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Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217J2381999-10-13013 October 1999 Informs That Attached Questions Transmitted by Fax on 991013 to J Rainsberry of Southern California Corp to Prepare for Upcoming Telephone Call ML20212G3791999-09-24024 September 1999 Notification of 991006-07 Meeting with Industry in San Clemente,California to Discuss Technical Issues Re Industry Development of Submittals for risk-informed Technical Specification Improvements ML20211J5591999-09-0101 September 1999 Informs That Application Date in First Line of Attached Ltr Issued 990823 Corrected to Read 990625, Not 1997. Requests That Corrected Copy Be Submitted to H Ray ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20211H0431999-08-0909 August 1999 Submits Comments on San Onofre Response to NRC Request for Addl Info on risk-informed IST Program ML20210G4671999-07-30030 July 1999 Forwards Draft rept,NUREG/CR-xxxx,Vol x,INEEL/EXT-99-00373, High-Pressure Safety Injection Sys Reliability,1987-1997 ML20195H7251999-06-11011 June 1999 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam,Submittal for Retake Exam Administered on 990416 ML20195H6031999-06-11011 June 1999 Forwards Exam Repts 50-361/99-301 & 50-362/99-301 Administered at Facility on 990416,with as Given Written Exam Attached ML20207F1141999-06-0404 June 1999 Notification of Significant Licensee Meeting with Util on 990628 to Discuss Emergency Preparedness Program Status & Planned Changes ML20205Q4491999-04-19019 April 1999 Forwards Viewgraphs of 990419 Telcon Re SG Eddy Current Insp Results Obtained During Imminent Refueling Outage ML20205N8821999-04-15015 April 1999 Forwards Questions Transmitted by Fax on 990415 to J Rainsberry of SCE & Request for Conference Call to Be Scheduled with Staff to Discuss SG Eddy Current Insp Results Obtained During Imminent Refueling Outage ML20205N5991999-04-14014 April 1999 Forwards Questions That Were Transmitted by Fax on 990414 to J Rainsberry of Southern California Corp,In Preparation for Upcoming Telcon on Recirculation Signal/Emergency Feedwater Actuation Signal While Channel in Tripped Condition ML20205M0111999-04-13013 April 1999 Forwards Questions to Be Discussed in Upcoming Telcon on GL 95-07.Questions Transmitted by Fax on 990413 to J Rrainsberry of SCE ML20205K4621999-04-0606 April 1999 Notification of Licensee Meeting with Util on 990422 to Discuss Results of PPR 99-01 ML20207L7041999-03-0202 March 1999 Notification of 990318 Meeting with SCE in Rockville, Maryland to Discuss SCE Mgt Plans for Future risk-informed License Amend Applications for SONGS ML20207L7091999-03-0202 March 1999 Notification of 990317 Meeting with SCE in Rockville, Maryland to Discuss Topics Resulting from NRC Staff Review & Confirmatory Analysis of Licensee Request to Remove Hydrogen Control Sys from SONGS Licensing Basis.Meeting Agenda Encl ML20202C3931999-01-22022 January 1999 Forwards Exam Rept Administered on 981115-20 at San Onofre Nuclear Generating Station,With as Given Written Exam Encl ML20199L3401999-01-22022 January 1999 Forwards Facility Submitted Outline,Initial Exam & as Given Operating Exam for Test Administered on 981115-20 at San Onofre Nuclear Generation Station ML20198M3241998-12-29029 December 1998 Submits Summary of Telcon Re Proposed Criteria to Support Development of SER Constraints for Reload Analysis Tr,For Plant,Units 2 & 3 ML20196G6481998-11-0303 November 1998 Notification of Significant Meeting with Util on 981125 at One White Flint to Discuss Licensee Views on Efforts to Maintain Safety Conscious Work Environ ML20155C9621998-10-27027 October 1998 Notification of 981124 Meeting with Util to Discuss Results of Employee Concerns Program Survey ML20153B4531998-09-0404 September 1998 Notification of Cancellation of 980924 Meeting with TVA in Rockville,Md to Discuss Review of Best Estimate of LOCA Methodology at Plant,Unit 2 ML20236Y6301998-08-0808 August 1998 Forwards Monthly Rept Reflecting Status of 10CFR2.206 Petitions as of 980731.Petitions on Plant GT97494 & GT97339 for Which DD Became Final Actions During Month Were Closed. Portion of Encl Withheld ML20237A0011998-08-0707 August 1998 Informs That Extension Granted on Envirocare Decision of 980904.Two Week Extension on Philadelphia VA Decision of 980828 Requested.Submits Concurrence of Changes.Rept on 2.206 July Status for Plants Encl ML20236K9071998-07-0707 July 1998 Notification of 980710 Meeting W/Util,Rescheduled from 980707,in Rockville MD to Discuss Proposed Amend for Extension of Allowed Outage Times for EDG ML20236K3021998-06-30030 June 1998 Notification of 980707 Meeting W/Util in Rockville,Md to Discuss Licensee Proposed Amend for Extension of Allowed Outage Times for EDG ML20249C2721998-06-19019 June 1998 Notification of 980707 Meeting W/Util in Arlington,Texas to Discuss SONGS New Security Mgt ML20249A1181998-06-11011 June 1998 Notification of 980630 Meeting W/Util in Region IV Office to Discuss Plant Performance Status & Effectiveness of Initiatives to Improve Performance ML20249A1221998-06-11011 June 1998 Forwards Unsolicited Info from San Onofre Licensee Re Emergency Diesel Generator Delegation Allowed Outage Time Extension TS Request ML20249A5621998-06-10010 June 1998 Notification of 980615 Meeting W/Util in Rockville,Md to Discuss SONGS Mgt drop-in Visit by Licensee New Manager, Regulatory Affairs ML20248L8621998-06-0909 June 1998 Forwards May 1998 Rept on Status of Public Petitioners Under 10CFR2.206.Petition on Seabrook (GT970873) for Which DD 98- 03 Became Final Agency Decision on 980413 Closed.Attachment 3 Withheld ML20248C8461998-05-29029 May 1998 Notification of 980529 Meeting W/Util in Rockville,Md for Licensee to Present Proposal for Performing Own Reload Analyses ML20248B6071998-05-26026 May 1998 Notification of Licensee Meeting W/Util on 980528 Re drop-in Visit by Licensee New Manager of Regulatory Affairs for Purpose of Meeting Senior Region IV Mgt ML20216H3281998-04-15015 April 1998 Notification of 980429 Meeting W/Util in Rockville,Md to Discuss Licensee Proposal for Changing Minimum Tcold for Plant Operation & Performing Own Reload Analyses ML20198J5461998-01-0707 January 1998 Notification of Licensee Meeting W/Util on 980120 to Discuss Apparent Violations Involving Physical Security Program. Meeting Not Open to Public ML20198F8931997-12-22022 December 1997 Informs That on 970304,San Onofre,Unit 2,pressurizer Vessel Experienced Cooldown Transient at Rate Greater than 200 F/Hr Limit Specified in Tss.Fracture Mechanics Evaluation of Pressurizer Transient Met Criteria in App G of ASME Code ML20203D4321997-12-0909 December 1997 Notifies of 971223 Meeting W/Util in Rockville,Md to Discuss Use of Mechanical Nozzle Seal Assemblies as Alternate ASME Code Replacements at Plant ML20199A7951997-11-0707 November 1997 Notification of Meeting W/Util on 971121 at Plant to Discuss Employee Concerns Program ML20198Q8611997-11-0606 November 1997 Forwards Copy of e-mail Response to e-mail Inquiry Received from J Chang of San Onofre Nuclear Station Re Info Notice 97-038, Level Sensing System Initiates Common Mode Failure of High Pressure Injection Pumps ML20217J6961997-10-16016 October 1997 Notification of Meeting W/Util on 971023 in Rockville,Md to Discuss Plans for Inspecting SG at Plant,Units 2 & 3 & Runtime Analysis Submitted on 970925 ML20211C4001997-09-22022 September 1997 Notification of Revised Licensee Meeting W/Util on 970930 in Arlington,Tx Re Predecisional Enforcement Conference ML20210T2841997-09-10010 September 1997 Notification of 970924 Licensee Meeting W/Sce in in Arlington,Tx Re Predecisional Enforcement Conference ML20141J8201997-08-18018 August 1997 Notification of 970821 Licensee Meeting W/Util in Arlington, Tx to Discuss RCS Nozzle Penetration Cracking ML20217G5901997-08-0202 August 1997 Informs That Notification Was Made to NRC Operations Center on 970802 as Listed ML20149F8771997-07-18018 July 1997 Notification of 970827 Licensee Meeting W/Util in San Clemente,Ca Re SALP ML20149D7881997-07-15015 July 1997 Revised Notice of Licensee Meeting W/Util in Arlington,Tx on 970805 to Discuss Employee Concerns Program ML20140B6061997-06-0303 June 1997 Notification of 970611 Meeting in Rockville,Md to Discuss Evaluation Rept Re Eggcrate Support Degradation Identified in San Onofre Unit 3 SG ML20141K8751997-05-27027 May 1997 Notifies of 970529 Meeting W/Util in Rockville,Md to Discuss San Onofre Unit 3 SG Eggcrate Visual Exam Results ML20138G2891997-04-30030 April 1997 Notification of 970509 Meeting W/Util in Rockville,Md to Discuss Operational Issues Re Eggcrate Support Degradation Recently Identified in Plant,Unit 3 SGs ML20149H5221997-04-25025 April 1997 Amended Emergency Petition Re Degradation of Steam Generator Internal Tube Supports (Egg Crates),Based on 970417 Rept. Plant Will Not Be Able to Completely Withstand Major Seismic Event 1999-09-24
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217J2381999-10-13013 October 1999 Informs That Attached Questions Transmitted by Fax on 991013 to J Rainsberry of Southern California Corp to Prepare for Upcoming Telephone Call ML20212G3791999-09-24024 September 1999 Notification of 991006-07 Meeting with Industry in San Clemente,California to Discuss Technical Issues Re Industry Development of Submittals for risk-informed Technical Specification Improvements ML20211J5591999-09-0101 September 1999 Informs That Application Date in First Line of Attached Ltr Issued 990823 Corrected to Read 990625, Not 1997. Requests That Corrected Copy Be Submitted to H Ray ML20211H4441999-08-27027 August 1999 Notification of Significant Meeting with Util on 990916 & 17 in Arlington,Tx to Improve Utility & NRC Understanding of Industry & Regulatory Perspectives on Current Issues ML20211H0431999-08-0909 August 1999 Submits Comments on San Onofre Response to NRC Request for Addl Info on risk-informed IST Program ML20210G4671999-07-30030 July 1999 Forwards Draft rept,NUREG/CR-xxxx,Vol x,INEEL/EXT-99-00373, High-Pressure Safety Injection Sys Reliability,1987-1997 ML20195H6031999-06-11011 June 1999 Forwards Exam Repts 50-361/99-301 & 50-362/99-301 Administered at Facility on 990416,with as Given Written Exam Attached ML20195H7251999-06-11011 June 1999 Forwards NRC Approved Operator Licensing Exam Facility Outline & Initial Exam,Submittal for Retake Exam Administered on 990416 ML20207F1141999-06-0404 June 1999 Notification of Significant Licensee Meeting with Util on 990628 to Discuss Emergency Preparedness Program Status & Planned Changes ML20205Q4491999-04-19019 April 1999 Forwards Viewgraphs of 990419 Telcon Re SG Eddy Current Insp Results Obtained During Imminent Refueling Outage ML20205N8821999-04-15015 April 1999 Forwards Questions Transmitted by Fax on 990415 to J Rainsberry of SCE & Request for Conference Call to Be Scheduled with Staff to Discuss SG Eddy Current Insp Results Obtained During Imminent Refueling Outage ML20205N5991999-04-14014 April 1999 Forwards Questions That Were Transmitted by Fax on 990414 to J Rainsberry of Southern California Corp,In Preparation for Upcoming Telcon on Recirculation Signal/Emergency Feedwater Actuation Signal While Channel in Tripped Condition ML20205M0111999-04-13013 April 1999 Forwards Questions to Be Discussed in Upcoming Telcon on GL 95-07.Questions Transmitted by Fax on 990413 to J Rrainsberry of SCE ML20205K4621999-04-0606 April 1999 Notification of Licensee Meeting with Util on 990422 to Discuss Results of PPR 99-01 ML20207L7091999-03-0202 March 1999 Notification of 990317 Meeting with SCE in Rockville, Maryland to Discuss Topics Resulting from NRC Staff Review & Confirmatory Analysis of Licensee Request to Remove Hydrogen Control Sys from SONGS Licensing Basis.Meeting Agenda Encl ML20207L7041999-03-0202 March 1999 Notification of 990318 Meeting with SCE in Rockville, Maryland to Discuss SCE Mgt Plans for Future risk-informed License Amend Applications for SONGS ML20199L3401999-01-22022 January 1999 Forwards Facility Submitted Outline,Initial Exam & as Given Operating Exam for Test Administered on 981115-20 at San Onofre Nuclear Generation Station ML20202C3931999-01-22022 January 1999 Forwards Exam Rept Administered on 981115-20 at San Onofre Nuclear Generating Station,With as Given Written Exam Encl ML20198M3241998-12-29029 December 1998 Submits Summary of Telcon Re Proposed Criteria to Support Development of SER Constraints for Reload Analysis Tr,For Plant,Units 2 & 3 ML20196G6481998-11-0303 November 1998 Notification of Significant Meeting with Util on 981125 at One White Flint to Discuss Licensee Views on Efforts to Maintain Safety Conscious Work Environ ML20155C9621998-10-27027 October 1998 Notification of 981124 Meeting with Util to Discuss Results of Employee Concerns Program Survey ML20153B4531998-09-0404 September 1998 Notification of Cancellation of 980924 Meeting with TVA in Rockville,Md to Discuss Review of Best Estimate of LOCA Methodology at Plant,Unit 2 ML20236Y6301998-08-0808 August 1998 Forwards Monthly Rept Reflecting Status of 10CFR2.206 Petitions as of 980731.Petitions on Plant GT97494 & GT97339 for Which DD Became Final Actions During Month Were Closed. Portion of Encl Withheld ML20237A0011998-08-0707 August 1998 Informs That Extension Granted on Envirocare Decision of 980904.Two Week Extension on Philadelphia VA Decision of 980828 Requested.Submits Concurrence of Changes.Rept on 2.206 July Status for Plants Encl ML20236K9071998-07-0707 July 1998 Notification of 980710 Meeting W/Util,Rescheduled from 980707,in Rockville MD to Discuss Proposed Amend for Extension of Allowed Outage Times for EDG ML20236K3021998-06-30030 June 1998 Notification of 980707 Meeting W/Util in Rockville,Md to Discuss Licensee Proposed Amend for Extension of Allowed Outage Times for EDG ML20249C2721998-06-19019 June 1998 Notification of 980707 Meeting W/Util in Arlington,Texas to Discuss SONGS New Security Mgt ML20249A1221998-06-11011 June 1998 Forwards Unsolicited Info from San Onofre Licensee Re Emergency Diesel Generator Delegation Allowed Outage Time Extension TS Request ML20249A1181998-06-11011 June 1998 Notification of 980630 Meeting W/Util in Region IV Office to Discuss Plant Performance Status & Effectiveness of Initiatives to Improve Performance ML20249A5621998-06-10010 June 1998 Notification of 980615 Meeting W/Util in Rockville,Md to Discuss SONGS Mgt drop-in Visit by Licensee New Manager, Regulatory Affairs ML20248L8621998-06-0909 June 1998 Forwards May 1998 Rept on Status of Public Petitioners Under 10CFR2.206.Petition on Seabrook (GT970873) for Which DD 98- 03 Became Final Agency Decision on 980413 Closed.Attachment 3 Withheld ML20248C8461998-05-29029 May 1998 Notification of 980529 Meeting W/Util in Rockville,Md for Licensee to Present Proposal for Performing Own Reload Analyses ML20248B6071998-05-26026 May 1998 Notification of Licensee Meeting W/Util on 980528 Re drop-in Visit by Licensee New Manager of Regulatory Affairs for Purpose of Meeting Senior Region IV Mgt ML20216H3281998-04-15015 April 1998 Notification of 980429 Meeting W/Util in Rockville,Md to Discuss Licensee Proposal for Changing Minimum Tcold for Plant Operation & Performing Own Reload Analyses ML20198J5461998-01-0707 January 1998 Notification of Licensee Meeting W/Util on 980120 to Discuss Apparent Violations Involving Physical Security Program. Meeting Not Open to Public ML20198F8931997-12-22022 December 1997 Informs That on 970304,San Onofre,Unit 2,pressurizer Vessel Experienced Cooldown Transient at Rate Greater than 200 F/Hr Limit Specified in Tss.Fracture Mechanics Evaluation of Pressurizer Transient Met Criteria in App G of ASME Code ML20203D4321997-12-0909 December 1997 Notifies of 971223 Meeting W/Util in Rockville,Md to Discuss Use of Mechanical Nozzle Seal Assemblies as Alternate ASME Code Replacements at Plant ML20199A7951997-11-0707 November 1997 Notification of Meeting W/Util on 971121 at Plant to Discuss Employee Concerns Program ML20198Q8611997-11-0606 November 1997 Forwards Copy of e-mail Response to e-mail Inquiry Received from J Chang of San Onofre Nuclear Station Re Info Notice 97-038, Level Sensing System Initiates Common Mode Failure of High Pressure Injection Pumps ML20217J6961997-10-16016 October 1997 Notification of Meeting W/Util on 971023 in Rockville,Md to Discuss Plans for Inspecting SG at Plant,Units 2 & 3 & Runtime Analysis Submitted on 970925 ML20211C4001997-09-22022 September 1997 Notification of Revised Licensee Meeting W/Util on 970930 in Arlington,Tx Re Predecisional Enforcement Conference ML20210T2841997-09-10010 September 1997 Notification of 970924 Licensee Meeting W/Sce in in Arlington,Tx Re Predecisional Enforcement Conference ML20141J8201997-08-18018 August 1997 Notification of 970821 Licensee Meeting W/Util in Arlington, Tx to Discuss RCS Nozzle Penetration Cracking ML20217G5901997-08-0202 August 1997 Informs That Notification Was Made to NRC Operations Center on 970802 as Listed ML20149F8771997-07-18018 July 1997 Notification of 970827 Licensee Meeting W/Util in San Clemente,Ca Re SALP ML20149D7881997-07-15015 July 1997 Revised Notice of Licensee Meeting W/Util in Arlington,Tx on 970805 to Discuss Employee Concerns Program ML20140B6061997-06-0303 June 1997 Notification of 970611 Meeting in Rockville,Md to Discuss Evaluation Rept Re Eggcrate Support Degradation Identified in San Onofre Unit 3 SG ML20141K8751997-05-27027 May 1997 Notifies of 970529 Meeting W/Util in Rockville,Md to Discuss San Onofre Unit 3 SG Eggcrate Visual Exam Results ML20138G2891997-04-30030 April 1997 Notification of 970509 Meeting W/Util in Rockville,Md to Discuss Operational Issues Re Eggcrate Support Degradation Recently Identified in Plant,Unit 3 SGs ML20149H5221997-04-25025 April 1997 Amended Emergency Petition Re Degradation of Steam Generator Internal Tube Supports (Egg Crates),Based on 970417 Rept. Plant Will Not Be Able to Completely Withstand Major Seismic Event 1999-09-24
[Table view] |
Text
G. H.
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! :rci 'o UNITED STATES M. '
['$. J) u ( [' g g,
NUCLEAR REGULATORY COMMISSION Sc O ml REGION V gg s-
- y, 1450 MARIA LANE, SUITE 210
% ' 'W/ ,6 WALNUT CREEK, CALIFORNI A 94596
- JUL 171986 MEMORANDUM FOR: C. J. Heltemes, Jr., Director Office for Analysir and i Evaluation of Operational Data FROM: J. B. Martin, Regional Administrator
SUBJECT:
ABNORMAL OCCURRENCE REPORT TO CONGRESS FOR SECOND QUARTER CY 1986 Attached are proposed writeups for the subject report in response to your memorandum of July 1, 1986. .
By memorandum, J. L. Montgomery to C. J. Heltemes, dated July 9, 1986, we forwarded a proposed A0 regarding a diagnostic misadministration at Tripler Army Medical Center.
A proposed Enclosure 3 item was forwarded to your office by memorandum D. F.
Kirsch to F. Hebdon, dated April 30, 1986. We will review the writeup your office proposed to prepare covering a series of such events and provide appropriate comments at that time.
l Should you have questions regarding the ite.is proposed for the subject report, !
please contact Jess Crews or Bobby Faulkenberry of my staff. !
/4 (2 . .
p'w . B. Martin Regicnal Admini ator
Enclosures:
- 1. Appendix B Items - A0 85-1 (update) and A0 86-1 (update)
- 2. Appendix C Item - Suspected Sabotage (Palo Verde Nuclear Generating Station) cc w/ enclosures:
J. Crews A. Chaffee P. Johnson P. Narbut R. Huey N
'N x 8708070161 870'804 PDR FOIA PDR E GORDON87-377 3
'. . l I
Enclosure 1 APPENDIX B UPDATE OF PREVIOUSLY REPORTED ABNORMAL OCCURRENCES 85-1 Premature Criticality During Startup 1
{ This abnormal occurrence was originally reported in NUREG 0090, Volume 8, No. 1. The item involved Summer Unit 1. It is updated to describe a somewhat similar event which occurred at San Onofre Unit 3 on April 13, 1986.
San Onofre Premature Criticality l
At 11:16 a.m. on April 13, 1986, while the licensee was performing a recovery from a spurious reactor trip which had occurred 'the previous day, the reactor tripped after achieving criticality at a withdrawal l position lower than predicted by the Estimated Critical Position (ECP). '
The licensee made a 4-hour report of the reactor tip to the NRC Duty Officer at 3:00 p.m. PST. This ENS report indicated that the reactor had tripped on departure from nucleated boiling ratio (DNBR) and local power .
density (LPD) trip signals generated by the core protection calculator I (CPC), because of penalty factors resulting from minor control rod misalignments. The following sequence of events occurred:
i Operations personnel calculated an ECP of 60 inches on group 6, l
l j
l based on an estimated criticality at 11:00 a.m. Although two s l
previous startups had been conducted since the first refueling i outage which ended in early 1986, this was the first startup with j significant xenon present. '
j
- Regulating groups 1, 2, and 3 were withdrawn to their upper group limits. However, they were not individually aligned to uniform height at the fully withdrawn position, as specified in the j procedure, because of preoccupation with achieving criticality near the 11:00 a.m. time on which the ECP was based. As a result, some group 1 rods were inserted approximately one inch more than group 2 rods, which generated an out-of-sequence penalty factor signal to the CPC. The operators' intent was to dress the rods after criticality was achieved before the penalty factors became effective (at 10E-4% power).
When group 4 rods reached approximately 80 inches withdrawn, the reactor achieved criticality (at approximately 10E-5% power). This was not immediately recognized by the operator and rod withdrawal continued to approximately 114 inches before the critical condition was recognized. The reactor controls were being manipulated by a reactor operator trainee under the direct supervision of a licensed reactor operator. Other licensed personnel were present in the control room.
When criticality was recognized, the operator began inserting control rods. However, power had by this time reached 10E-4% power,
l at whf-h point the CPC reactor trips were enabled. Increasing penalty factors as the rods were inserted initiated DNBR and LPD reactor trips at a rod position of 98 inches on' group 4. Actual unsafe DNBR or LPD conditions did not exist. Peak reactor power i during the transient was approximately 10E-2%, with startup rates in !
the range of 1.5 to 1.7. decades per minute. )
The licensee determined on April,13, following the trip, that the !
incorrect ECP was caused by incorrect xenon tables (used to predict the I reactivity worth of xenon) in the. Operations Physics Data Summary' Book.
Due to. improper administrative control of the ECP data, the xenon tables for cycle 1 operation were being usca instead of the tables required for cycle 2. Indications are that the licensed operator who was performing the t,tartup (i.e., supervising the trainee) also did not devote appropriate attention to availabie indications of approaching criticality and was not anticipating criticality "at any time" as directed by the approved procedure.
Following a post-trip review by the licensee and an appropriate addition of boron, Unit 3 started up later on April 13 and was operating at full power on April 14.
l On June 20, 1986, a Nati.:e of Violation was transmitted to the licensee '
for failure to closely monitor nuclear instrumentation and for failure to recognize the premature criticality.
86-1 Loss of Power and Water Hammer Event This abnornal occurrence involving San Onofre Unit I was originally reported ,
in NUREG 0090, Volume 9, No. 1. It is updated to provide significant updating l l eaterial.
San Onofre Unit 1 Yhe licensee and principal NRC staff members met with the Commissioners on June 12, 1986. The Commissioners reviewed the licensee's and staff's actions taken to analyze and correct the deficiencies that led to the i event. Principal ancng these actions was the development and i implementation of a Material Condition Review Program. The program was designed to define a suitable material standard for-systems and components in an older plant and to ensure that the material condition of those items was maintained.
, The NRC Office of Inspection and Enforcement issued an Information l
Notice to all nuclear power facilities on June 16, 1986. describing environmentally induced aging of an electrical power cable, the degradation of which contributed to the initiation of this event.
On June 25, 1986, the Region V Administrator visited the site to assess the material condition of Unit 1. Although minor deficiencies were identified, the Unit Condition was found to be greatly improved from what it had b$en prior to the November 21, 1985 event.
l l
l _ _ _ . _ _ _ _ _ ______________a
On July 13, 1986, the Regional Administrator concurred with the restart of Unit 1. The unit achieved criticality on July 15, 1986 in prepnation-for return to service. .
l This item is considered closed for purposes of reporting in this NRC document.
l l
i i
l 1.
1 l
)
Enclosure 2 l
Appendix C OTHER EVEWTS OF INTEREST l
- 1. Suspected Sabotage (Palo Verde Nuclear Generating Station).
On hay 14, 1986, beginning at approximately .B:59 pm, PDT, offsite power on 3 of 4 transmission lines was lost due to phase-to ground faults on each line. The power remained faulted through the evening until the afternoon of May 15, 1986. During the morning hours of May 15, the l licensee found that a rope or strap had been slung over the transmission I lines causing a phase to ground fault. The fault locations on each line 1 l was about 35 miles from the plant. l l
The transmission lines converge on the site frem 4 different directions. l l
The ground straps were far enough apart to require a coordinated effort l by several individuals to accomplish the power loss within a few minutes.
Unit I was in Mode 5 for a maintenance outage. Unit 2 remained in Mode 3 pending completion of the investigation of the event. Unit 3 was in the !
preoperational test phase, with no fuel in the reactor.
1 The licensee notified local law enforcement agencies and the TPI.
1 In accordance with Title 18, Section 1365 3US Code, the FBI (Phoenix l Office) assumed principal jurisdiction of this incident. They l coordinated their investigative efforts with the Maricopa County Sheriff's Office, the Arizona Department of Public Safety and NRC OI (Region V). The FBI continues to analvze physical evidence obtained at j each of the three areas. l The licensee has offered a $25,000 recard for " information leading to the arrest acd conviction of the person or persons responsible for the May 14 sabotage of three major high-voltage lines tied to the Palo Verde Nuclear Generating Station."
The event is of considerable concern because it was deliberate, coordinated sabotage by a group of people. In this event, there was no challenge to plant safety system because cffsite power remained available through the non-faulted transmission line. The plants were all designed to safely shutdown without any offsite power. However, until the saboteurs are apprehended, the potential for futurc challenges to the plant safety systems remains.
_ _ _ _ - _ - _ _ _ _ _ _ _