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Category:EXHIBITS (DOCKETING AND SERVICES BRANCH INFORMATION
MONTHYEARML20059D2431994-01-0707 January 1994 Package of Intervenor Exhibits Consisting of Related Correspondence Not Admitted Into Evidence.Related Correspondence ML20059M5291993-11-19019 November 1993 Applicant Exhibits A-21,A-22,A-24,A-25,A-26,A-29 & A-F1, Consisting of Related Correspondence Not Admitted Into Evidence.Related Correspondence IR 05000275/19910041993-08-24024 August 1993 Intervenor Exhibit I-MFP-70,consisting of Insp Rept,Re Rept Numbers 50-275/91-04 & 50-323/91-04,dtd 910304 IR 05000275/19930111993-08-24024 August 1993 Intervenor Exhibit I-MFP-26,consisting of Re Insp Repts 50-275/93-11 & 50-323/93-11 ML20059M7491993-08-24024 August 1993 Intervenor Exhibit I-MFP-T-2,consisting of 920422 Rev 4 to Procedure MP E-57.8 Temp Monitoring ML20059M7521993-08-24024 August 1993 Intervenor Exhibit I-MFP-T-3,consisting of 900227 Rept, Effects of Localized High Temps Upon EQ Components ML20059M7581993-08-24024 August 1993 Intervenor Exhibit I-MFP-T-3A,consisting of 900225 Table Re EQ Devices Affected by Localized High Temperatures ML20059M7601993-08-24024 August 1993 Intervenor Exhibit I-MFP-T-4,consisting of Rev O to MP E-57.8A, Temp Monitoring ML20059C7361993-08-24024 August 1993 Intervenor Exhibit I-MFP-88,consisting of NRC Insp of Diablo Canyon Units 1 & 2 ML20059D0841993-08-24024 August 1993 Intervenor Exhibit I-MFP-139,consisting of Insp Rept Re Dockets 50-275 & 50-323,dtd 920417 IR 05000275/19920131993-08-24024 August 1993 Intervenor Exhibit I-MFP-140,consisting of 920416,mgt Meeting Repts 50-275/92-13 & 50-323/92-13 ML20059D2241993-08-24024 August 1993 Intervenor Exhibit I-MFP-220,consisting of Protest of Util IR 05000275/19910061993-08-24024 August 1993 Intervenor Exhibit I-MFP-71,consisting of Rept of EC W/Util Mgt,Re Rept Numbers 50-275/91-06 & 50-323/91-06,dtd 910411 ML20059D2071993-08-24024 August 1993 Intervenor Exhibit I-MFP-193,consisting of Review of LER 1-90-015-00,re Docket 50-275,dtd 910118 ML20059M8621993-08-24024 August 1993 Intervenor Exhibit I-MFP-35,consisting of Rept, Self- Evaluation of Diablo Canyon Power Plant, Dtd Jul 1993 IR 05000275/19920161993-08-24024 August 1993 Intervenor Exhibit I-MFP-137,consisting of Insp Rept Re Dockets 50-275/92-16 & 50-323/92-16,dtd 920707 ML20059M5041993-08-24024 August 1993 Staff Exhibit S-2,consisting of Re Notice of Violation IR 05000275/19900291993-08-24024 August 1993 Intervenor Exhibit I-MFP-69,consisting of Insp Rept,Re Rept Numbers 50-275/90-29 & 50-323/90-29,dtd 910207 IR 05000275/19920171993-08-24024 August 1993 Intervenor Exhibit I-MFP-102,consisting of Insp Rept Re Dockets 50-275/92-17 & 50-323/92-17,dtd 920508 ML20059M1381993-08-24024 August 1993 Staff Exhibit S-1,consisting of Re 920519 Enforcement Conference IR 05000275/19920261993-08-24024 August 1993 Intervenor Exhibit I-MFP-118,consisting of Notice of Violation & Insp Rept Re Docket 50-275/92-26 & 50-323/93-26,dtd 921113 ML20059D2101993-08-23023 August 1993 Intervenor Exhibit I-MFP-196,consisting of Mgt Summary, DCO-91-MM-N067 D6, Asw Pump Vault Drain Check Valves, 910115 ML20059D1721993-08-23023 August 1993 Intervenor Exhibit I-MFP-168,consisting of Mgt Summary, Ncr DCO-91-EM-N009, FCV 495/496 Corrosion, ML20059D1841993-08-23023 August 1993 Intervenor Exhibit I-MFP-178,consisting of Mgt Summary, Ncr DCO-91-TR-N044, Maintenance Personnel Qualifications, ML20059D2031993-08-23023 August 1993 Intervenor Exhibit I-MFP-192,consisting of LER 1-90-015-01, Re Docket 50-275,dtd 910125 ML20059D1961993-08-23023 August 1993 Intervenor Exhibit I-MFP-191,consisting of Nonconformance Rept & Mgt summary,DCI-90-OP-N083, P-14 ESF Actuation Due to Valve Leakage, ML20059M5251993-08-23023 August 1993 Applicant Exhibit A-23,consisting of Rept DCO-93-TN-N006, DCM Maint & Testing Requirements ML20059M6071993-08-23023 August 1993 Applicant Exhibit A-28,consisting of Re LER 1-92-009-01 Involving Dose Limits Potentially Exceeded from Chemical & Vol Control Sys Valve Diaphragm Leakage Due to Thermally Induced Degradation ML20059D2181993-08-23023 August 1993 Intervenor Exhibit I-MFP-216,consisting of Nonconformance Rept & Mgt Summary DCO-90-SE N080,dtd 920128 ML20059D1871993-08-23023 August 1993 Intervenor Exhibit I-MFP-190,consisting of Mgt Summary, Ncr DC1-91-TN-N002, Backleakage Through Check Valve FW-1-531, ML20059D1821993-08-23023 August 1993 Intervenor Exhibit I-MFP-172,consisting of Mgt Summary, Rev 00,NCR DCO-91-MM-N049, Deg 1-3 Test Cock Valve, 911002 ML20059D2121993-08-23023 August 1993 Intervenor Exhibit I-MFP-210,consisting of Rept, SI-1-8805A, Failed to Cycle on Actuation Signal, ML20059C9651993-08-21021 August 1993 Intervenor Exhibit I-MFP-122,consisting of LER 2-91-007-00, Re Docket 50-323,dtd 911101 ML20059C9431993-08-21021 August 1993 Intervenor Exhibit I-MFP-117,consisting of LER 1-92-022-00, Re Docket 50-275,dtd 921030 ML20059C9571993-08-21021 August 1993 Intervenor Exhibit I-MFP-120,consisting of LER 1-92-013-00, ML20059D0701993-08-21021 August 1993 Intervenor Exhibit I-MFP-138,consisting of Nonconformance Rept, & Rev 00,NCR DC1-92-EM-N010,dtd 920729 ML20059C9871993-08-21021 August 1993 Intervenor Exhibit I-MFP-124,consisting of Technical Review Group Meeting Minutes Distribution, & 920124 DCI-91-TI-N047, Reactor Trip Due to Personnel Error & Safety Injection Due to Leaking Steam Dump Valves ML20059M5191993-08-21021 August 1993 Applicant Exhibit A-22,consisting of Responding to Violations Noted in Insp Repts 50-275/92-26 & 50-323/92-26 ML20059C9981993-08-21021 August 1993 Intervenor Exhibit I-MFP-127,consisting of LER 2-91-007-00, Re Docket 50-323,dtd 911101 ML20059C9901993-08-21021 August 1993 Intervenor Exhibit I-MFP-126,consisting of 911030, DC2-91-TI-N088 D2, Inadvertent SI Due to Personnel Error ML20059C9631993-08-21021 August 1993 Intervenor Exhibit I-MFP-121,consisting of 910503, Ncr DC1-OP-N038, Diesel Generator Start & Valve Actuation Due to Personnel Error, Mgt Summary ML20059C9841993-08-21021 August 1993 Intervenor Exhibit I-MFP-123,consisting of LER 1-91-009-00, Re Docket 50-275,dtd 910617 ML20059M5941993-08-21021 August 1993 Applicant Exhibit A-27,consisting of Responding to Violations Noted in Insp Repts 50-275/92-16 & 50-323/92-16 ML20059D0531993-08-21021 August 1993 Intervenor Exhibit I-MFP-136,consisting of Ncr DC1-MM-N028, Unit 1 Loss of Offsite Power - 910307, ML20059D1591993-08-21021 August 1993 Intervenor Exhibit I-MFP-154,consisting of LER 1-92-004-00, Re Docket 50-275,dtd 920520 ML20059D1301993-08-21021 August 1993 Intervenor Exhibit I-MFP-149,consisting of LER 1-91-006-00, Re Docket 50-275,dtd 910425 ML20059D0081993-08-21021 August 1993 Intervenor Exhibit I-MFP-129,consisting of LER 1-92-010-00, Re Dockets 50-275 & 50-323,dtd 921015 ML20059D1671993-08-21021 August 1993 Intervenor Exhibit I-MFP-155,consisting of LER 1-91-002-01, Re Docket 50-275,dtd 910517 ML20059D1461993-08-21021 August 1993 Intervenor Exhibit I-MFP-150A,consisting of Mgt Summary, Ncr DC1-90-WP-N093, Inadvertent Ground Causes CVI, ML20059D1421993-08-21021 August 1993 Intervenor Exhibit I-MFP-150,consisting of LER 1-90-019-00, Re Docket 50-275,dtd 910128 1994-01-07
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARDCL-99-123, Comment on Prs 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors & Draft NUREG-1022, Event Reporting Guidelines. Util Areas of Concern Includes ESF Actuations, Significantly Degraded Components & Historical Limitations1999-09-20020 September 1999 Comment on Prs 10CFR50 & 72 Re Reporting Requirements for Nuclear Power Reactors & Draft NUREG-1022, Event Reporting Guidelines. Util Areas of Concern Includes ESF Actuations, Significantly Degraded Components & Historical Limitations ML20205N4081999-04-14014 April 1999 Comments Opposing Proposed Rules 10CFR2,19 & 20 Re Proposed Repository at Yucca Mountain.Requests Information on How Much Radiation Being Released Now at Diablo & Hanford NPPs ML20205N4601999-03-21021 March 1999 Introduces K Schumann as Representative of Nuclear Waste Committee (Nuwic) of San Lius Obispo County.Informs That Nuwic & Nuclear Waste Management Committee Concerned with Transportation of Spent Nuclear Fuel Rods from Dcnpp ML20195E8841998-11-24024 November 1998 Petition for Mod to OLs to Require Plant Owner to Have Independent Contractor Evaluate Plant Safety Culture ML20236T3011998-07-24024 July 1998 Order Prohibiting Involvement in NRC Licensed Avtivities (Effective Immediately).Lh Brooks Prohibited for 5 Yrs from Date of Order from Engaging in NRC Licensed Activities ML20248C2261998-05-22022 May 1998 Comment Opposing Revised Proposed Rule 10CFR50 Re Protection & Safety Sys ML20129J4191996-10-18018 October 1996 Order Approving Application Re Corporate Restructuring of Pacific Gas & Electric Company by Establishment of Holding Company DCL-95-206, Comment Supporting Petition for Rulemaking PRM-50-61 Re Improving Fire Protection Regulations1995-10-0606 October 1995 Comment Supporting Petition for Rulemaking PRM-50-61 Re Improving Fire Protection Regulations ML20091P8721995-08-23023 August 1995 Comment Opposing Petition for Rulemaking PRM-50-61 Re Nuclear Energy Institute Proposed Amends on Fire Safety for All NPPs DCL-95-001, Comment on Proposed Changes to Reactor Pressure Vessel Integrity Rule 10CFR50.Endorses NEI Comments1995-01-0303 January 1995 Comment on Proposed Changes to Reactor Pressure Vessel Integrity Rule 10CFR50.Endorses NEI Comments ML20077M7521994-12-30030 December 1994 Comment Opposing Proposed Rule 10CFR50 Re Shutdown & Low Power Operation for Nuclear Power Reactors DCL-94-270, Comment on Proposed Rules 10CFR2,51 & 54 Re Rulemaking for NPP License Renewal.Endorses Comments & Changes Proposed by NEI 941208 Submittal1994-12-0808 December 1994 Comment on Proposed Rules 10CFR2,51 & 54 Re Rulemaking for NPP License Renewal.Endorses Comments & Changes Proposed by NEI 941208 Submittal ML20149H0851994-11-0404 November 1994 Initial Decision (Construction Period Recovery/Recapture).* Renewed Motion to Reopen Record 940808,denied.Served on 941104.W/Certificate of Svc ML20072L2651994-08-23023 August 1994 PG&E Opposition to San Luis Obispo Mothers for Peace Renewed Motion to Reopen Record.* Util Opposes San Luis Obispo for Peace Motion Based on Affidavit Stating No Evidence Found in Motion Re Flaw in Program.W/Certificate of Svc ML20072F0291994-08-12012 August 1994 Erratum to San Luis Obispo Mothers for Peace Motion to Reopen Record.* Intervenors Corrects Error in Renewed Motion to Reopen Record Re Application for License Amend to Extend Term of Operating License for Plant.W/Certificate of Svc ML20072B2651994-08-0909 August 1994 Comment Supporting Proposed Rule 10CFR26 Re FFD Requirements Concerning Random Drug Testing ML20072A5821994-08-0808 August 1994 San Luis Obispo Mothers for Peace Renewed Motion to Reopen Record Re PG&E Application for Amend to Extend Term of OL for Plant.* Motion to Reopen Record to Introduce Insp Rept Identifying Alleged Problems W/Plant.W/Certificate of Svc ML20071L2061994-07-26026 July 1994 Comment Supporting Proposed Rule 10CFR26 Re Changing Current Drug Testing Policies to Exclude All Personnel in nonsafety-related Positions ML20072B8481994-07-26026 July 1994 Comment Opposing Proposed Rule 10CFR26 Re Changes to FFD Requirements Concerning Random Drug Testing ML20071L1901994-07-20020 July 1994 Comments on Proposed Rule 10CFR26 Re Relaxing Rule on Drug Testing of Employees Working at NPP DCL-94-134, Comment Supporting Petition for Rulemaking PRM-50-60 Re Amend to 10CFR50.54 by Changing Frequency W/Which Each Licensee Conducts Independent Reviews of Emergency Preparedness Program1994-06-27027 June 1994 Comment Supporting Petition for Rulemaking PRM-50-60 Re Amend to 10CFR50.54 by Changing Frequency W/Which Each Licensee Conducts Independent Reviews of Emergency Preparedness Program DCL-94-135, Comment Supporting Petition for Rulemaking PRM-50-59 Re Proposed Amend to 10CFR50.54(p) Concerning Frequency W/Which Licensee Conducts Independent Reviews of Security Programs1994-06-27027 June 1994 Comment Supporting Petition for Rulemaking PRM-50-59 Re Proposed Amend to 10CFR50.54(p) Concerning Frequency W/Which Licensee Conducts Independent Reviews of Security Programs ML20064D1791994-03-0707 March 1994 Pacific Gas and Electric Co Reply in Opposition to San Luis Obispo Mothers for Peace Motion to Reopen Record.* Motion to Reopen Record Denied.W/Certificate of Svc ML20064D1961994-03-0404 March 1994 Affidavit of Mj Angus Re Motion to Reopen Record ML20063L5721994-02-25025 February 1994 San Luis Obispo Mothers for Peace Re Util Application for License Amend to Extend Term of Operating License for Plant.* Advises That Record of Proceeding Should Be Reopened to Consider Insp 93-36 Re Util Surveillance of Asw Sys DCL-94-021, Comment Supporting Petition for Rulemaking PRM-21-2 Re Commercial Grade Item Dedication Facilitation1994-01-26026 January 1994 Comment Supporting Petition for Rulemaking PRM-21-2 Re Commercial Grade Item Dedication Facilitation ML20059D2431994-01-0707 January 1994 Package of Intervenor Exhibits Consisting of Related Correspondence Not Admitted Into Evidence.Related Correspondence ML20062N0001993-12-30030 December 1993 PG&E Reply Findings of Fact & Conclusions of Law.* Mothers for Peace Proposed Findings & Conclusions Do Not Provide Any Supportable Rationale to Change Findings & Conclusions Previously Proposed by Pg&E.W/Certificate of Svc ML20058P3931993-12-22022 December 1993 NRC Staff Findings of Fact & Conclusions of Law in Form of Initial Decision.* Certificate of Svc ML20058K7491993-12-0202 December 1993 NRC Staff Motion for Extension of Time.* Board Has Extended Filing Time for Util Until 931230.W/Certificate of Svc. Served on 931206.Granted for Board on 931203 ML20058K8771993-12-0202 December 1993 NRC Staff Motion for Extension of Time.* Requests That Board Extend Date for Staff to File Findings Until 931222. W/Certificate of Svc ML20059M5291993-11-19019 November 1993 Applicant Exhibits A-21,A-22,A-24,A-25,A-26,A-29 & A-F1, Consisting of Related Correspondence Not Admitted Into Evidence.Related Correspondence ML20058E0741993-11-19019 November 1993 San Luis Obispo Mothers for Peace Proposed Findings of Fact & Conclusions of Law Re Licensee Application for License Amend to Extend Term of Operating License for Plant.* W/ Certificate of Svc ML20059E8931993-10-28028 October 1993 Memorandum & Order (Motion for Extension of Time).* San Luis Obispo Mothers for Peace 931018 Request for two-wk Extension of Time to File Proposed Findings of Fact & Conclusions of Law Granted.W/Certificate of Svc.Served on 931029 ML20059E8531993-10-27027 October 1993 NRC Staff Response to Board Memorandum & Order Re Extension of Time.* Staff Believes That San Luis Obispo Mothers for Peace Has Shown No Good Cause for Requesting Extension to File Proposed Findings of Fact.W/Certificate of Svc ML20059E8631993-10-25025 October 1993 Pacific Gas & Electric Co Response to Motion for Extension of Time.* Util Does Not Agree W/Board Assessment That Mothers for Peace Request Appears to Be Reasonable But Will Not Oppose Request.W/Certificate of Svc ML20059B2191993-10-19019 October 1993 Memorandum & Order (Responses to Motion for Extension of Time).* Board Believes Intervenor Request for Extension of Time to File Proposed Findings of Fact Appears Reasonable. W/Certificate of Svc.Served on 931019 ML20059B1071993-10-18018 October 1993 San Luis Obispo Mothers for Peace Motion for Extension of Time for Filing Proposing Findings of Fact & Conclusions of Law.* Requests Extension of Two Wks or Until 931119 to File Proposed Findings of Fact.W/Certificate of Svc ML20057D0531993-09-23023 September 1993 Notice of Appearance.* Notice Given That Undersigned Attorney Enters Appearance in Listed Matter & Listed Info Provided.W/Certificate of Svc ML20057B0401993-09-14014 September 1993 NRC Staff Reply to PG&E Response to Staff Motion to Amend Protective Order.* NRC Staff Moves Board to Adopt Language Requested in 930817 Motion as Stated.W/Certificate of Svc ML20056G4891993-08-30030 August 1993 Pacific Gas & Electric Co Response to Motion to Amend Protective Order.* Staff Asks That Protective Order Be Clarified by Adding New Footnote to Paragraph 3 of Order. W/Certificate of Svc ML20059C7361993-08-24024 August 1993 Intervenor Exhibit I-MFP-88,consisting of NRC Insp of Diablo Canyon Units 1 & 2 IR 05000275/19920161993-08-24024 August 1993 Intervenor Exhibit I-MFP-137,consisting of Insp Rept Re Dockets 50-275/92-16 & 50-323/92-16,dtd 920707 IR 05000275/19930111993-08-24024 August 1993 Intervenor Exhibit I-MFP-26,consisting of Re Insp Repts 50-275/93-11 & 50-323/93-11 ML20059M1381993-08-24024 August 1993 Staff Exhibit S-1,consisting of Re 920519 Enforcement Conference IR 05000275/19920131993-08-24024 August 1993 Intervenor Exhibit I-MFP-140,consisting of 920416,mgt Meeting Repts 50-275/92-13 & 50-323/92-13 ML20059D0841993-08-24024 August 1993 Intervenor Exhibit I-MFP-139,consisting of Insp Rept Re Dockets 50-275 & 50-323,dtd 920417 IR 05000275/19920261993-08-24024 August 1993 Intervenor Exhibit I-MFP-118,consisting of Notice of Violation & Insp Rept Re Docket 50-275/92-26 & 50-323/93-26,dtd 921113 ML20059M5041993-08-24024 August 1993 Staff Exhibit S-2,consisting of Re Notice of Violation ML20059M8621993-08-24024 August 1993 Intervenor Exhibit I-MFP-35,consisting of Rept, Self- Evaluation of Diablo Canyon Power Plant, Dtd Jul 1993 1999-09-20
[Table view] |
Text
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use. u /
' IN W I M ~. 172144 Pacific Gas and Electric Company $ g. f Qu,, 4E,
- ~
we-June 17, 1991 '93 GCT 28 P5 Z8 PG&E Letter No. DCL-91-154 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Re: Docket No. 50-275, OL-DPR-80 Diablo Canyon Unit 1 Licensee Event Report 1-91-009-00 Reactor Trip Due to Personnel Error and Safety Injection Due to Leaking Steam Dump Valves Gentlemen:
Pursuant to 10 CFR 50.73(a)(2)(iv) and 10 CFR 50.73(a)(2)(1)(B), PG&E is submitting the enclosed Licensee Event Report (LER) concerning a reactor trip resulting from personnel inadvertently satisfying reactor trip logic while performing surveillance testing. During the recovery from the reactor trip, the reactor coolant system was cooled at a rate greater than 100 degrees fahrenheit in any hour, in violation of Technical Specifications.
This event has in no way affected the health and safety of the public.
Sincerely,
,). D. Shif sL cc: Ann P. Hodgdon John B. Martin Phillip J. Morrill Paul P. Narbut Harry Rood NOCLEAR REGULATORY c0MMISSION
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LICENSEE EVENT REPORT (LER) ',
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- AcsLITv mam 0) oocarT sasot a f ri paw (3 DIABLO CANYON UNIT 1 0l5l0l0l0l2l7l5 1l' 7 l
ina o) REACTOR TRIP DUE TO PERSONNEL ERROR AND SAFETY INJECTION DUE TO LEAKING STEAM DUMP VALVES EDE N ' OAYE (,) LIA Inseta (6) Sep0RT Omit (7) .1 ME R F ACILifit, INv0LvtD (0)
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l On May 17,1991, at 0624 PDT, with Unit 1 operating at 100 per u..t power, a reactor trip occurred due to nuclear instrumentation power range two-out-of-four channels high flux at high setpoint signals. At 0625 PDT, a safety injection occurred due to two-out-of-four low pressurizer pressure signals. During the event, reactor coolant system cooldown exceeded the allowable rate of 100 degrees Fahrenheit per hour of Technical Specification 3.4.9.1.b. An Unusual-Event was declared at 0625 PDT on May 17, 1991. A one-hour emergency report required by 10 CFR 50.72(a)(1)(i) was made on May 17, 1991, at 0633 PDT.
The cause of the reactor trip was determined to be personnel error. An 1&C technician ,
, inadvertently deenergized a second nuclear instrumentation power range channel (N42) '
! while performing surveillance testing on another power range channel (N41). The cause
- of the safety injection was steam dump valves that failed open and overcooled the reactor coolant system.
Corrective actions for the event included: (1) temporary stoppage of all I&C work until i I&C personnel were tailboarded on the necessity of self-verification; and (2) l installation of switch and fuse covers on each channel to act as a physical barrier to '
present inadvertent actions.
Corrective actions for the steam dump valves will be discussed in Licensee Event Report 1-90-017-01.
5391S/0085K
1
( LICENSEE EVENT REPORT (LER) TEXT CONTINUATION 172144 ,
mu u n - m man mca m un => ma m l DIABLO CANYON UNIT 1 0l5l0l0l0l2l7l5 91 -
0l0l9 -
0l0 2l"l7 1(af (D)
- 1. Plant Conditions Unit I was in Mode 1 (Power Operation) at 100 percent power.
II. Description of Event A. Event:
On May 17,1991, at 0620 PDT, two In.,trumentation and Controls (I&C) technicians were performing Surveillance Test Procedure (STP) 1-20,
" Nuclear Power Range Incore/Excore Calibration," on nuclear instrumentation (NI)(IG) power range channel N41.. The instrument channel under test had the cabinet instrument drawer (IG)(PL) open.
The next step in the procedure required removal of the fuse (IG)(FU) for reconnection of that channel's signal and high voltage cables.
The technician who was to remove the fuse had previously manipulated the futa in that channel while the drawer was closed. The technician went to the instrument drawers and inadvertently pulled the fuse for NI channel N42, which had its drawer closed and was adjacent to channel N41. This resulted in the protection logic recognizing a two-out-of-four high flux at high power signal coincidence for a reactor (AB)(RCT) trip.
On May 17,1991, at 0624 PDT, with Unit I at 100 percent power, a reactor trip occurred due to the protection system two-out-of-four high flux at high setpoint signal coincidence, which initiated a main turbine (TA)(TRB) trip. Following the reactor and main turbine. trips, the condenser steam dump valves (SD")(SB)(V) automatically opened to prevent reactor coolant system (RCS)(AB) pressure and temperature increase. RCS pressure and temperature decreased and, to close the SDVs and mitigate the cooldown, a close signal was manuall; initiated.
Two SDVs,1-PCV-1 and 1-PCV-II, did not close following the close signal.
Control room operators entered Emergency Procedure E-0 . " Reactor Trip or Safety injection," and verified the automatic responses of the protection system.
One minute and 38 seconds after the reactor trip, RCS pressure and temperature had decreased sufficiently to result in a safety injection )
(SI) on two-out-of-four low pressurizer (AB)(PZR) pressure (s;1850 psig) signal coincidence. ,
l An Unusual Event (UE) was declared on May 17, 1991, at 0625 PDT, in I response to the SI. Due to previous experience with SDVs failing to close following actuation, operators quickly identified the malfunction. At 0627 PDT, on May 17, 1991, operators terminated the 53915/0085K
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION p21,44 ,
.xini, - m -.o -i. m u.-.. .m on
[
DIABLO CANYON UNIT I 0l5l0l0l0l2l7l5 91 -
0l0l9 -
0l0 3l"l7 IIII (37) cooldown by closing the main steam isolation valves (MSIV)(SB)(V) and MSIV bypass valves (SB)(V).
A one-hour emergency report required by 10 CFR 50.72(a)(1)(i) was made '
on May 17, 1991, at 0633 PDT. This report indicated that RCS pressure dropped from the normal operating pressure (NOP) of 2235 psig to 1640 psig and T,y, dropped from the normal operating temperature (NOT) of 574 degrees to 507 degrees. Subsequent analysis of recorded data determined that RCS pressure and temperature had reached as low as 1730 psig and 465 degrees T , exceeding Technical Specification 3.4.9.1.b.limitsforRCScoob,ingof100degreesinonehour.
On May 17, 1991, at 0800 PDT, operators returned Unit I to N0P and NOT, and stabilized the Unit in Mode 3 (Hot Standby).
B. Inrperable Structures, Components, or Systems that Contributed to the Event:
None.
C. Dates and Approximate Times for Major Occurrences:
- 1. May 17, 1991, at 0624 PDT: Event / discovery date. Unit 1 I
reactor trips when a second power l range rii channel is inadvertently l
deenergized by an I&C technician, which satisfies the two-out-of-four protection system logic for a t reactor trip.
- 2. May 17, 1991, at 0625 PDT: An 51 results due to RCS pressure decreasing caused by two SDVs
- leaking excessively following automatic open actuation and manual close signal. - A VE is declared.
- 3. May 17, 1991, at 0627 PDT: Operators manually close the MSIV and MSIV bypass valves to isolate the SDVs.
! 4. May 17, 1991, at 0633 PDT: A one-hour emergency report required by 10 CFR 50.72(a)(1)(i) was made.
! 5. May 17, 1991, at 0800 PDT: Unit I was stabilized in Mode 3 at NOP and NOT. !
53915/0085K
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION 172144' ,
- i , mon = m cmtv maata m m m nu m I DIABLO CANYON UNIT 1 0l5l0l0l0l2l7l5 91 -
0l0l9 -
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D. Other Systems or Secondary Functions Affected:
l Other than the two SDVs, all equipment functioned as intended to '
stabilize Unit 1 in Mode 3.
Valves 1-PCV-1 and 1-PCV-Il opened per design but, following closure l signal, failed to close. It was determined that the inner plug stem ;
of the valves separated from the mair stem, and resulted in excessive .
leakage through the valves. The' valve stem separation was the result of microwelding of the valve seat. Corrective actions being taken regarding the SDVs failure to close will be discussed in LER l-90-017-01.
E. Method of Discovery:
The reactor trip was immediately apparent to plant operators due to alarms and indications received in the control room. The cause of the SI (SDV failure) was apparent to the operators due to a recent similar l transient.
F. Operators Actions:
Operators verified the automatic functions of the protection system.
Operators closed the SDVs, but the cooldown' continued. Operators then closed the MSIV and MSIV bypass valves terminating the cooldown of the RCS. i G. Safety System Responses: ,
- 1. The reactor trip breakers (AA)(BKR)' opened.
- 2. The control rod urive mechanism (AA)(DRIV) allowed the control rods to drop into the reactor.
- 3. The main turbine tripped.
l 4. An SI signal was initiated on low pressurizer pressure, j 5. The 51 pumps (BQ)(P) started.
- 6. The residual heat removal pumps (BP)(P) started.
- 7. .The charging pumps (BQ)(P) started.
- 8. The motor-driven auxiliary feedwater (AfW) pumps'(BA)(MO)(P) ;
started per design.
- 9. Diesel Generators (EK)(DG) 1-1, 1-2, and 1-3 started, and per design did not load.
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III. Cause of the Event A. Immediate Cause:
An I&C technician, while performing surveillance testing on NI power range channel N41, inadvertently removed a fuse in NI power range channel N42.
B. Root Cause:
The root cause was determined to be personnel error (cognitive) in that the I&C technician did not perform self-verification. I&C policy, " Policy For Unit / Channel / Component Self-verification," dated June 30, 1988, requires that an individual verify his own action as correct prior to performing the action.
IV. Analysis of the Event A. Safety Analysis:
- 1. Reactor Trip and Safety Injection:
Impact to the departure from nucleate boiling ratio (DNBR) resulting from accidental depressurization of the RCS caused by secondary side depressurization is analyzed in Section 15.2.13 of the Final Safety Analysis Report (FSAR) Update. Accidental depressurization of the RCS is identified as a Londition II event (Faults of Moderate frequency). The overcooling and resulting depressurization of the RCS reported in this LER is bounded by the FSAR Update analysis, and therefore the minimum DNBR was not lower than 1.30 during this event.
- 2. Overcooling:
A Westinghouse engineering evaluation of the RCS considered the impact of the thermal transient upon the pressurizer, reactor vessel, RCS piping, the thick metal of the steam generators (AB)(SG), and the reactor coolant pumps (AB)(P).
Westinghouse reviewed temperature and pressure data and compared these with evaluations of similar transients at other plants and the evaluation performed for PG&E's December 24,_1990 rapid cooldown event (LER l-90-017-00). The' comparison showed that the DCPP Unit I rapid cooldown event is bounded by transients previously analyzed. The Westinghouse evaluation concluded that the above described DCPP Unit I transient did not adversely affect the structural integrity of the affected components and-system, and that the RCS could be returned to NOP and NOT and the unit restarted safely.
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V. Corrective Actions A. Immediate Corrective Actions:
- 1. The plant w4s stabilized in Mode 3.
- 2. An immediate, temporary I&C work stoppage was directed by management. I&C personnel were tailboarded on the necessity of self-verification.
B. Corrective Actions to Prevent Recurrence:
- 1. A temporary physical barrier has been installed over the NI l drawer face to prevent inadvertent operation of switches or fuse acti"ity.
- 2. A memorandum has been sent to Shift Control Technicians informing i them of the new temporary physical barriers and their use.
- 3. A design change will be implemented to install a permanent, removable physical barrier design for the NI drawers.
- 4. In addition to the self-verification training already part of the Maintenance Department training, additional self-verification training will be integrated into I&C laboratory performance training.
- 5. The technician involved in the event has been counselled as to the necessity for self-verification.
- 6. An INP0 video on self-verification practices will be presented to j I&C personnel during the quarterly update meeting.
VI. Additional Information A. Failed Components: '
Copes Vulcan valves 1-PCV-1 and 1-PCV-11, model D-100-160-3, eight inch. i B. Previous Similar LERs: l
- 1. ESF Actuations Due To Personnel Error:
LER l-91-005-00, " Actuation of Wrong Test Switch Causes Unplanned Diesel Generator Start (ESF) Actuation due to Personnel Error,"
describes an event wherein a non-licensed operator inadvertently l actuated the wrong Solid State Protection System (SSPS)(JG) test 53915/0085K
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DIABLO CANYON UNIT 1 0l5l0l0l0l2l7l5 91 -
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! switch resulting in an unplanned Emergency Diesel Generator l start, an ESF actuation. The root cause of this event was failure to follow self-verification policies. The corrective action did not prevent the most recent event reported in LER l-91-009-00 since the counselling was directed only at Operations personnel.
- 2. Condenser 40 Percent Steam Dump Valves:
LER l-90-017-00, dated January 23, 1991, reported a Unit 1 l reactor trip and SI due to a stuck open pressurizer spray valve.
I During this event, SDV l-PCV-1 leaked excessively following
! actuation. The corrective actions to prevent recurrence for this event dealt primarily with the stuck open pressurizer spray valve, which would not have prevented the contributory cause on the SDVs failure reported in LER l-91-009-00. The corrective actions to prevent SDV failure have identified but had not been completed on Unit I at the time of the May 17, 1991 reactor trip.
These corrective actions will be described in LER 1-90-017-01. i i
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