|
---|
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 ML20059M1381993-08-24024 August 1993 Staff Exhibit S-1,consisting of Re 920519 Enforcement Conference 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 ML20059D2241993-08-24024 August 1993 Intervenor Exhibit I-MFP-220,consisting of Protest of Util ML20059M8621993-08-24024 August 1993 Intervenor Exhibit I-MFP-35,consisting of Rept, Self- Evaluation of Diablo Canyon Power Plant, Dtd Jul 1993 IR 05000275/19920261993-08-24024 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 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 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 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 1999-09-20
[Table view] |
Text
- - - . .-. . .- . . . .
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GrcgoryM.Nueger l l Pacific G4iand Electric Company 77 Beate Siree!.FooinH51
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415t973-4684 Nutieat Power Generation A "
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'93 CCI 28 P6 :28 l June 24, 1993 m;- , y PG&E Letter No. DCL-93-159 we a j U.S. Nuclear Regulatory Commission !
~
ATTN: Document Control Desk
' Washington, D.C. 20555- l y :
Re: Docket No. 50-323, OL-DPR-C:
Diablo Canyon Unit 2 Licensee Event Report 2-93-004-01 . .
Technical Specification 3.9.12 Not Met When The Fuel Handling Building Ventilation System Was Inoperable During Fuel Movement Due To Programmatic Deficiency 1
Gentlemen:
PGaE is submitting the enclosed revision to Licensee Event. Report 2-93-004 pursuant to 10 CFR 50.73(a)(2)(i)(B) concerning the violation of Technical Specification 3.9.12 due to a blocked open personnel door causing a reduced negative pressure in the fuel handling building. This revision is being submitted to report the results of PG&E's root cause ;
investigation, corrective actions for this event, and minor editorial comments in other sections of this LER.
This event has in no way affected the health and safety of the public.
Sincerely,
, 4 A f wy --
i Gregory M. Rueger cc: Bobbie H. Faulkenberry Ann P. Hodgdon.
Mary H. Miller Sheri R. Peterson CPUC Diablo Distribution INP0 NuctEAR RECUT ATcRY COMMIS$l0N DC2-93-TP-N015 Enc 1osure vecw in : v.3 no cAcR$gA2LML 3@0-d% ~ rM m Q_:,w W& - M 6153S/85K/ALN/2246 n~
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LICENSEE EVENT REPORT (LER) TEXT CONTINUATION _
j FACIL.ITV NAME (1) DOCKET NUM6(R (2) LER NUMBER f6) PArat (3) 1
=
== = ]
DIABLO CANYON UNIT 2 0l5l0l0l0l3l2l3 93 -
0l0l4 -
0l1 2 'l 'l 7 ,
TERI (17)
I I. Plant Conditions Unit 2 was in Mode 6 (Refueling) at 0 percent power during this event. ]
II. Description of Event A. Summary:
1 On March 17, 1992, during the Unit 2 fifth refueling outage (2RS), at approximately 0800 PST, an ammonia /hydrazine leak occurred on the 100 foot elevation of the fuel handling building (FHB)(ND). During this time, insert (DB) shuffle was in progress in the Unit 2 spent' fuel-pool (SFP)(DB) and the FHB ventilation system (FHBVS)(VG) was in the iodine removal mode. At 1008 FST, Technical Specification ,
(TS) 3.9.12 was not met when a-FHB door was propped open to dissipate fumes. -
B.
Background:
Final Safety Analysis Report (FSAR) Update Section 9.4.4.1 indicates that the requirement for the design of the FHBVS-system is to remove-more air than is supplied so that all potential air leakages will be into and not out of the FHB. The FSAR Update assumes'that the spent fuel pool area is supplied with less air than is exhausted, thus creating a negative pressure with respect to ambient. A negative pressure assures that exfiltration from the area of a spent fuel handling accident would be through the FHB exhaust.
FSAR Update Section 9.4.4.2 indicates that the iodine removal mode of FHBVS operation is required when there is a potential for radioactive particulates and/or radioactive gases in the exhaust air of_ the FiiB and routes all exhaust air through roughing filters-(VG)(FLT), high efficiency particulate air filters (HEPA)(VG)(FLT), and activated charcoal filters (VG)(ADS). When not manually selected, the iodine removal mode of ventilation is automatically initiated by a radiation -
detector (VG)(DET).
Administrative Procedure (AP) C-66, " Control of Doors Important to l Safety," requires that an individual put into effect all compensatory I actions prior to impairing the function of any identified ventilation boundary door. In any situation where requirements are unclear, AP C-66 requires notification of the shift foreman (SFM) prior to impairing the function of a door. This procedure specifically addresses the loss of differential pressure maintenance function of FHB doors and suspension of concurrent fuel handling activities in the FHB. i I
6153S/85K
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION - ,,
i DOCKET NUMBER (,). L(R NUMBER i6) P Ar,E (3)
FCCILITV NANC (3)
DIABLO CANYON UNIT 2 0l5l0l0l0l3l2l3 93- -
0l0l4 -
0l1 3 l"l 7 j TEAT (17)
C. Event
Description:
On March 17, 1993, at approximately 0800 PST, an ammonia /hydrazine leak from a valve (KD)(V) used in.feedwater (SJ) ' chemistry control occurred on the 100 foot elevation of the FHB.- During this time insert shuffle was in' progress in' the Unit 2 SFP and the FHBVS was in the iodine removal mode.
To permit air sampling and to assist in the dissipation of-ammonia /hydrazine fumes, personnel door 258-2-(ND)(DR) was propped open at approximately 1008 PST. The SFM was informed of the open FHB door at 1015 PST. During the time the FHB door.was open.it was attended by Operations personnel.
On March 17,1993, at 1018 PST, the fuel handling senior reactor !
operator (SRO) checked the FHB pressure and determined it to;be _
approximately negative 0.10-inch H,0 (TS 3.9.12 requires a pressure '
l not less than negative 1/8-inch [0.125"] H,0). - Thus, Operations -
determined that the FHBVS was not in compliance with TS 3.9.12 and was inoperable. The fuel handling SRO immediately directed fuel handling.
equipment be placed in a safe configuration and informed the SFM. Thei insert shuffle was halted. The SFM recognized that the out-of-specification FHB pressure was a result of the FHB door being propped open.
l The FHB door was permitted to remain open until 1035 PST to decrease i the concentration of the ammonia /hydrazine fumes in the FHB to an acceptable amount, at which tinie the door was closed. - ;
_ On March 17,.1993, at 1040 PST, FHB pressure was determined to be
" negative 0.22-inch H,0 and the fnsert shuffle was re's'umed. -
~
During this event, from 1008 to 1018 PST, the FHB ventilation system was not considered inoperable by PG&E. operations' personnel since it l was believed that the FHB doors may be temporarily blocked open as long as they are attended. For this event, hazardous material response personnel were present the entire time the door was blocked ,
open.
D. Inoperable Structures, Components, or Systems that Contributed to the Event:
None.
E. Dates and Approximate Times for. Major Occurrences:
- 1. March 17, 1993, at 0730 PST: Insert shuffle commenced in the Unit 2 SFP pool with the ventilation system'in iodine i- 6153S/85K
i
)
6 LICENSEE EVENT REPORT (LER) TEXT CONTINUATION
> n a uiv = = m mcn* *a>=a m un ca m nu m DIABLO CANYON UNIT 2 Ol5l0l0l0l3l2l3 93 -
0l0l4 -
0l1 4l"l7
)
finT 07) removal mode (only one operable '
train of ventilation).
- 2. March 17, 1993, at 0800 PST: Ammonia /hydrazine leak occurred on the 100 foot elevation of the FHB..
- 3. March 17, 1993, at 100a PST: . Event date.. Door 258-2 was opened and attended, to assist in fume
- dissipation while insert shuffle was in progress.
- 4. March 17, 1993, at 1015 PST: SFM was-notified that the FHB door had been opened.
- 5. March 17, 1993, at 1018'PST: Discovery date. Fuel handling SRO checked the negative pressure in
.the FHB and found>it to be approximately negative 0.10-inch-H,0 (TS 3.9.12 limit is negative l
1/8-inch [0.125"] H,0) .
- 6. March 17, 1993, at 1021 PST: Fuel handling SR0 placed fuel handling equipment in a safe -
configuration.
- 7. March 17, 1993, at 1035 PST: Ammonia /hydrazine fume limits dropped to acceptable levels and '
door 258-2 was closed.
- 8. March 17, 1993, at 1037 PST: FHB nega61ve pressure was verified-to be negative 0.22-inch H,0.
- 9. March 17, 1993, at 1040 PST: Unit 2 insert shuffle in the SFP was resumed.
F. Other Systems or' Secondary Functions Affected: .
None. !
I G. Method of Discovery:
The'SFM, when informed that the FHB personnel door was open to mitigate the ammonia /hydrazine fume concentration in the FHB, directed.
the fuel handling SR0 to determine the FHB pressure. The fuel handling SRO confirmed that TS 3.9.12 limits had.been exceeded.
l 6153S/85K l
1
LICENSEE EVENT REPORT (LER). TEXT CONTINUATION maure - m acar =ta m "a ta + um ml.
DIABLO CANYON UNIT 2 0l5l0l0l0l3l2l3 93 -
0l0l4 -
0l1 5 l 'l 7 TEX (17)
H. Operator Actions:
The SFM was informed that the FHB door was opened while-insert l shuffling was .taking place. The fuel handling'SR0 observed FHB pressure to be less negative than rcquired by TS 3.9.12 and' halted SFP activities. Insert shuffle was resumed with the' concurrence of the-SFM when FHB pressure returned to an acceptable value.
I. Safety System Responses:
None required. -
III. Cause of the Event A. Immediate Cause:
The immediate cause of this event was maintaining FHB personnel door l 258-2 open, resulting in the TS 3.9.12 negative pressure limit being exceeded.
B. Root Cause:
PG&E has determined that1the root cause of'this event is-programmatic deficiency, in.that hazardous material response personnel were not aware that door 258-2 was a ventilation boundary for the FHB and the associated consequences of opening it.
IV. Analysis of the Event The 4el inserts were moved over spent fuel, so the potentiahfor. an x accident during this event did exist. In analyzmy the potential for fuel.
l handling accidents for FSAR Update cases, it is considered far more credible that a fuel assembly could be damaged by being dropped against a sharp edge rather than sustaining damage due to a dropped load while in the storage rack. Therefore, the " expected case" assumption of 17 damaged rods would conservatively bound the potential source term from a dropped insert l handling tool. The FSAR Update expected case also assumes decay of 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br />; the decay time during this event was in excess of 280 hours0.00324 days <br />0.0778 hours <br />4.62963e-4 weeks <br />1.0654e-4 months <br />. Thus,
! the possible source term was bounded by the existing.FSAR Update i assumptions.
The FHBVS has two modes of operation. The normal mode exhausts air through roughing and HEPA filters and Fan E-4 (VG)(FAN) without flowing through a charcoal filter. The iodine removal mode exhausts air'through roughing and HEPA filters and either Fan E-5 or E-6 with air flow also through. charcoal-filters. When not manually selected, the iodine removal mode of ventilation is automatically initiated by a radiation detector.
6153S/85K
t LICENSEE EVENT REPORT (LER) TEXT CONTINUATION -
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Since negative building pressure was maintained throughout the event, unfiltered leakage from the FHB would not have occurred. The results of charcoal absorbers testing indicated absorber efficiency was_ in excess of the assumptions used for FSAR Update. determination-of site boundary dose.
It may therefore be stated that the radiological consequences _of a load ' drop accident during this event would have been-conservatively. bounded by the FSAR expected case fuel handling accident'.
During this event, each time a door was opened.an operator was_present while the door was open. Operators recognize that FHB doors must be maintained closed if a radiation alarm occurs for the FHBVS. If an accident had occurred, the FHB radiation detector would have detected'any significant iodine activity and alarmed, alerting operators to close any open FHB doors.
~
The FHB exhaust air flow would have automatically shifted to the iodine ramoval mode (although during this event the FHB ventilation system was already in the iodine removal mode), and any iodine activity would have exhausted through the charcoal filters.
Therefore, the health and safety of the public were not adversely affected-by this event.
V. Corrective Actions A. Immediate Corrective Actions:
- 1. The leaking ammonia /hydrazine valve was isolated. 4
- 2. All fuel handling activities were suspended and the fuel handling equipment was placed in a safe configuration when FHB pressure was identified as out-of-specification.
- 3. FHB pressure was verified to be more negative than negative.
l 1/8-inch (0.125") H,0 prior to the resumption of the insert-shuffle.
- 4. An event summary was prepared and personnel were briefed'on this event and the necessity for awareness-of TS requirements during response to an incident.
B. Corrective Actions to Prevent Recurrence:
PG&E will enhance plant response procedures to clarify that- the SFM should be notified prior to keeping a ventilation boundary door open for more than personnel egress.
6153S/85K
LICENSEE EVENT REPORT (LER) TEXT CONTINUATION h
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DIABLO CANYON UNIT 2 0l5l0l0l0l3l2l3 93 -
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t VI. Additional Information A. Failed Components:
None. I B. Previous Similar Events:
LER 2-90-002, " Fuel Handling Building Ventilation System Inoperable During Fuel Movement Due to Programmatic Error" The corrective actions to prevent recurrence from this 1990 event 4 included the installation of. signs at FHB doors to remind personnel i that the doors were pressure boundaries for the FHB ventilation system. This corr ctive action wa effective, sinca each time the ,
door was. opened during the event of March'17, 1993, an. operator was-present so that the doors could be closed in the event.of:a radiation ;
alarm in the FHB. The fact that these doors'were ventilation ;
boundaries was identified, but it was not common knowledge to all !
plant personnel that blocking open the doors could result in exceeding.-
the FHB negative pressure limits.
)
6153S/85X