |
| | |
| | During Shutdown 12/24/96 12/20/96 12/19/96 12/19/96 12/13/96 12/11/96 All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | licensees, certificate |
| | |
| | holders, and registrants |
| | |
| | All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All U.S. Nuclear Regulatory |
| | |
| | Commission |
| | |
| | Medical Use Licensees authorized |
| | |
| | to use strontium-90 (Sr-90)eye applicators |
| | |
| | All holders of OLs or CPs for nuclear power reactors 96-66 96-65 OL = Operating |
| | |
| | License CP = Construction |
| | |
| | Permit |
| | |
| | IN 96-71 December 27, 1996 following |
| | |
| | up on both deliberate |
| | |
| | and inadvertent |
| | |
| | acts with respect to plant operation should be available. |
| | |
| | t (2) The licensees' |
| | actions were limited in scope and depth, at least initially, in pursuing the events.(3) The licensees' |
| | Operations |
| | |
| | staff were not sensitive |
| | |
| | to abnormalities |
| | |
| | identified |
| | |
| | earlier and apparently |
| | |
| | assumed no malice. Since the Operations |
| | |
| | staff may be the first to encounter |
| | |
| | signs of tampering, vandalism, or malicious |
| | |
| | mischief during its tours and surveillance |
| | |
| | activities, sensitivity |
| | |
| | to precursors |
| | |
| | plays a key role in timely response to events of this nature. Therefore, licensees |
| | |
| | may wish to periodically |
| | |
| | refresh their Operations |
| | |
| | staff's sensitivity |
| | |
| | to and awareness |
| | |
| | of the evaluation |
| | |
| | process to ensure effective |
| | |
| | response to these acts.(4) The licensee's |
| | |
| | Security staff was not told about these problems until well into the sequence of events at St. Lucie. Security's |
| | |
| | ability to identify the perpetrator(s) |
| | and institute |
| | |
| | other protective |
| | |
| | measures diminishes |
| | |
| | severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to the NRC Operations |
| | |
| | Center within one hour of discovery. |
| | |
| | This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | project manager.original signed by D.B. Matthews Thomas T. Martin, Director Division of Reactor Program Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: |
| | Loren Bush, NRR David Skeen, NRR (301) 415-2944 (301) 415-1174 E-mail: llb@nrc.gov |
| | |
| | E-mail: dls@nrc.gov |
| | |
| | Tech Editor has reviewed and concurred |
| | |
| | on 9/27/96 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices DOCUMENT NAME: 96-71.IN To receive a copy of this document. |
| | |
| | hIdlcate I the box: 'C' -Copy w/o attachmentlenclosure |
| | |
| | 'E' -Copy wfattachmentlenclosure |
| | |
| | 'N' -No copy OFFICE TECH CONTS I C/PECB:DRPM |
| | |
| | I D/DRP I I NAME LBush* AChaffee* |
| | TMart DSkeen* L ' I DATE 10/31/96 11/01/96 12 OFFICIAL RECORD COPY |
| | |
| | * IN 96-December , 1996 following |
| | |
| | up on both deliberate |
| | |
| | and inadvertent |
| | |
| | acts with respect to plant operation should be available. |
| | |
| | (2) The licensees' |
| | actions were limited in scope and depth, at least initially, in pursuing the events.(3) The licensees' |
| | Operations |
| | |
| | staff were not sensitive |
| | |
| | to abnormalities |
| | |
| | identified |
| | |
| | earlier and apparently |
| | |
| | assumed no malice. Since the Operations |
| | |
| | staff may be the first to encounter |
| | |
| | signs of tampering, vandalism, or malicious |
| | |
| | mischief during its tours and surveillance |
| | |
| | activities, sensitivity |
| | |
| | to precursors |
| | |
| | plays a key role in timely response to events of this nature. Therefore, licensees |
| | |
| | may wish to periodically |
| | |
| | refresh their Operations |
| | |
| | staff's sensitivity |
| | |
| | to and awareness |
| | |
| | of the evaluation |
| | |
| | process to ensure effective |
| | |
| | response to these acts.(4) The licensee's |
| | |
| | Security staff was not told about these problems until well into the sequence of events at St. Lucie. Security's |
| | |
| | ability to identify the perpetrators |
| | |
| | and institute |
| | |
| | other protective |
| | |
| | measures diminishes |
| | |
| | severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to the NRC Operations |
| | |
| | Center within one hour of discovery. |
| | |
| | This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation |
| | |
| | project manager.Thomas T. Martin, Director Division of Reactor Program Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | contacts: |
| | Loren Bush, NRR David Skeen, NRR (301) 415-2944 (301) 415-1174 E-mail: llb@nrc.gov |
| | |
| | E-mail: dls@nrc.gov |
| | |
| | Tech Editor has reviewed and concurred |
| | |
| | on 9/27/96 Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices DOCUMENT NAME: G:\DLS\96-XXX |
| | |
| | To receive a copy of this document. |
| | |
| | indicate In the box: 'C -Copy w/o attachment/enclosure |
| | |
| | WE -Copy wlettachmenlenClosure |
| | |
| | N -No copy OFFICE TECH CONTS C/PECB:DRPM |
| | |
| | l D/DRPJ- I NAME LBush* AChaffee* |
| | Toard n DSkeen1 A a e haW DATE 10/31/96 11/01/96 12/zo /96 Al. -r ... -.A In-n n/I U11l.IWAL |
| | |
| | KLLUKU HUrY 4 t |
| | |
| | * IN 96-XX November xx, 1996 available. |
| | |
| | Furthermore, the licensee contingency |
| | |
| | plans requiredby |
| | |
| | 10 CFR 73.55(h)(1) |
| | and the implementing |
| | |
| | procedures |
| | |
| | required by Appendix C to Part 73 did not adequately |
| | |
| | address tampering, vandalism, and malicious |
| | |
| | mischief.(2) The licensee actions were limited in scope and depth, at least initially, in pursuing the events.(3) The Operations |
| | |
| | staff was not sensitive |
| | |
| | to abnormalities |
| | |
| | identified |
| | |
| | earlier and apparently |
| | |
| | assumed no malice. Since the Operations |
| | |
| | staff may be the first to encounter |
| | |
| | signs of tampering, vandalism, or malicious |
| | |
| | mischief during its tours and surveillance |
| | |
| | activities, sensitivity |
| | |
| | to precursors |
| | |
| | plays a key role in timely response to events of this nature. Therefore, licensees |
| | |
| | may wish to periodically |
| | |
| | refresh their Operations |
| | |
| | staffs sensitivity |
| | |
| | to and awareness |
| | |
| | of the evaluation |
| | |
| | process to ensure effective |
| | |
| | response to these acts.(4) The licensee's |
| | |
| | Security staff was not told about these problems until well into the sequence of events. Security's |
| | |
| | ability to identify the perpetrator(s) |
| | and institute |
| | |
| | other protective |
| | |
| | measures diminishes |
| | |
| | severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to the NRC Operations |
| | |
| | Center within one hour of discovery. |
| | |
| | This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Thomas T. Martin, Director Division of Reactor Program Management |
| | |
| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
| | |
| | Contact: Loren Bush, NRR (301) 415-2944 E-mail: llb@nrc.gov |
| | |
| | David Skeen, NRR (301) 415-1174 E-mail: dls@nrc.gov |
| | |
| | Attachment: |
| | List of Recently Issued NRC Information |
| | |
| | Notices DOCUMENT NAME: G:MDLS\IN96-XX.TPR |
| | |
| | To receive a copy of this document. |
| | |
| | hIdicate hI the box: 'C' -Copy w/o attachmenVenclosure |
| | |
| | 'E' -Copy wlattachmentlenclosure |
| | |
| | 'N' -No copy OFFICE PECB:DRPM |
| | |
| | IC PSGB:DRPM |
| | |
| | C/PSGB:DRPM |
| | |
| | C/PECB:DRPM , D/DRPM NAME DSkeenZot-C |
| | |
| | LBush* LCunninghamnM |
| | |
| | AChaffeeCifv-' |
| | TMartin DATE 10/3//96 10/xv/96 10/ /96 1l// /96 3y9 10/ /96-i OFFICIAL RECORD COPY*- pervias 44 1i I |
| | |
| | K.IN 96-XX October xx, 1996 available. |
| | |
| | Furthermore, the licensee contingency |
| | |
| | plans requiredby |
| | |
| | 10 CFR 73.55(h)(1) |
| | and the implementing |
| | |
| | procedures |
| | |
| | required by Appendix C to Part 73 did not adequately |
| | |
| | address tampering, vandalism, and malicious |
| | |
| | mischief.(2) The licensee actions were limited in scope and depth, at least initially, in pursuing the events.(3) The Operations |
| | |
| | staff was not sensitive |
| | |
| | to abnormalities |
| | |
| | identified |
| | |
| | earlier and apparently |
| | |
| | assumed no malice. Since the Operations |
| | |
| | staff may be the first to encounter |
| | |
| | signs of tampering, vandalism, or malicious |
| | |
| | mischief during its tours and surveillance |
| | |
| | activities, sensitivity |
| | |
| | to precursors |
| | |
| | plays a key role in timely response to events of this nature. Therefore, licensees |
| | |
| | may wish to periodically |
| | |
| | refresh their Operations |
| | |
| | staffs sensitivity |
| | |
| | to and awareness |
| | |
| | of the evaluation |
| | |
| | process to ensure effective |
| | |
| | response to these acts.(4) The licensee's |
| | |
| | Security staff was not told about these problems until well into the sequence of events. Security's |
| | |
| | ability to identify the perpetrator(s) |
| | and institute |
| | |
| | other protective |
| | |
| | measures diminishes |
| | |
| | severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to the NRC Operations |
| | |
| | Center within one hour of discovery. |
| | |
| | This information |
| | |
| | notice requires no specific action or written response. |
| | |
| | If you have any questions |
| | |
| | about the information |
| | |
| | in this notice, please contact one of the technical |
| | |
| | contacts listed below or the appropriate |
| | |
| | Office of Nuclear Reactor Regulation (NRR) project manager.Thomas T. Martin, Director Division of Reactor Program Management |
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| | ===Office of Nuclear Reactor Regulation=== |
| | Technical |
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| | Contact: Loren Bush, NRR (301) 415-2944 E-mail: llbenrc.gov |
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| ==Description of Circumstances==
| | David Skeen, NRR (301) 415-1174 E-mail: dIs@nrc.gov |
| Recent events at operating reactors indicate that some licensee personnel may notrecognize the potential significance of early indications of potential tampering, vandalism,or malicious mischief. As a result, licensee response may be untimely and of limited scopeand depth. Failure to promptly question, resolve the significance and implement anappropriate strategy to mitigate the consequence of a potential tampering, vandalism, ormalicious mischief situation, could leave the plant in a vulnerable state for a significantperiod of time. Lack of detailed planning, procedures, and training frequently plays a rolein the quality of response to these events. Brief accounts of two events illustrate theissue:Improperly Positioned Valve at Beaver ValleyDuring the conduct of a quarterly surveillance on Friday, July 14, 1995, to verify theposition of certain safety-related locked valves; the licensee determined that the servicewater cross-connect valve at the discharge of the recirculation spray heat exchanger wasin the incorrect position (shut in lieu of open), that the chain used to secure the valve inthe proper position had been cut, and that the lock appeared to have been placed back onthe chain in a manner that made it difficult to detect the condition. The licensee's staffinitially assumed the valve had been inadvertently mispositioned during earlier operationalevolutions, but subsequent interviews and analysis were unable to confirm thisassumption. 2I1.1 r?Pfs ITE 0i-1tttt S%-071Z 9017-21 ai41 -A,- _ -[,A_ ,a 0 SQAI 912flfA1--v----60do 'I 11 IT2D4t ICG
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| IN 96-71December 27, 1996 Licensee management first learned of the event on Tuesday, July 18, 1995. Consequ-ently, licensee management was not able to oversee the licensee evaluation of the eventuntil considerable time had elapsed. The licensee's determination that potential tamperingcould not be ruled out was not made until six days after the incorrect valve positionwas identified. Thorough valve lineup checks and locked valve surveillances were notcompleted for both Beaver Valley units until after the plant staff made an emergencynotification system (ENS) call on Thursday evening, July 20, 1995. The similarity of thisevent to an event in the early 1 980s heightened the concern of both licensee and NRCpersonnel who knew of the previous events.Misadjusted Valves and Disabled Locks at St. LucieIn May 1996, St. Lucie personnel identified two pressure-relief valves which, when tested,were found to have pressure setpoints 55 percent and 9 percent above their design values.These valves also had broken wire seals. The root cause could not be determined.Although tampering could not be ruled out, it was concluded that the more likely cause forthe misadjusted valves was poor maintenance. Licensee management decided to alert theSecurity force; however, site Security was not notified. The failure to follow through onalerting site Security precluded coordinated actions of Operations and Security staffs toenhance awareness to other possible tampering events.On July 26, 1996, St. Lucie staff identified nine padlocks and two door locks in vital areasthat were intentionally damaged to inhibit opening the locks. These locks controlledpersonnel access to various pieces of plant equipment. The licensee did not identifykeylock switches as needing to be checked; consequently, these switches were notchecked until August 1996. Although the tampering of components within a vital areaindicated the need to be alert to additional tampering, other than alerting Security, thelicensee failed to consider additional measures to detect tampering. On August 14, 1996,St. Lucie staff identified three additional examples of tampering in vital areas that inhibitedthe opening of locks associated with safety-related equipment.DiscussionThe following factors may have contributed to these events:(1) The licensees' contingency plans required by 10 CFR 73.55(h)(1) and theimplementing procedures required by Appendix C to Part 73 did not adequatelyaddress tampering, vandalism, and malicious mischief. Other licensee procedurestouched some aspects of these situations; however, no plan or process was used toevaluate the potential malevolent event and determine its importance. Factors suchas safety significance, overtness, intent, sophistication of method, and the historyof similar incidents were not considered. Information Notice 83-27, "OperationalResponse to Events Concerning Deliberate Acts Directed Against Plant Equipment,"described events in which licensees were not prepared to assess the situation andtake necessary steps to ensure the operability of systems important to safety ormake decisions concerning continued operation. The information notice indicatedthat guidelines or procedures prepared by the licensee outlining a process of
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| iIN 96-71December 27, 1996 following up on both deliberate and inadvertent acts with respect to plant operationshould be available.(2) The licensees' actions were limited in scope and depth, at least initially, in pursuingthe events.(3) The licensees' Operations staff were not sensitive to abnormalities identified earlierand apparently assumed no malice. Since the Operations staff may be the first toencounter signs of tampering, vandalism, or malicious mischief during its tours andsurveillance activities, sensitivity to precursors plays a key role in timely response toevents of this nature. Therefore, licensees may wish to periodically refresh theirOperations staff's sensitivity to and awareness of the evaluation process to ensureeffective response to these acts.(4) The licensee's Security staff was not told about these problems until well into thesequence of events at St. Lucie. Security's ability to identify the perpetrators andinstitute other protective measures diminishes severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported tothe NRC Operations Center within one hour of discovery.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation project manager.Thomas T. Martin, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Loren Bush, NRR(301) 415-2944E-mail: llb(nrc.govDavid Skeen, NRR(301) 415-1174E-mail: dls@nrc.govAttachment: List of Recently Issued NRC Information NoticesAM -chrobL~A 4?f-r S
| | Notices DOCUMENT NAME: G:IDLSIN96-XX.TPR |
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| W-AttachmentIN 96-71December 27, 1996 LIST OF RECENTLY ISSUEDNRC INFORMATION NOTICESInformation Date ofNotice No. Subject Issuance Issued to96-7096-6996-6896-67Year 2000 Effect on ComputerSystem SoftwareOperator Actions AffectingReactivityIncorrect Effective DiaphragmArea Values in Vendor ManualResult in Potential Failureof Pneumatic DiaphragmActuatorsVulnerability of EmergencyDiesel Generators to FuelOil/Lubricating Oil Incom-patibilityRecent MisadministrationsCaused by Incorrect Cali-brations of Strontium-90Eye ApplicatorsUndetected Accumulationof Gas in Reactor CoolantSystem and InaccurateReactor Water LevelIndication During Shutdown12/24/9612/20/9612/19/9612/19/9612/13/9612/11/96All U.S. NuclearRegulatory Commissionlicensees, certificateholders, and registrantsAll holders of OLsor CPs for nuclearpower reactorsAll holders of OLsor CPs for nuclearpower reactorsAll holders of OLsor CPs for nuclearpower reactorsAll U.S. NuclearRegulatory CommissionMedical Use Licenseesauthorized to usestrontium-90 (Sr-90)eye applicatorsAll holders of OLsor CPs for nuclearpower reactors96-6696-65OL = Operating LicenseCP = Construction Permit
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| IN 96-71December 27, 1996 following up on both deliberate and inadvertent acts with respect to plant operationshould be available. t(2) The licensees' actions were limited in scope and depth, at least initially, in pursuingthe events.(3) The licensees' Operations staff were not sensitive to abnormalities identified earlierand apparently assumed no malice. Since the Operations staff may be the first toencounter signs of tampering, vandalism, or malicious mischief during its tours andsurveillance activities, sensitivity to precursors plays a key role in timely response toevents of this nature. Therefore, licensees may wish to periodically refresh theirOperations staff's sensitivity to and awareness of the evaluation process to ensureeffective response to these acts.(4) The licensee's Security staff was not told about these problems until well into thesequence of events at St. Lucie. Security's ability to identify the perpetrator(s) andinstitute other protective measures diminishes severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported tothe NRC Operations Center within one hour of discovery.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation project manager.original signed by D.B. MatthewsThomas T. Martin, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Loren Bush, NRR David Skeen, NRR(301) 415-2944 (301) 415-1174E-mail: llb@nrc.gov E-mail: dls@nrc.govTech Editor has reviewed and concurred on 9/27/96Attachment: List of Recently Issued NRC Information NoticesDOCUMENT NAME: 96-71.INTo receive a copy of this document. hIdlcate I the box: 'C' -Copy w/oattachmentlenclosure 'E' -Copy wfattachmentlenclosure 'N' -No copyOFFICE TECH CONTS I C/PECB:DRPM I D/DRP I INAME LBush* AChaffee* TMartDSkeen* L ' IDATE 10/31/96 11/01/96 12OFFICIAL RECORD COPY
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| * IN 96-December , 1996 following up on both deliberate and inadvertent acts with respect to plant operationshould be available.(2) The licensees' actions were limited in scope and depth, at least initially, in pursuingthe events.(3) The licensees' Operations staff were not sensitive to abnormalities identified earlierand apparently assumed no malice. Since the Operations staff may be the first toencounter signs of tampering, vandalism, or malicious mischief during its tours andsurveillance activities, sensitivity to precursors plays a key role in timely response toevents of this nature. Therefore, licensees may wish to periodically refresh theirOperations staff's sensitivity to and awareness of the evaluation process to ensureeffective response to these acts.(4) The licensee's Security staff was not told about these problems until well into thesequence of events at St. Lucie. Security's ability to identify the perpetrators andinstitute other protective measures diminishes severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported tothe NRC Operations Center within one hour of discovery.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation project manager.Thomas T. Martin, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor RegulationTechnical contacts: Loren Bush, NRR David Skeen, NRR(301) 415-2944 (301) 415-1174E-mail: llb@nrc.gov E-mail: dls@nrc.govTech Editor has reviewed and concurred on 9/27/96Attachment: List of Recently Issued NRC Information NoticesDOCUMENT NAME: G:\DLS\96-XXXTo receive a copy of this document. indicate In the box: 'C -Copy w/oattachment/enclosure WE -Copy wlettachmenlenClosure N -No copyOFFICE TECH CONTS C/PECB:DRPM l D/DRPJ- INAME LBush* AChaffee* Toard nDSkeen1 A a e haWDATE 10/31/96 11/01/96 12/zo /96Al. -r ... -.A In-n n/IU11l.IWAL KLLUKU HUrY 4 t
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| * IN 96-XXNovember xx, 1996 available. Furthermore, the licensee contingency plans requiredby 10 CFR73.55(h)(1) and the implementing procedures required by Appendix C to Part 73 didnot adequately address tampering, vandalism, and malicious mischief.(2) The licensee actions were limited in scope and depth, at least initially, in pursuing theevents.(3) The Operations staff was not sensitive to abnormalities identified earlier andapparently assumed no malice. Since the Operations staff may be the first toencounter signs of tampering, vandalism, or malicious mischief during its tours andsurveillance activities, sensitivity to precursors plays a key role in timely response toevents of this nature. Therefore, licensees may wish to periodically refresh theirOperations staffs sensitivity to and awareness of the evaluation process to ensureeffective response to these acts.(4) The licensee's Security staff was not told about these problems until well into thesequence of events. Security's ability to identify the perpetrator(s) and institute otherprotective measures diminishes severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to theNRC Operations Center within one hour of discovery.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.Thomas T. Martin, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor Regulation
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| Loren Bush, NRR(301) 415-2944E-mail: llb@nrc.govDavid Skeen, NRR(301) 415-1174E-mail: dls@nrc.govAttachment: List of Recently Issued NRC Information NoticesDOCUMENT NAME: G:MDLS\IN96-XX.TPRTo receive a copy of this document. hIdicate hI the box: 'C' -Copy w/oattachmenVenclosure 'E' -Copy wlattachmentlenclosure 'N' -No copyOFFICE PECB:DRPM IC PSGB:DRPM C/PSGB:DRPM C/PECB:DRPM , D/DRPMNAME DSkeenZot-C LBush* LCunninghamnM AChaffeeCifv-' TMartinDATE 10/3//96 10/xv/96 10/ /96 1l// /96 3y9 10/ /96-i OFFICIAL RECORD COPY*- pervias 44 1i I
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| K.IN 96-XXOctober xx, 1996 available. Furthermore, the licensee contingency plans requiredby 10 CFR73.55(h)(1) and the implementing procedures required by Appendix C to Part 73 didnot adequately address tampering, vandalism, and malicious mischief.(2) The licensee actions were limited in scope and depth, at least initially, in pursuing theevents.(3) The Operations staff was not sensitive to abnormalities identified earlier andapparently assumed no malice. Since the Operations staff may be the first toencounter signs of tampering, vandalism, or malicious mischief during its tours andsurveillance activities, sensitivity to precursors plays a key role in timely response toevents of this nature. Therefore, licensees may wish to periodically refresh theirOperations staffs sensitivity to and awareness of the evaluation process to ensureeffective response to these acts.(4) The licensee's Security staff was not told about these problems until well into thesequence of events. Security's ability to identify the perpetrator(s) and institute otherprotective measures diminishes severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to theNRC Operations Center within one hour of discovery.This information notice requires no specific action or written response. If you have anyquestions about the information in this notice, please contact one of the technical contactslisted below or the appropriate Office of Nuclear Reactor Regulation (NRR) project manager.Thomas T. Martin, DirectorDivision of Reactor Program ManagementOffice of Nuclear Reactor Regulation
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| Loren Bush, NRR(301) 415-2944E-mail: llbenrc.govDavid Skeen, NRR(301) 415-1174E-mail: dIs@nrc.govAttachment: List of Recently Issued NRC Information NoticesDOCUMENT NAME: G:IDLSIN96-XX.TPRTo receive a copy of this document,. Indicate i the box: 'C' -Copy w/oattachment/enclosure 'E' -Copy w/attachmenVenclosure 'N' -No copyOFFICE PECB:DRPM -I PSGB:DRPM C/PSWJ RM/ )C/PECB:DRPM I D/DRPMINAME US-keen A50L- ILBush Xx:i' ILCurh&FaIIt V AChaffee TMartinDATE 10/6/4/96 10t796 10 9E -910/ /96 10/ /96OFFICIAL RECORD COPY
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Licensee Response to Indications of Tampering, Vandalism, or Malicious MischiefML031050461 |
Person / Time |
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Site: |
Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Issue date: |
12/27/1996 |
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From: |
Martin T T Office of Nuclear Reactor Regulation |
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To: |
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References |
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IN-96-071, NUDOCS 9612300051 |
Download: ML031050461 (8) |
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Similar Documents at Beaver Valley, Millstone, Hatch, Monticello, Calvert Cliffs, Dresden, Davis Besse, Peach Bottom, Browns Ferry, Salem, Oconee, Mcguire, Nine Mile Point, Palisades, Palo Verde, Perry, Indian Point, Fermi, Kewaunee, Catawba, Harris, Wolf Creek, Saint Lucie, Point Beach, Oyster Creek, Watts Bar, Hope Creek, Grand Gulf, Cooper, Sequoyah, Byron, Pilgrim, Arkansas Nuclear, Three Mile Island, Braidwood, Susquehanna, Summer, Prairie Island, Columbia, Seabrook, Brunswick, Surry, Limerick, North Anna, Turkey Point, River Bend, Vermont Yankee, Crystal River, Haddam Neck, Ginna, Diablo Canyon, Callaway, Vogtle, Waterford, Duane Arnold, Farley, Robinson, Clinton, South Texas, San Onofre, Cook, Comanche Peak, Yankee Rowe, Maine Yankee, Quad Cities, Humboldt Bay, La Crosse, Big Rock Point, Rancho Seco, Zion, Midland, Bellefonte, Fort Calhoun, FitzPatrick, McGuire, LaSalle, Fort Saint Vrain, Shoreham, Satsop, Trojan, Atlantic Nuclear Power Plant |
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Category:NRC Information Notice
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Appendix VI: NRC FOIA Responses (B-51 Through B-53); Turkey Point Event Report; NRC Information Notice 2010-12: Containment Liner Cor Information Notice 2012-13, Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs and Corrective Actions in the Spent Fuel Pool Information Notice 2012-13, Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool2012-08-10010 August 2012 Boraflex Degradation Surveillance Programs And Corrective Actions In The Spent Fuel Pool Information Notice 2012-11, Age Related Capacitor Degradation2012-07-23023 July 2012 Age Related Capacitor Degradation ML12031A0132012-02-0606 February 2012 U.S. Nuclear Regulatory Commission Investigation Report No. 2-2010-058, Cpn International, Inc Information Notice 2011-19, Licensee Event Reports Containing Information Pertaining to Defects to Basic Components2011-09-26026 September 2011 Licensee Event Reports Containing Information Pertaining to Defects to Basic Components Information Notice 2011-15, Steel Containment Degradation and Associated License Renewal Aging Management Issues2011-08-0101 August 2011 Steel Containment Degradation and Associated License Renewal Aging Management Issues Information Notice 2011-17, Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping2011-07-26026 July 2011 Calculation Methodologies for Operability Determinations of Gas Voids in Nuclear Power Plant Piping Information Notice 2011-13, Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 Official Exhibit - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-13, Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13)2011-06-29029 June 2011 Official Exhibit - Nys000329-00-Bd01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (Nrc in 2011-13) Information Notice 2011-13, OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13)2011-06-29029 June 2011 OFFICIAL EXHIBIT - NYS000329-00-BD01 - NRC Information Notice 2011-13, Control Rod Blade Cracking Resulting in Reduced Design Lifetime (Jun 29, 2011) (NRC in 2011-13) Information Notice 2011-04, IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 IN: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 In: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2011-04, in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors2011-02-23023 February 2011 in: Contaminants and Stagnant Conditions Affecting Stress Corrosion Cracking in Stainless Steel Piping in Pressurized Water Reactors Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review2010-12-30030 December 2010 New England Coalition'S Motion for Leave to Reply to NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 and Entergy'S Response to the Supplement to Nec'S Petition for Commission Review of LBP-10-19 Information Notice 2010-26, 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-262010-12-21021 December 2010 2010/12/21-NRC Staff'S Objection to Nec'S Notification of Information Notice 2010-26 ML13066A1872009-12-16016 December 2009 Draft NRC Information Notice 2009-xx - Underestimate of Dam Failure Frequency Used in Probabilistic Risk Assessments ML1007804482009-11-23023 November 2009 Email from Peter Bamford, NRR to Pamela Cowan, Exelon on TMI Contamination Control Event Information Notice 2009-11, NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-112009-07-0707 July 2009 NSP000059-Revised Prefiled Testimony of Northard/Petersen/Peterson-NRC Information Notice 2009-11 Information Notice 2009-10, Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10)2009-07-0707 July 2009 Official Exhibit - NYS000019-00-BD01- NRC Information Notice 2009-10, Transformers Failures - Recent Operating Experience (Jul. 7, 2009) (NRC in 2009-10) Information Notice 2009-09, Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify2009-06-19019 June 2009 Improper Flow Controller Settings Renders Injection Systems Inoperable and Surveillance Did Not Identify Information Notice 2008-12, Reactor Trip Due to Off-Site Power Fluctuation2008-07-0707 July 2008 Reactor Trip Due to Off-Site Power Fluctuation Information Notice 2008-11, Service Water System Degradation at Brunswicksteam Electric Plant Unit 12008-06-18018 June 2008 Service Water System Degradation at Brunswicksteam Electric Plant Unit 1 Information Notice 2008-04, Counterfeit Parts Supplied to Nuclear Power Plants2008-04-0707 April 2008 Counterfeit Parts Supplied to Nuclear Power Plants Information Notice 1991-09, Counterfeiting of Crane Valves2007-09-25025 September 2007 Counterfeiting of Crane Valves Information Notice 2007-28, Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls2007-09-19019 September 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Due to Inadequate Chemistry Controls Information Notice 2007-29, Temporary Scaffolding Affects Operability of Safety-Related Equipment2007-09-17017 September 2007 Temporary Scaffolding Affects Operability of Safety-Related Equipment Information Notice 2007-14, Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station2007-03-30030 March 2007 Loss of Offsite Power and Dual-Unit Trip at Catawba Nuclear Generating Station Information Notice 2007-06, Potential Common Cause Vulnerabilities in Essential Service Water Systems2007-02-0909 February 2007 Potential Common Cause Vulnerabilities in Essential Service Water Systems Information Notice 2007-05, Vertical Deep Draft Pump Shaft and Coupling Failures2007-02-0909 February 2007 Vertical Deep Draft Pump Shaft and Coupling Failures Information Notice 2006-31, Inadequate Fault Interrupting Rating of Breakers2006-12-26026 December 2006 Inadequate Fault Interrupting Rating of Breakers Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves as a Result of Stem Nut Wear Information Notice 2006-29, Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear2006-12-14014 December 2006 Potential Common Cause Failure of Motor-operated Valves As a Result of Stem Nut Wear Information Notice 2006-13, E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination2006-07-13013 July 2006 E-mail from M. Mclaughlin on NRC, Regarding NRC Information Notice 2006-13: Groundwater Contamination 2020-09-03 The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>.
[Table view]The following query condition could not be considered due to this wiki's restrictions on query size or depth: <code> [[:Beaver Valley]] OR [[:Millstone]] OR [[:Hatch]] OR [[:Monticello]] OR [[:Calvert Cliffs]] OR [[:Dresden]] OR [[:Davis Besse]] OR [[:Peach Bottom]] OR [[:Browns Ferry]] OR [[:Salem]] OR [[:Oconee]] OR [[:Mcguire]] OR [[:Nine Mile Point]] OR [[:Palisades]] OR [[:Palo Verde]] OR [[:Perry]] OR [[:Indian Point]] OR [[:Fermi]] OR [[:Kewaunee]] OR [[:Catawba]] OR [[:Harris]] OR [[:Wolf Creek]] OR [[:Saint Lucie]] OR [[:Point Beach]] OR [[:Oyster Creek]] OR [[:Watts Bar]] OR [[:Hope Creek]] OR [[:Grand Gulf]] OR [[:Cooper]] OR [[:Sequoyah]] OR [[:Byron]] OR [[:Pilgrim]] OR [[:Arkansas Nuclear]] OR [[:Three Mile Island]] OR [[:Braidwood]] OR [[:Susquehanna]] OR [[:Summer]] OR [[:Prairie Island]] OR [[:Columbia]] OR [[:Seabrook]] OR [[:Brunswick]] OR [[:Surry]] OR [[:Limerick]] OR [[:North Anna]] OR [[:Turkey Point]] OR [[:River Bend]] OR [[:Vermont Yankee]] OR [[:Crystal River]] OR [[:Haddam Neck]] OR [[:Ginna]] OR [[:Diablo Canyon]] OR [[:Callaway]] OR [[:Vogtle]] OR [[:Waterford]] OR [[:Duane Arnold]] OR [[:Farley]] OR [[:Robinson]] OR [[:Clinton]] OR [[:South Texas]] OR [[:San Onofre]] OR [[:Cook]] OR [[:Comanche Peak]] OR [[:Yankee Rowe]] OR [[:Maine Yankee]] OR [[:Quad Cities]] OR [[:Humboldt Bay]] OR [[:La Crosse]] OR [[:Big Rock Point]] OR [[:Rancho Seco]] OR [[:Zion]] OR [[:Midland]] OR [[:Bellefonte]] OR [[:Fort Calhoun]] OR [[:FitzPatrick]] OR [[:McGuire]] OR [[:LaSalle]] OR [[:Fort Saint Vrain]] OR [[:Shoreham]] OR [[:Satsop]] OR [[:Trojan]] OR [[:Atlantic Nuclear Power Plant]] </code>. |
UNITED STATES NUCLEAR REGULATORY
COMMISSION
OFFICE OF NUCLEAR REACTOR REGULATION-
WASHINGTON, DC 20555-0001 December 27, 1996 NRC INFORMATION
NOTICE NO. 96-71: LICENSEE RESPONSE TO INDICATIONS
OF TAMPERING, VANDALISM, OR MALICIOUS MISCHIEF
Addressees
All holders of operating
licenses or construction
permits for nuclear power reactors.
Purpose
This information
notice is being issued to alert licensees
to the benefits of planning a response to indications
of tampering, vandalism, or malicious
mischief.
It is expected that recipients
will review the information
for applicability
to their facilities
and consider actions, as appropriate.
However, suggestions
contained
in this information
notice are not NRC requirements;
therefore, no specific action or written response is required.Description
of Circumstances
Recent events at operating
reactors indicate that some licensee personnel
may not recognize
the potential
significance
of early indications
of potential
tampering, vandalism, or malicious
mischief.
As a result, licensee response may be untimely and of limited scope and depth. Failure to promptly question, resolve the significance
and implement
an appropriate
strategy to mitigate the consequence
of a potential
tampering, vandalism, or malicious
mischief situation, could leave the plant in a vulnerable
state for a significant
period of time. Lack of detailed planning, procedures, and training frequently
plays a role in the quality of response to these events. Brief accounts of two events illustrate
the issue: Improperly
Positioned
Valve at Beaver Valley During the conduct of a quarterly
surveillance
on Friday, July 14, 1995, to verify the position of certain safety-related
locked valves; the licensee determined
that the service water cross-connect
valve at the discharge
of the recirculation
spray heat exchanger
was in the incorrect
position (shut in lieu of open), that the chain used to secure the valve in the proper position had been cut, and that the lock appeared to have been placed back on the chain in a manner that made it difficult
to detect the condition.
The licensee's
staff initially
assumed the valve had been inadvertently
mispositioned
during earlier operational
evolutions, but subsequent
interviews
and analysis were unable to confirm this assumption.
2 I1.1 r?Pfs ITE 0i-1tttt S%-071Z 9017-21 ai 41 -A,- _ -[,A_ ,a 0 S QAI 912flfA1--v----60do
'I 11 I T2D4t ICG
IN 96-71 December 27, 1996 Licensee management
first learned of the event on Tuesday, July 18, 1995. Consequ-ently, licensee management
was not able to oversee the licensee evaluation
of the event until considerable
time had elapsed. The licensee's
determination
that potential
tampering could not be ruled out was not made until six days after the incorrect
valve position was identified.
Thorough valve lineup checks and locked valve surveillances
were not completed
for both Beaver Valley units until after the plant staff made an emergency notification
system (ENS) call on Thursday evening, July 20, 1995. The similarity
of this event to an event in the early 1 980s heightened
the concern of both licensee and NRC personnel
who knew of the previous events.Misadjusted
Valves and Disabled Locks at St. Lucie In May 1996, St. Lucie personnel
identified
two pressure-relief
valves which, when tested, were found to have pressure setpoints
55 percent and 9 percent above their design values.These valves also had broken wire seals. The root cause could not be determined.
Although tampering
could not be ruled out, it was concluded
that the more likely cause for the misadjusted
valves was poor maintenance.
Licensee management
decided to alert the Security force; however, site Security was not notified.
The failure to follow through on alerting site Security precluded
coordinated
actions of Operations
and Security staffs to enhance awareness
to other possible tampering
events.On July 26, 1996, St. Lucie staff identified
nine padlocks and two door locks in vital areas that were intentionally
damaged to inhibit opening the locks. These locks controlled
personnel
access to various pieces of plant equipment.
The licensee did not identify keylock switches as needing to be checked; consequently, these switches were not checked until August 1996. Although the tampering
of components
within a vital area indicated
the need to be alert to additional
tampering, other than alerting Security, the licensee failed to consider additional
measures to detect tampering.
On August 14, 1996, St. Lucie staff identified
three additional
examples of tampering
in vital areas that inhibited the opening of locks associated
with safety-related
equipment.
Discussion
The following
factors may have contributed
to these events: (1) The licensees'
contingency
plans required by 10 CFR 73.55(h)(1)
and the implementing
procedures
required by Appendix C to Part 73 did not adequately
address tampering, vandalism, and malicious
mischief.
Other licensee procedures
touched some aspects of these situations;
however, no plan or process was used to evaluate the potential
malevolent
event and determine
its importance.
Factors such as safety significance, overtness, intent, sophistication
of method, and the history of similar incidents
were not considered.
Information
Notice 83-27, "Operational
Response to Events Concerning
Deliberate
Acts Directed Against Plant Equipment," described
events in which licensees
were not prepared to assess the situation
and take necessary
steps to ensure the operability
of systems important
to safety or make decisions
concerning
continued
operation.
The information
notice indicated that guidelines
or procedures
prepared by the licensee outlining
a process of
i IN 96-71 December 27, 1996 following
up on both deliberate
and inadvertent
acts with respect to plant operation should be available.
(2) The licensees'
actions were limited in scope and depth, at least initially, in pursuing the events.(3) The licensees'
Operations
staff were not sensitive
to abnormalities
identified
earlier and apparently
assumed no malice. Since the Operations
staff may be the first to encounter
signs of tampering, vandalism, or malicious
mischief during its tours and surveillance
activities, sensitivity
to precursors
plays a key role in timely response to events of this nature. Therefore, licensees
may wish to periodically
refresh their Operations
staff's sensitivity
to and awareness
of the evaluation
process to ensure effective
response to these acts.(4) The licensee's
Security staff was not told about these problems until well into the sequence of events at St. Lucie. Security's
ability to identify the perpetrators
and institute
other protective
measures diminishes
severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to the NRC Operations
Center within one hour of discovery.
This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation
project manager.Thomas T. Martin, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contacts:
Loren Bush, NRR (301) 415-2944 E-mail: llb(nrc.gov
David Skeen, NRR (301) 415-1174 E-mail: dls@nrc.gov
Attachment:
List of Recently Issued NRC Information
Notices AM -chrobL~A
4?f-r S
W-Attachment
IN 96-71 December 27, 1996 LIST OF RECENTLY ISSUED NRC INFORMATION
NOTICES Information
Date of Notice No. Subject Issuance Issued to 96-70 96-69 96-68 96-67 Year 2000 Effect on Computer System Software Operator Actions Affecting Reactivity
Incorrect
Effective
Diaphragm Area Values in Vendor Manual Result in Potential
Failure of Pneumatic
Diaphragm Actuators Vulnerability
of Emergency Diesel Generators
to Fuel Oil/Lubricating
Oil Incom-patibility
Recent Misadministrations
Caused by Incorrect
Cali-brations of Strontium-90
Eye Applicators
Undetected
Accumulation
of Gas in Reactor Coolant System and Inaccurate
Reactor Water Level Indication
During Shutdown 12/24/96 12/20/96 12/19/96 12/19/96 12/13/96 12/11/96 All U.S. Nuclear Regulatory
Commission
licensees, certificate
holders, and registrants
All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All holders of OLs or CPs for nuclear power reactors All U.S. Nuclear Regulatory
Commission
Medical Use Licensees authorized
to use strontium-90 (Sr-90)eye applicators
All holders of OLs or CPs for nuclear power reactors 96-66 96-65 OL = Operating
License CP = Construction
Permit
IN 96-71 December 27, 1996 following
up on both deliberate
and inadvertent
acts with respect to plant operation should be available.
t (2) The licensees'
actions were limited in scope and depth, at least initially, in pursuing the events.(3) The licensees'
Operations
staff were not sensitive
to abnormalities
identified
earlier and apparently
assumed no malice. Since the Operations
staff may be the first to encounter
signs of tampering, vandalism, or malicious
mischief during its tours and surveillance
activities, sensitivity
to precursors
plays a key role in timely response to events of this nature. Therefore, licensees
may wish to periodically
refresh their Operations
staff's sensitivity
to and awareness
of the evaluation
process to ensure effective
response to these acts.(4) The licensee's
Security staff was not told about these problems until well into the sequence of events at St. Lucie. Security's
ability to identify the perpetrator(s)
and institute
other protective
measures diminishes
severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to the NRC Operations
Center within one hour of discovery.
This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation
project manager.original signed by D.B. Matthews Thomas T. Martin, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contacts:
Loren Bush, NRR David Skeen, NRR (301) 415-2944 (301) 415-1174 E-mail: llb@nrc.gov
E-mail: dls@nrc.gov
Tech Editor has reviewed and concurred
on 9/27/96 Attachment:
List of Recently Issued NRC Information
Notices DOCUMENT NAME: 96-71.IN To receive a copy of this document.
hIdlcate I the box: 'C' -Copy w/o attachmentlenclosure
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I D/DRP I I NAME LBush* AChaffee*
TMart DSkeen* L ' I DATE 10/31/96 11/01/96 12 OFFICIAL RECORD COPY
- IN 96-December , 1996 following
up on both deliberate
and inadvertent
acts with respect to plant operation should be available.
(2) The licensees'
actions were limited in scope and depth, at least initially, in pursuing the events.(3) The licensees'
Operations
staff were not sensitive
to abnormalities
identified
earlier and apparently
assumed no malice. Since the Operations
staff may be the first to encounter
signs of tampering, vandalism, or malicious
mischief during its tours and surveillance
activities, sensitivity
to precursors
plays a key role in timely response to events of this nature. Therefore, licensees
may wish to periodically
refresh their Operations
staff's sensitivity
to and awareness
of the evaluation
process to ensure effective
response to these acts.(4) The licensee's
Security staff was not told about these problems until well into the sequence of events at St. Lucie. Security's
ability to identify the perpetrators
and institute
other protective
measures diminishes
severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to the NRC Operations
Center within one hour of discovery.
This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation
project manager.Thomas T. Martin, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
contacts:
Loren Bush, NRR David Skeen, NRR (301) 415-2944 (301) 415-1174 E-mail: llb@nrc.gov
E-mail: dls@nrc.gov
Tech Editor has reviewed and concurred
on 9/27/96 Attachment:
List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:\DLS\96-XXX
To receive a copy of this document.
indicate In the box: 'C -Copy w/o attachment/enclosure
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l D/DRPJ- I NAME LBush* AChaffee*
Toard n DSkeen1 A a e haW DATE 10/31/96 11/01/96 12/zo /96 Al. -r ... -.A In-n n/I U11l.IWAL
KLLUKU HUrY 4 t
- IN 96-XX November xx, 1996 available.
Furthermore, the licensee contingency
plans requiredby
10 CFR 73.55(h)(1)
and the implementing
procedures
required by Appendix C to Part 73 did not adequately
address tampering, vandalism, and malicious
mischief.(2) The licensee actions were limited in scope and depth, at least initially, in pursuing the events.(3) The Operations
staff was not sensitive
to abnormalities
identified
earlier and apparently
assumed no malice. Since the Operations
staff may be the first to encounter
signs of tampering, vandalism, or malicious
mischief during its tours and surveillance
activities, sensitivity
to precursors
plays a key role in timely response to events of this nature. Therefore, licensees
may wish to periodically
refresh their Operations
staffs sensitivity
to and awareness
of the evaluation
process to ensure effective
response to these acts.(4) The licensee's
Security staff was not told about these problems until well into the sequence of events. Security's
ability to identify the perpetrator(s)
and institute
other protective
measures diminishes
severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to the NRC Operations
Center within one hour of discovery.
This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Thomas T. Martin, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
Contact: Loren Bush, NRR (301) 415-2944 E-mail: llb@nrc.gov
David Skeen, NRR (301) 415-1174 E-mail: dls@nrc.gov
Attachment:
List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:MDLS\IN96-XX.TPR
To receive a copy of this document.
hIdicate hI the box: 'C' -Copy w/o attachmenVenclosure
'E' -Copy wlattachmentlenclosure
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IC PSGB:DRPM
C/PSGB:DRPM
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LBush* LCunninghamnM
AChaffeeCifv-'
TMartin DATE 10/3//96 10/xv/96 10/ /96 1l// /96 3y9 10/ /96-i OFFICIAL RECORD COPY*- pervias 44 1i I
K.IN 96-XX October xx, 1996 available.
Furthermore, the licensee contingency
plans requiredby
10 CFR 73.55(h)(1)
and the implementing
procedures
required by Appendix C to Part 73 did not adequately
address tampering, vandalism, and malicious
mischief.(2) The licensee actions were limited in scope and depth, at least initially, in pursuing the events.(3) The Operations
staff was not sensitive
to abnormalities
identified
earlier and apparently
assumed no malice. Since the Operations
staff may be the first to encounter
signs of tampering, vandalism, or malicious
mischief during its tours and surveillance
activities, sensitivity
to precursors
plays a key role in timely response to events of this nature. Therefore, licensees
may wish to periodically
refresh their Operations
staffs sensitivity
to and awareness
of the evaluation
process to ensure effective
response to these acts.(4) The licensee's
Security staff was not told about these problems until well into the sequence of events. Security's
ability to identify the perpetrator(s)
and institute
other protective
measures diminishes
severely as time elapses.Events of this nature are required by Appendix G to Part 73 of 10 CFR to be reported to the NRC Operations
Center within one hour of discovery.
This information
notice requires no specific action or written response.
If you have any questions
about the information
in this notice, please contact one of the technical
contacts listed below or the appropriate
Office of Nuclear Reactor Regulation (NRR) project manager.Thomas T. Martin, Director Division of Reactor Program Management
Office of Nuclear Reactor Regulation
Technical
Contact: Loren Bush, NRR (301) 415-2944 E-mail: llbenrc.gov
David Skeen, NRR (301) 415-1174 E-mail: dIs@nrc.gov
Attachment:
List of Recently Issued NRC Information
Notices DOCUMENT NAME: G:IDLSIN96-XX.TPR
To receive a copy of this document,.
Indicate i the box: 'C' -Copy w/o attachment/enclosure
'E' -Copy w/attachmenVenclosure
'N' -No copy OFFICE PECB:DRPM
-I PSGB:DRPM
C/PSWJ RM/ )C/PECB:DRPM
I D/DRPM INAME US-keen A50L- ILBush Xx:i' ILCurh&FaIIt
V AChaffee TMartin DATE 10/6/4/96
10t796 10 9E -910/ /96 10/ /96 OFFICIAL RECORD COPY
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list | - Information Notice 1996-01, Potential For High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-01, Potential for High Post-Accident Closed-Cycle Cooling Water Temperatures to Disable Equipment Important to Safety (3 January 1996)
- Information Notice 1996-02, Inoperability of Power-Operated Relief Valves Masked by Downstream Indications During Testing (5 January 1996, Topic: Stroke time)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation as a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-03, Main Steam Safety Valve Setpoint Variation As a Result of Thermal Effects (5 January 1996)
- Information Notice 1996-04, Incident Reporting Requirements for Radiography Licensees (10 January 1996, Topic: Brachytherapy, Overexposure, Depleted uranium)
- Information Notice 1996-05, Partial Bypass of Shutdown Cooling Flow from Reactor Vessel (18 January 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-06, Design & Testing Deficiencies of Tornado Dampers at Nuclear Power Plants (25 January 1996)
- Information Notice 1996-07, Slow Five Percent Scram Insertion Times Caused by Viton Diaphragms in Scram Solenoid Pilot Valves (26 January 1996)
- Information Notice 1996-08, Thermally Induced Pressure Locking of a High Pressure Coolant Injection Gate Valve (5 February 1996, Topic: Anchor Darling, Cold shutdown justification)
- Information Notice 1996-09, Damage in Foreign Steam Generator Internals (12 February 1996, Topic: Eddy Current Testing, Earthquake)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which Is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-10, Potential Blockage by Debris of Safety System Piping Which is Not Used During Normal Operation or Tested During Surveillances (13 February 1996)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential For Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1996-11, Ingress of Demineralizer Resins Increases Potential for Stress Corrosion Cracking of Control Rod Drive Mechanism Penetrations (14 February 1996, Topic: Intergranular Stress Corrosion Cracking, Stress corrosion cracking)
- Information Notice 1996-12, Control Rod Insertion Problems (15 February 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-13, Potential Containment Leak Paths Through Hydrogen Analysis (26 February 1996, Topic: Stress corrosion cracking, Integrated leak rate test)
- Information Notice 1996-14, Degradation of Radwaste Facility Equipment at Millstone Nuclear Power Station, Unit 1 (1 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-15, Unexpected Plant Performance During Performance of New Surveillance (8 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-16, BWR Operation with Indicated Flow Less than Natural Circulation (14 March 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-17, Reactor Operation Inconsistent with the Updated Final Safety Analysis Report (18 March 1996)
- Information Notice 1996-18, Compliance with 10 CFR Part 20 for Airborne Thorium (25 March 1996, Topic: Stress corrosion cracking, Brachytherapy)
- Information Notice 1996-19, Failure of Tone Alert Radios to Activate When Receiving a Shortened Activation Signal (2 April 1996, Topic: Tone Alert Radio, Siren)
- Information Notice 1996-20, Demonstration of Associated Equipment Compliance with 10 CFR 34.20 (4 April 1996, Topic: Brachytherapy)
- Information Notice 1996-21, Safety Concerns Related to the Design of the Door Interlock Circuit on Nucletron High-Dose Rate and Pulsed Dose Rate Remote Afterloading Brachytherapy Devices (10 April 1996, Topic: Brachytherapy)
- Information Notice 1996-22, Improper Equipment Settings Due to Use of Nontemperature-Compensated Test Equipment (11 April 1996, Topic: Brachytherapy)
- Information Notice 1996-23, Fires in Emergency Diesel Generator Exciters During Operation Following Undetected Fuse Blowing (22 April 1996, Topic: Brachytherapy, Overspeed trip, Overspeed)
- Information Notice 1996-24, Preconditioning of Molded-Case Circuit Breakers Before Surveillance Testing (25 April 1996, Topic: Brachytherapy)
- Information Notice 1996-25, Traversing In-Core Probe Overwithdrawn at Lasalle County Station, Unit 1 (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems with Overhead Cranes (30 April 1996, Topic: Brachytherapy)
- Information Notice 1996-26, Recent Problems With Overhead Cranes (30 April 1996)
- Information Notice 1996-27, Potential Clogging of High Pressure Safety Injection Throttle Valves During Recirculation (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-28, Suggested Guidance Relating to Development and Implementation of Corrective Action (1 May 1996, Topic: Brachytherapy)
- Information Notice 1996-29, Requirements in 10 CFR Part 21 for Reporting and Evaluating Software Errors (20 May 1996, Topic: Brachytherapy)
- Information Notice 1996-30, Inaccuracy of Diagnostic Equipment for Motor-Operated Butterfly Valves (21 May 1996)
- Information Notice 1996-31, Cross-Tied Safety Injection Accumulators (22 May 1996)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (II) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-32, Implementation of 10 CFR 50.55a(g) (6) (ii) (A), Augmented Examination of Reactor Vessel (5 June 1996, Topic: Non-Destructive Examination)
- Information Notice 1996-33, Erroneous Data From Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-33, Erroneous Data from Defective Thermocouple Results in a Fire (24 May 1996, Topic: Reverse polarity)
- Information Notice 1996-34, Hydrogen Gas Ignition During Closure Welding of a VSC-24 Multi-Assembly Sealed Basket (31 May 1996)
- Information Notice 1996-35, Failure of Safety Systems on Self-Shielded Irradiators Because of Inadequate Maintenance and Training (11 June 1996)
- Information Notice 1996-36, Degradation of Cooling Water Systems Due to Icing (12 June 1996, Topic: High winds, Ultimate heat sink, Frazil ice)
- Information Notice 1996-37, Inaccurate Reactor Water Level Indication and Inadvertent Draindown During Shutdown (18 June 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-38, Results of Steam Generator Tube Examinations (21 June 1996, Topic: Stress corrosion cracking)
- Information Notice 1996-39, Estimates of Decay Heat Using ANS 5.1 Decay Heat Standard May Vary Significantly (5 July 1996)
- Information Notice 1996-40, Defciencies in Material Dedication and Procurement Practices and in Audits of Vendors (7 October 1996, Topic: Coatings, Commercial Grade, Troxler)
- Information Notice 1996-41, Effects of a Decrease in Feedwater Temperature on Nuclear Instrumentation (26 July 1996, Topic: Feedwater Heater)
- Information Notice 1996-42, Unexpected Opening of Multiple Safety Relief Valves (5 August 1996, Topic: Reactor Vessel Water Level)
- Information Notice 1996-43, Failures of General Electric Magne-Blast Circuit Breakers (2 August 1996, Topic: Hardened grease)
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