|
---|
Category:CONTRACTED REPORT - RTA
MONTHYEARML20203H8821998-09-30030 September 1998 Technical Evaluation Rept on Second 10-year ISI Program Plan:Entergy Operations,Waterford-3 Steam Electric Station ML20135E5841997-02-26026 February 1997 Revised, TER of IPE Submittal & RAI Responses for Waterford-3 Steam Electric Station ML20082S9371991-09-30030 September 1991 Trip Rept:Onsite Analysis of Human Factors of Event at Waterford 3 on 910624 (Manual Reactor Trip W/Excess Steam Demand) ML20082N0921991-06-18018 June 1991 Draft Assessment of Intersystem LOCA Risks - Methodology & Application:C-E Plant ML20070Q7671988-12-31031 December 1988 Nuclear Power Plant Sys Sourcebook,Waterford 3 ML20235C4721988-10-31031 October 1988 Pump & Valve Inservice Testing Program,Waterford Steam Electric Station,Unit 3 ML20148M0691988-03-31031 March 1988 Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at Waterford Unit 3 ML20236F7931987-09-30030 September 1987 Structural Adequacy of Waterford 3 Basemat, Technical Evaluation Rept ML20195G5451987-09-30030 September 1987 TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing Waterford Steam Electric Station,Unit 3, Technical Evaluation Rept ML20235L8431987-06-30030 June 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Waterford 3, Informal Rept ML20214Q9311987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Waterford-3, Informal Rept ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML20215N8071986-10-23023 October 1986 3 Emergency Preparedness Exercise on 861015 ML20215K4591986-09-30030 September 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Waterford Unit 3,Washington Nuclear Plant Units 1 & 3 ML20197C6021986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3,St Lucie Units 1 & 2 & Waterford Unit 3 ML20137Z3171985-10-21021 October 1985 Design Verification & Design Validation Audit of SPDS for Louisiana Power & Light Waterford Unit 3 ML20138N8441985-09-30030 September 1985 Dcrdr for Waterford Unit 3, Technical Evaluation Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20117C1881985-04-30030 April 1985 III Project I Rept, Informal Rept ML20113D2221985-01-0404 January 1985 Comments on Detailed Control Room Design Review Program Plan ML20107H7551984-07-18018 July 1984 Review of Waterford III Basemat Analysis ML20107H7321984-06-21021 June 1984 Review of Waterford III Basemat Analysis ML20107H6731984-04-16016 April 1984 Review of Waterford III Basemat Analysis ML20024B9571983-07-31031 July 1983 Draft DHR During Total Loss of Feedwater Event for C-E Sys 80 Plant. ML20076A7681983-05-31031 May 1983 Draft Control of Heavy Loads at Nuclear Power Plants, Waterford Generating Station,Unit 3,Louisiana Power & Lighting Co (Phase 1), Technical Evaluation Rept ML20112J4101983-03-31031 March 1983 Audit of Environ Qualification of Safety-Related Electrical Equipment at Waterford Steam Electric Station,Unit 3 ML20062A9371982-04-30030 April 1982 Control of Heavy Loads at Nuclear Power Plants,Waterford Generating Station,Unit 3, Draft Technical Evaluation Rept 1998-09-30
[Table view] Category:QUICK LOOK
MONTHYEARML20203H8821998-09-30030 September 1998 Technical Evaluation Rept on Second 10-year ISI Program Plan:Entergy Operations,Waterford-3 Steam Electric Station ML20135E5841997-02-26026 February 1997 Revised, TER of IPE Submittal & RAI Responses for Waterford-3 Steam Electric Station ML20082S9371991-09-30030 September 1991 Trip Rept:Onsite Analysis of Human Factors of Event at Waterford 3 on 910624 (Manual Reactor Trip W/Excess Steam Demand) ML20082N0921991-06-18018 June 1991 Draft Assessment of Intersystem LOCA Risks - Methodology & Application:C-E Plant ML20070Q7671988-12-31031 December 1988 Nuclear Power Plant Sys Sourcebook,Waterford 3 ML20235C4721988-10-31031 October 1988 Pump & Valve Inservice Testing Program,Waterford Steam Electric Station,Unit 3 ML20148M0691988-03-31031 March 1988 Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at Waterford Unit 3 ML20236F7931987-09-30030 September 1987 Structural Adequacy of Waterford 3 Basemat, Technical Evaluation Rept ML20195G5451987-09-30030 September 1987 TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing Waterford Steam Electric Station,Unit 3, Technical Evaluation Rept ML20235L8431987-06-30030 June 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Waterford 3, Informal Rept ML20214Q9311987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Waterford-3, Informal Rept ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML20215N8071986-10-23023 October 1986 3 Emergency Preparedness Exercise on 861015 ML20215K4591986-09-30030 September 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Waterford Unit 3,Washington Nuclear Plant Units 1 & 3 ML20197C6021986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3,St Lucie Units 1 & 2 & Waterford Unit 3 ML20137Z3171985-10-21021 October 1985 Design Verification & Design Validation Audit of SPDS for Louisiana Power & Light Waterford Unit 3 ML20138N8441985-09-30030 September 1985 Dcrdr for Waterford Unit 3, Technical Evaluation Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20117C1881985-04-30030 April 1985 III Project I Rept, Informal Rept ML20113D2221985-01-0404 January 1985 Comments on Detailed Control Room Design Review Program Plan ML20107H7551984-07-18018 July 1984 Review of Waterford III Basemat Analysis ML20107H7321984-06-21021 June 1984 Review of Waterford III Basemat Analysis ML20107H6731984-04-16016 April 1984 Review of Waterford III Basemat Analysis ML20024B9571983-07-31031 July 1983 Draft DHR During Total Loss of Feedwater Event for C-E Sys 80 Plant. ML20076A7681983-05-31031 May 1983 Draft Control of Heavy Loads at Nuclear Power Plants, Waterford Generating Station,Unit 3,Louisiana Power & Lighting Co (Phase 1), Technical Evaluation Rept ML20112J4101983-03-31031 March 1983 Audit of Environ Qualification of Safety-Related Electrical Equipment at Waterford Steam Electric Station,Unit 3 ML20062A9371982-04-30030 April 1982 Control of Heavy Loads at Nuclear Power Plants,Waterford Generating Station,Unit 3, Draft Technical Evaluation Rept 1998-09-30
[Table view] Category:ETC. (PERIODIC
MONTHYEARML20203H8821998-09-30030 September 1998 Technical Evaluation Rept on Second 10-year ISI Program Plan:Entergy Operations,Waterford-3 Steam Electric Station ML20135E5841997-02-26026 February 1997 Revised, TER of IPE Submittal & RAI Responses for Waterford-3 Steam Electric Station ML20082S9371991-09-30030 September 1991 Trip Rept:Onsite Analysis of Human Factors of Event at Waterford 3 on 910624 (Manual Reactor Trip W/Excess Steam Demand) ML20082N0921991-06-18018 June 1991 Draft Assessment of Intersystem LOCA Risks - Methodology & Application:C-E Plant ML20070Q7671988-12-31031 December 1988 Nuclear Power Plant Sys Sourcebook,Waterford 3 ML20235C4721988-10-31031 October 1988 Pump & Valve Inservice Testing Program,Waterford Steam Electric Station,Unit 3 ML20148M0691988-03-31031 March 1988 Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at Waterford Unit 3 ML20236F7931987-09-30030 September 1987 Structural Adequacy of Waterford 3 Basemat, Technical Evaluation Rept ML20195G5451987-09-30030 September 1987 TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing Waterford Steam Electric Station,Unit 3, Technical Evaluation Rept ML20235L8431987-06-30030 June 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Waterford 3, Informal Rept ML20214Q9311987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Waterford-3, Informal Rept ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML20215N8071986-10-23023 October 1986 3 Emergency Preparedness Exercise on 861015 ML20215K4591986-09-30030 September 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Waterford Unit 3,Washington Nuclear Plant Units 1 & 3 ML20197C6021986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3,St Lucie Units 1 & 2 & Waterford Unit 3 ML20137Z3171985-10-21021 October 1985 Design Verification & Design Validation Audit of SPDS for Louisiana Power & Light Waterford Unit 3 ML20138N8441985-09-30030 September 1985 Dcrdr for Waterford Unit 3, Technical Evaluation Rept ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20117C1881985-04-30030 April 1985 III Project I Rept, Informal Rept ML20113D2221985-01-0404 January 1985 Comments on Detailed Control Room Design Review Program Plan ML20107H7551984-07-18018 July 1984 Review of Waterford III Basemat Analysis ML20107H7321984-06-21021 June 1984 Review of Waterford III Basemat Analysis ML20107H6731984-04-16016 April 1984 Review of Waterford III Basemat Analysis ML20024B9571983-07-31031 July 1983 Draft DHR During Total Loss of Feedwater Event for C-E Sys 80 Plant. ML20076A7681983-05-31031 May 1983 Draft Control of Heavy Loads at Nuclear Power Plants, Waterford Generating Station,Unit 3,Louisiana Power & Lighting Co (Phase 1), Technical Evaluation Rept ML20112J4101983-03-31031 March 1983 Audit of Environ Qualification of Safety-Related Electrical Equipment at Waterford Steam Electric Station,Unit 3 ML20062A9371982-04-30030 April 1982 Control of Heavy Loads at Nuclear Power Plants,Waterford Generating Station,Unit 3, Draft Technical Evaluation Rept 1998-09-30
[Table view] Category:INCOMING CORRESPONDENCE
MONTHYEARML20217L0101999-10-18018 October 1999 Provides Update of Waterford 3 Effort for Review of Ufsar. Info Listed Includes Background Mgt Expectations,Review Status & Results,Clarifications Re Review & Conclusions ML20217L0141999-10-18018 October 1999 Submits Update to NRC Staff Re Circumstances & Plans for Submitting Certification Rept on Waterford 3 Plant Specific Simulator ML20217G7051999-10-14014 October 1999 Forwards Comments on Four of NRC RO Examination Questions for Exam Administered During Week of 991004 05000382/LER-1999-014, Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal1999-10-12012 October 1999 Forwards LER 99-014-00,providing Details of Reactor Shutdown Due to Loss of RCP Controlled bleed-off Flow.Attached Commitment Identification/Voluntary Enhancement Form Identifies All Commitments Contained in Submittal ML20217D5151999-10-0707 October 1999 Forwards Application for Renewal of SRO License for C Fugate License SOP-43039-3,IAW 10CFR55.57.Without Encls 05000382/LER-1999-013, Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form1999-09-23023 September 1999 Forwards LER 99-013-00,providing Details of Exceeding TS Limits for RCS Cooldown Rates.All Commitments Contained in Submittal Are Identified on Encl Commitment Identification/ Voluntary Enhancement Form ML20212C2391999-09-16016 September 1999 Requests Cancellation of SRO Licenses for Bn Coble,License SOP-43835,due to Job Assignment Location & CA Rodgers, License SOP-43537-1,due to Resignation from Company, Effective 990901 ML20212C2471999-09-16016 September 1999 Forwards Five Final Applications for RO Licenses for G Esquival,Jm Hearn,Md Lawson,Re Simpson & PI Wood.Written Exam & Operating Test to Be Administered,Is Requested. Encls Withheld ML20211P4121999-09-0707 September 1999 Requests NRC Staff Review & Approval of Integrated Nuclear Security Plan (Insp) & Integrated Security Training & Qualification Plan (Ist&Q), for Use by All Entergy Operations,Inc.Encl Withheld,Per 10CFR2.790(d) ML20211M8391999-09-0303 September 1999 Forwards Revised Epips,Including Rev 25 to EP-001-020,rev 24 to EP-001-030,rev 25 to EP-001-040,rev 30 to EP-002-100,rev 22 to EP-001-010,rev 27 to EP-002-010,rev 26 to EP-002-102 & Rev 16 to EP-002-190.Listed Proprietary Revs to Epips,Encl ML20211L3681999-09-0202 September 1999 Forwards Five Preliminary Applications for Reactor Operator Licenses for Individuals Listed,Iaw 10CFR55.31.Encls Withheld 05000382/LER-1999-011, Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form1999-08-31031 August 1999 Forwards LER 99-011-00,providing Details of Reactor Shutdown Due to Loss of Controlled bleed-off Flow.All Commitments Contained in Submittal Identified on Attached Commitment Identification/Voluntary Enhancement Form ML20211M3641999-08-30030 August 1999 Forwards Written Examination,Operating Tests & Supporting Ref Matl Identified in Attachment 2 of ES-210,in Response to NRC .Encl Withheld ML20211E3281999-08-26026 August 1999 Forwards fitness-for-duty Performance Data for Period of 990101-0630,IAW 10CFR26.71(d).Ltr Does Not Contain Commitments 05000382/LER-1999-010, Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form1999-08-26026 August 1999 Forwards LER 99-010-00,providing Details of Inadequate Pumping Capacity in Dry Cooling Tower Area.All Commitments Contained in Submittal Are Identified on Attached Commitment Identification Voluntary Enhancement Form 05000382/LER-1999-009, Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately1999-08-26026 August 1999 Forwards LER 99-009-00 Re Discovery of Condition of Noncompliance with App R Involving Inadequate Separation of Essential Cables Routed in Fire Area RAB-30 in Rab. Compensatory Measures Were Established Immediately ML20211F3561999-08-24024 August 1999 Forwards CTS Pages & TS Proposed marked-up Pages for Insertion Into TS Change Request NPF-38-207 Re Efas, Originally Submitted on 980702.Original NSHC Determination Continues to Be Applicable ML20211F5421999-08-24024 August 1999 Forwards Proposed marked-up TS Page Xviii, Index Administrative Controls, Correcting Page Number Re TS Change Request NPF-38-220.Editorial Changes for TS Change NPF-38-221 Discussed ML20211C5101999-08-19019 August 1999 Forwards Certified Copies of Liability Insurance Policy Endorsements Issued in First Half of 1999 for Each Entergy Operations,Inc Nuclear Unit,Per 10CFR140.15 ML20210Q6161999-08-12012 August 1999 Forwards Corrected Copy of Monthly Operating Rept for July 1999 for Waterford 3.Original Rept,Submitted with ,Contained Typos ML20210S0561999-08-12012 August 1999 Submits Voluntary Response to NRC AL 99-02, Operating Reactor Licensing Action Estimates, for NRC Fys 2000 & 2001 for Waterford 3 ML20217F2661999-08-12012 August 1999 Forwards Copy of 1999 Waterford 3 Biennial Exercise Package to Be Performed Using Waterford 3 CR Simulator 05000382/LER-1999-008, Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl1999-07-29029 July 1999 Forwards LER 99-008-00,re Failure to Perform Testing of ESF Filtration Units Per TS Srs.Commitments Made by Util Also Encl ML20210H4291999-07-29029 July 1999 Forwards Response to NRC Rai,Associated with TS Change Request NPF-38-208,proposing to Replace Ref to Supplement 1 with Ref to Supplement 2 of Calculative Methods for CE Small Break LOCA Evaluation Model, in ACs Section of TSs ML20210F9451999-07-27027 July 1999 Forwards Proprietary & non-proprietary Version of Rev 29 to EPIP EP-002-100, Technical Support Ctr Activation,Operation & Deactivation. Proprietary Info Withheld,Per 10CFR2.790 ML20210D3171999-07-23023 July 1999 Submits Proposal for Final Resolution of Reracking Spent Fuel Pool at Plant,Per License Amend 144,issued by NRC in .No New Commitments Are Contained in Ltr 05000382/LER-1999-007, Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached1999-07-23023 July 1999 Forwards LER 99-007-00,providing Details of Operation Outside Tornado Missile Protection Licensing Basis for turbine-driven Emergency Feedwater Pump Exhaust Stack & Steam Supply Piping.All Commitments Identified on Attached ML20209G9771999-07-13013 July 1999 Forwards Objectives & Guidelines for Waterford 3 Emergency Preparedness Exercise Scheduled for 991013.List of Objectives cross-referenced Where Applicable to Relevant Sections of NUREG-0654 ML20209D4051999-07-0707 July 1999 Forwards Revised TS Pages to Replace Attachment C,Entirely in Original TS Change Request NPF-38-207,per 990519 Discussion with C Patel of Nrc.Changes to Action 20 Delete Word Requirement & Revise Word Modes to Mode ML20209B6081999-06-30030 June 1999 Submits Response to NRC GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Disclosure Encl 05000382/LER-1999-005, Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits1999-06-24024 June 1999 Forwards LER 99-005-00,providing Details of Discovery of Untested Electrical Contacts in safety-related Logic Circuits ML20196G5731999-06-24024 June 1999 Forwards Operator Licensing Exam Outlines Associated with Exam Scheduled for Wk of 991004.Exam Development Is Being Performed in Accordance with NUREG-1021,Rev 8 ML20212J4121999-06-23023 June 1999 Responds to NRC Re Reconsideration of EA 98-022. Details Provided on Actions Util Has Taken or Plans to Take to Address NRC Concerns with Ability to Demonstrate Adequate Flow Availability to Meet Design Requirements ML20196E9371999-06-22022 June 1999 Forwards Revs Made to EP Training Procedures.Procedures NTC-217 & NTC-217 Have Been Deleted.Procedure NTP-203 Was Revised to Combine Requirement Previously Included in Procedures NRC-216 & NTC-217 ML20196A1021999-06-17017 June 1999 Provides Supplemental Response to GL 95-07, Pressure Locking & Thermal Binding of Safety-Related Power-Operated Gate Valves, Per 990513 Request of NRC Project Manager ML20195F3671999-06-0909 June 1999 Forwards Rev 21,Change 0 to EP-001-010, Unusual Event. Rev Reviewed in Accordance with 10CFR50.54(q) Requirements & Determined Not to Decrease Effectiveness of Emergency Plan ML20195C7801999-06-0303 June 1999 Submits Response to Violations Noted in Insp Rept 50-382/99-08.Corrective Actions:All Licensee Access Authorization Personnel Were Retrained Prior to Completion of Insp ML20195C2951999-05-28028 May 1999 Forwards Annual Evaluation of Changes & Errors Identified in Abb CE ECCS Performance Evaluation Models Used for LOCA Analyses.Results of Annual Evaluation for CY98 Detailed in Attached Rept,Based Upon Suppl 10 to Abb CE Rept ML20195C0241999-05-28028 May 1999 Notifies NRC of Operator Medical Condition for Waterford 3 Opertaor Sp Wolfe,License SOP-43723.Attached NRC Form & Memo Contain Info Concerning Condition.Without Encls ML20196L3281999-05-24024 May 1999 Informs That Entergy Is Withdrawing TS Change Request NPF-38-205 Re TS 3.3.3.7.1, Chlorine Detection Sys & TS 3.3.3.7.3, Broad Range Gas Detection Submitted on 980629 ML20206S4691999-05-17017 May 1999 Requests Waiver of Exam for SRO Licenses for an Vest & Hj Lewis,Iaw 10CFR55.47.Both Individuals Have Held Licenses at Plant within Past Two Year Period,But Licenses Expired Upon Leaving Util Employment.Encl Withheld 05000382/LER-1999-004, Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.31999-05-14014 May 1999 Forwards LER 99-004-00 Re Discovery That Response Time Testing Had Not Been Performed for ESFAS Containment Cooling Function,As Required by TS SR 4.3.2.3 ML20206N1921999-05-10010 May 1999 Provides Revised Attachment 2 for Alternative Request IWE-02,originally Submitted 990429 Re Bolt Torque or Tension Testing of Class Mc pressure-retaining Bolting as Specified in Item 8.20 of Article IWE-2500,Table IWE-2500-1 ML20206J1471999-05-0606 May 1999 Requests That Implementation Date for TS Change Request NPF-38-211 Be within 90 Days of Approval to Allow for Installation of New Monitoring Sys for Broad Range Gas Detection Sys ML20206J1721999-05-0606 May 1999 Notifies That Proposed Schedule for Plant 1999 Annual Exercise Is Wk of 991013.Exercise Objective Meeting Scheduled for 990513 at St John Baptist Parish Emergency Operations Ctr ML20206G8021999-05-0404 May 1999 Provides Revised Response to NRC Re Violations Noted in Insp Rept 50-382/99-01.Licensee Denies Violation as Stated.Change Made Is Denoted by Rev Bar & Does Not Materially Impact Original Ltr ML20206E7811999-04-29029 April 1999 Proposes Alternatives to Requirements of ASME B&PV Code Section XI,1992 Edition,1992 Addenda,As Listed.Approval of Alternative Request on or Before 990915,requested ML20205T2531999-04-22022 April 1999 Forwards LER 99-S02-00,describing Occurrence of Contract Employee Inappropriately Being Granted Unescorted Access to Plant Protected Area ML20205R2611999-04-20020 April 1999 Forwards Rev 19 to Physical Security Plan,Submitted in Accordance with 10CFR50.54(p).Plan Rev Was Approved & Implemented on 990407.Rev Withheld,Per 10CFR73.21 ML20205Q3241999-04-16016 April 1999 Submits Addl Info Re TS Change Request NPF-38-215 for Administrative Controls TS Changes.Appropriate Pages from New Entergy Common QA Program Manual Provided as Attachment to Ltr 1999-09-07
[Table view] Category:TEXT-PROCUREMENT & CONTRACTS
MONTHYEARML20203H8821998-09-30030 September 1998 Technical Evaluation Rept on Second 10-year ISI Program Plan:Entergy Operations,Waterford-3 Steam Electric Station ML20135E5841997-02-26026 February 1997 Revised, TER of IPE Submittal & RAI Responses for Waterford-3 Steam Electric Station ML20082S9371991-09-30030 September 1991 Trip Rept:Onsite Analysis of Human Factors of Event at Waterford 3 on 910624 (Manual Reactor Trip W/Excess Steam Demand) ML20082N0921991-06-18018 June 1991 Draft Assessment of Intersystem LOCA Risks - Methodology & Application:C-E Plant ML20070Q7671988-12-31031 December 1988 Nuclear Power Plant Sys Sourcebook,Waterford 3 ML20235C4721988-10-31031 October 1988 Pump & Valve Inservice Testing Program,Waterford Steam Electric Station,Unit 3 ML20148M0691988-03-31031 March 1988 Technical Evaluation Rept for Natural Circulation,Boron Mixing & Cooldown at Waterford Unit 3 ML20236F7931987-09-30030 September 1987 Structural Adequacy of Waterford 3 Basemat, Technical Evaluation Rept ML20195G5451987-09-30030 September 1987 TMI Action-NUREG-0737 (II.D.1) Relief & Safety Valve Testing Waterford Steam Electric Station,Unit 3, Technical Evaluation Rept ML20235L8431987-06-30030 June 1987 Final Conformance to Generic Ltr 83-28,Item 2.2.2 - Vendor Interface Programs for All Other Safety-Related Components: Waterford 3, Informal Rept ML20214Q9311987-04-30030 April 1987 Conformance to Generic Ltr 83-28,Item 2.2.1 - Equipment Classification for All Other Safety-Related Components: Waterford-3, Informal Rept ML20214R7431987-03-31031 March 1987 Rev 1 to Conformance to Item 4.5.2 of Generic Ltr 83-28, Arkansas Nuclear One-2,Calvert Cliffs 1 & 2,Fort Calhoun, Main Yankee,Millstone 2,Palisades,Palo Verde 1,2 & 3,San Onofre 2 & 3,St Lucie 1 & 2,Waterford 3 & WNP 3 ML20215G2741987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface Maine Yankee,St Lucie Units 1 & 2 & Waterford 3 ML20214R1531987-03-31031 March 1987 Conformance to Item 2.1 (Part 2) of Generic Ltr 83-28, Reactor Trip Sys Vendor Interface,Maine Yankee,St Lucie 1 & 2 & Waterford 3, Informal Rept ML20210Q4481987-01-0909 January 1987 Reactor Trip Sys Reliability Conformance to Item 4.5.2 of Generic Ltr 83-28,Arkansas Nuclear One Unit 2,Calvert Cliffs Units 1 & 2,Fort Calhoun,Maine Yankee,Millstone Unit 2, Palisades,Palo Verde Units..., Technical Evaluation Rept ML20215N8071986-10-23023 October 1986 3 Emergency Preparedness Exercise on 861015 ML20215K4591986-09-30030 September 1986 Conformance to Generic Ltr 83-28,Item 2.1 (Part 1) Equipment Classification (Reactor Trip Sys Components), Waterford Unit 3,Washington Nuclear Plant Units 1 & 3 ML20197C6021986-04-30030 April 1986 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3,St Lucie Units 1 & 2 & Waterford Unit 3 ML20137Z3171985-10-21021 October 1985 Design Verification & Design Validation Audit of SPDS for Louisiana Power & Light Waterford Unit 3 ML20138N8441985-09-30030 September 1985 Dcrdr for Waterford Unit 3, Technical Evaluation Rept ML20138C1941985-08-15015 August 1985 Rev 1 to Project & Budget Proposal for NRC Work: Evaluation of Selected NRC Open Items Before Plant Fuel Load ML20244D3871985-07-10010 July 1985 Review of Licensee & Applicant Responses to NRC Generic Ltr 83-28 (Required Actions Based on Generic Implications of Salem ATWS Events),Item 1.2, `Post-Trip Review:Data & Info Capabilities' for Bellefonte Nuclear Plant. ML20244D4381985-06-30030 June 1985 Conformance to Generic Ltr 83-28,Items 3.1.3 & 3.2.3, Dresden Units 2 & 3,Millstone Unit 1,Monticello,Pilgrim & Quad Cities Units 1 & 2. Contains Info for Dresden & Quad Cities ML20117C1881985-04-30030 April 1985 III Project I Rept, Informal Rept ML20113D2221985-01-0404 January 1985 Comments on Detailed Control Room Design Review Program Plan ML20107H7551984-07-18018 July 1984 Review of Waterford III Basemat Analysis ML20107H7321984-06-21021 June 1984 Review of Waterford III Basemat Analysis ML20107H6731984-04-16016 April 1984 Review of Waterford III Basemat Analysis ML20024B9571983-07-31031 July 1983 Draft DHR During Total Loss of Feedwater Event for C-E Sys 80 Plant. ML20076A7681983-05-31031 May 1983 Draft Control of Heavy Loads at Nuclear Power Plants, Waterford Generating Station,Unit 3,Louisiana Power & Lighting Co (Phase 1), Technical Evaluation Rept ML20112J4101983-03-31031 March 1983 Audit of Environ Qualification of Safety-Related Electrical Equipment at Waterford Steam Electric Station,Unit 3 ML20062A9371982-04-30030 April 1982 Control of Heavy Loads at Nuclear Power Plants,Waterford Generating Station,Unit 3, Draft Technical Evaluation Rept 1998-09-30
[Table view] |
Text
-
OBattelle Pacific Northwest Laboratories P.O. Box 999 Rahland, Nshington U.$A 99352 Telephone (509) 375-3782 Telex 15-2874 October 23, 1986 -
E Mr.' Charles Hackney N-U.S. Nuclear Regulatory Commission 'i OG 3 iin b)i tyg Region IV ,
611 Ryan Plaza Drive -
Suite 1000 Arlington TX 76011
Dear Charles:
WATERFORD-3 EMERGENCY PREPAREDNESS EXERCISE OCTOBER 15, 1986.
Enclosed is the final report of T.P. Lynch and A. K. Loposer who were the Pacific Northwest Laboratory (PNL) participants during the exercise. Only minor changes have been made to the drafts given to you prior to leaving the site. The areas covered by PNL include:
T.P. Lynch - Operational Support Center, H.P. Access Control Point ~
A.K. Leposer - Control Room If you have any question regarding this report please contact me on FTS (509) 375-3782 or T. P. Lynch on FTS (509) 375-3794.
Sincerely, u' 4M James D. Jamison Timot P. L ch Technical Leader Research Scientist Emergency Preparedness Group Emergency Preparedness Group Health Physics Technology Section Health Physics Technology Section HEALTH PHYSICS DEPARTMENT HEALTH PHYSICS DEPARTMENT JDJ/TPL:lem Enclosure cc: DB Matthews, w/ enclosure stA2588a! ge68jjg2 F
%%S ,s 9
Y(
V * .
WATERFORD-3 EMERGENCY PREPAREDNESS EXERCISE October 15, 1986 A. Name: Timothy P.. Lynch B. Assignment: Operational Support Center, Health Physics Ass'ess Control Point.
C. Site Personnel Contacted: B. Crawley, Training Instructor; R. Azzarello, Emergency Planning Manager; D. Landeche, Health Physics Supervisor;
' Jack Lewis, Emergency Planning Coordinator; S. Lubinski, Emergency Planner; W. Favaloro, Training Instructor.
D. Positive Observations:
e The OSC was activated in a timely manner.
> e Solutions to the inplant problems were aggressively pursued.
- Communications with the Control Room and TSC were good.
- Status boards for plant parameters and the inplant teams were kept up to date.
- Personnel accountability was effectively maintained.
1
a :s .
e The critiques at the H.P. control point and the OSC were good.
E. Negative Observations:
e : The inplant radiological conditions encountered by the majority of the
~
reentry teams did not challenge the health physics staff's. ability to pre-plan for an activity where personnel could receive a significant dose.
- The Emergency Team Briefing Sheets should allow for an approval signature by either the OSC supervisor or the Radiological Controls ' Coordinator.
Training should be provided for OSC personnel to ensure the forms are completely filled out.
e The telephones in the OSC should have an indicating light to facilitate identifying which phone is ringing.
- The use of headsets by communicators and reducing the volume of the P.A.
in the OSC supervisors office are recommend'ed due to the noise level during P.A. announcements in the OSC.
e The criterion for OSC activation ^ contained in EP-2-101 should be modified to reflect the minimum staffing levels contained in Table 5-1 of the Emergency Plan.
2
e A checklist should be developed for use by the OSC supervisor during activation of the OSC.
~
- A' continuous air monitor should be placed in operation in the OSC.
F .' Chronology:
Time Observation 0735 Arrive at the OSC l
07442 P.A. announcement that an. Unusual Event has been declared based on seismic activity.
0802 Repeat announcement on Unusual Event.
0837- P.A. announcement for declaration of Alert based on loss of both shutdown cooling trains.
0850 1-H.P.,.2 Chem. techs, 10 Mech., 5 Electricians and 3 I and C signed in on roster board.
0855 ~ OSC supervisor briefs staff.on plant conditions which includes the "A and "B" LPSI pumps 00S.
0900 Repair teams are briefed for work on pumps.
3
Time Observation 0905. John Megahay assumes duties of E. D. Communicators set up. P.A.
system loud especially in OSC supervisor's office. OSC checks with TSC to determine ~if other teams are inplant.
0910 TSC informed that "B" LPSI pump is operational and the "A" LPSI pump needs a weld repair and that a team is being dispatched.
0914 OSC supervisor declares the OSC operational and informs the TSC.
0918 Work' authorizations complete for the two repair teams. P.A.
announcement that both the OSC and TSC are activated.
0935 Team #1 returns to OSC.
0927 . Team #2 receives briefing for job to replace turbo charger on EDG "B".
0930 Radio check with repair team #2. Team #1 is debriefed. "B" LPSI pump is operational.
0940 Portable instruments (ion chamber,-G.M.)~in current calibration.
0944 Reactor trips, offsite power is lost and the "A" EDG fails to start.
An SAE is declared. Team #3 prepares to check seismic monitors and team #4 prepares for repair of diesel generator "A" output breaker, i
4 a
Time Observation 0950 SAE' announced over the-P.A'. Personnel told to report to their assembly areas.
1000 Document control and warehouse personnel report to OSC to afford access.to needed equipment and manuals or procedures.
1012 Rescue team readies to locate three persons not accounted for. Not needed, persons found, i-1015 Personnel accountability for repair teams is being maintained.
Inplant teams periodically call in to OSC.
1032 P.A. announcement that accountability is complete.
e l 1024 Offsite assembly point reports everyone accounted for and they have been surveyed for contamination.
f.
1037. Determination made that the EFAT responsibility has been assumed by the TSC and those persons are deleted from the security accountability log. Logs are being utilized by each of the phone l
communicators.
1050- Plant parameter data is being kept current on the status board.
5 4
7-
, _ . ., , - , _ _ _ _ , , . . . . , .,-_m., . . , _ ,. , , . - - . _ , _ , . , . . _ . - , - , . _ . . - -,=r,, , _ _ .. , . -.
N
" ' s N
Time Observation 1110 P.A. announcement that a G'eneral Emergency is declared based on ,
degraded core sequence and loss of feed water capability.
c.
1122 EFW pump repairs will take about twelve' hours - repo'rt to the TSC. '
Defeating interlocks will allow an intertie to be established i between the "A"'and'"B" buses which could provide LPSI power. '
s 1130 P.A. announcement that the EOF has been activated and the-E0F ,
director is Fred Drummond.
, . x, # <
r
s .,
1225 Arrive at the -4 H.P. control point. < k 1304 EFAT arrives at the -35 ft. elevation location of the victim.
~ 1.341 Outside on the west side of the RAB at door 27. Ambulance is covered with herculite for contamination control. Spoke with .
controller, Bob'Crawley, and he noted the drill inside the plant '
went well and the priority was the victims medical conditions and that good radiological practices were followed. .
1400 Review of the RWP and H.P. surveys. Maximum dose rates were $5
- R/hr.
1415 A review of the Emergency Team Briefing Sheets shows that reentry teams not originating in the OSC did not have a management approval 6
,w - , , , - - , - - - p 3 y, r* ev-
- .c : .
4 - Time Observation
- y signature as did the sheets for. teams from the OSC. The RCC should y,
- s. be added as on alternate.
- x-4
. 1450 Instruments e'-e source checked with a button source and acceptable range is taped on side of the instruments checked.
V.
1524 Exercise Termination. Attended critique at the H.P. control point.
The critique was comprehensive. Discussed the OSC performance with lead _ controller (Spence Lubinski). It. appears that a good job was done.
1 l
'I 1
' ';~ .
- i. +
'i g.
%. (
x
{':;Q
E
, o I
WATERFORD-3 EMERGENCY PREPAREDNESS EXERCISE October 15, 1986 t
I A. Name: A. K. Loposer 4
B. Assignment: Control Room
.s ,
C. Site Personnel Contacted: R.Azzarello,E.P.Manaher;M.Phillippe, Controller (Control Room); R. Pollock, Controller (Control Rcom);
- 0. Pipkins, Controller (Control Room); T. Brown, Shift Supervisor; M. Bourgeoise, Shift Supervisor; J. Luehman, NRC Senior Resident; J. Lewis, Controller (TSC).
D. Positive Findings:
- Control Room operators were professional and businesslike in their drill E performance. Their attitude was excellent and they " played the gane".
They utilized lull periods to brainstorm various options for corrective action and for accident mitigation.
e The operators made frequent reference to procedures and to piping and instrumentation diagrams (P&ID's). Their competency in the use of their procedures, and their familiarity with them,- reflected good training and practice.
e' A good infonnation _ turnover occurred when the Shift Supervisor was relieved as Emergency Coordinator, and this relief was clearly announced to Control Room personnel.
8
,_ 5
$?O .-
w- -
3y u
- ' Bound logs were used and were well kept.
e Operators' attempted to foresee problems and take early action. For example:
o
- 1. The' communicator reminded the Emergency Coordinator of the need for
.}.
the first 30 minute notification update about five minutes before it
{
was due.
- 2. A boronometer reading was requested just prior to isolating LETDOWN.
- 3. Safety Injection was anticipated and manually initiated about.one minute prior to the Safety Injection Activation signal (SIAS) being
$riggered automatically.
- The cooperation and accomodation between the regular shift personnel and ejercise shift personnel was excellent.
S-E. llegative Observations:
)
- One item of prompting was noted at 0748 when a monitor suggested to the i
communicator that "this would be a good time to try out your answering
~
system". Where the communicator' asked-the monitor if he should make a tape, the monitor indicated that he should. Whether or not the communicator would have taken this action without the prompt is unknown.
- Incident to notifications to parishes and state agencies, the communicator provided the telephone number for call-back verification.
1 Section 5.1.4.2 of EP-2-010, " NOTIFICATIONS AliD COMMUNICATIONS" states:
9 w - -
-- , ~
"...the receiver of the message should at their discretion call back and i
verify the validity of the message on the pre-established call back numbers provided to the agencies." When the communicator provides the number for call-back incident to this notification the validity of any-call-back verification is defeated.
- The leak / crack on the discharge piping from "A" LPSI pump was reported at 0820. The Emergency Coordinator did not' declare an ALERT until 0838, 18 ,
minutes later. This time appeared somewhat excessive.
. . A delay in accountability occurred when the Shift Supervisor was.
mistakenly led to believe that the Shift auxiliary operators who were out in the plant were not required to check in for accountability. The delay this created impacted adversely on achieving timely accountability.
e There was no radiological check point set up at the entrance to the Control Room /TSC area to guard against inadvertent contamination of those spaces by persons entering who may have become contaminated enroute. An arrangement similar to that used at the E0F would appear adequate.
F. Chronology:
Time Objective 0645 Initial conditions established.
10
o t Time Objective 0735 Seismic event message passed.
-0744 Shift Supervisor (S/S) declared notice of Unusual Event (N0VE).
4 0753 Completed initial notifications to St. Charles and St. John's Parishes and to Louisiana Office of Emergency Preparedness-(L0EP).
0758 Waterford Plants #1.and #2 notified.
0812 NRC(HQ)notificationcompleted.
0818 First update to state and parishes sent.
0820 Message on weld crack / leak on LPSI pump-"A" was passed.
0838 Emergency Coordinator (EC) declared ALERT.
'0841 S/S-des' ired to start shutdown /cooldown but.was deterred by controller in order to maintain scenario.
0844 Alert notification passed to parishes and state (L0EP and Louisiana Nuclear Energy' Division (LNED)).
~
0845 Word Passed directing personnel in emergency response facilities to key in to accountability card readers.
11
Time Objective 0838 Mr. MeGahay arrived Control Room preparatory to relieving as E.C.
0905 Mr. MeGahay relieved S/S as Emergency' Coordinator (EC).
0913 TSC infonned S/S that LPSI pump "B" was operable and surveillance completed. (This was incorrect, and was so reported to TSC by SS.).
0925 LPSI pump "B" operable 0940 Loss of off-site power message passed.
0945 Attempts to close the Emergency Diesel Generator (EDG) "A" output breaker were unsuccessful.
0950 EC (in TSC)' declared Site Area Emergency (SAE).
0956 E0F activation commenced.
1011 Successfully closed 00G tie breaker to "83" bus.
1018 Emergency Feed Water (EFW) pump "A" tripped-out as it was started.
1025 Letdown monitor in Hi-Alarm status.
1033 Accountability announced complete. Secured (isolated) letdown due to high activity.
12
Time -0bjective
-1054' "A/B" EFW pump overspeeds.
1059 Report received of 12 hrs. to repair bent stem on valve MS-416.
t
^
1103 EC declared General Emergency (GE).
1205 Unsuccessfully attempted to start EFW pump "A" - tripped on over d
current.
1 1216 Steam generators (SG) have boiled dry. CUE card #36 passed, showing that CVR - 201 indicates both open.and shut.
1224- Successfully started EFW pump "A". Pressurizer relief lifted -.did not-fully reseat.
1230 Operators manually initiated safety injection-due to decreasing reactor coolant system (RCS) pressure.
~1231 Safety injection activation signal (SIAS) received.
1257 Completed taking PASS sample.
1303 Terminated emergency boration.
1305 ~ Report of medical emergency.
- 13 i
_ . _ . _ - . . ~ . _ _ _ _ _ _ . _ -. . _ _ . _ _ _ . - . . _ . _ . . _ _ _ _ _ _ _ _ . _ . _ - . _
I
. Time Objective 1352 Repairs / attempts to shut CVR-201 still unsuccessful, i
1433 CVR-201 shut,' release terminated.
E' 1444 ' HPSI flow throttled to 300 GPM.
1524 ' Exercise terminatied.
(
- +
d 4
J f'
i 4
I d
f a
4
,s 4
+
14 j
1
. _ , . - . . . ...._._.._.--___.._.-....,m__ ~ , . . , _ , , _ , . ,.,.,.._,-.,~,_..--..~._.,_..-,.___-.._.,.._,,.,.m. -
ATTACHMENT 1~
OPEN~ ITEMS
- 1. (CLOSED) Open Item (382/8410-01). This item was reported completed by the licensee as of April 4,1984. Procedures EP-1-010, UNUSUAL EVENT; EP-1-020, ALERT; EP-1-040, GENERAL EMERGENCY; all contained box-notes specifying that the alarm is to be sounded prior to the P/A announcement.
Incident to the annual exercise' conducted on October 15, 1986, it was observed.that this practice.was correctly followed. The item is CLOSED.
- 2. (CLOSED) Open Item (382/8410-02). This item was reported completed by the licensee as of May 23, 1984. During the exercise conducted on October 15, 1986, it was observed that the volume of the site announcing system in the Shift Supert>isor and Communicator Station areas was adequate, the level of the volume in the main area of the Control Room seemed low. This volume was adjustable higher, but was set at the level preferred by the operators. The item is closed.
- 3. (CLOSED) Open Item (382/8410-03). The-licensee reported this item completed as of November 28, 1984. Incident to the annual exercise conducted on October 15, 1986, a check of procedures in use in the Control Room was.made. All procedures checked were noted to be CONTROLLED COPIES. The item is CLOSED.
- 4. (CLOSED) Open Item (382/8410-04) The licensee reported this item completed as of October 25, 1984. During the annual exercise conducted 15
on October 15,.1986, the NRC inspector observed the communicator prepare and insert ALERT tapes, and a shift to an information tape directing
-callers to the.TSC, after the TSC activated. The escalation to-SITE AREA EMERGENCY occurred after TSC activation, thus no observation of a shift of tapes from ALERT to SITE AREA EMERGENCY was available. The operation, as observed, was performed correctly. . The item is CLOSED.
- 5. (CLOSED) Open Item (382/8410-05). The licensee reported this item completed as of November 28, 1984. During the course of the annual exercise conducted on October 15, 1986, the SHIFT SUPERVISOR /EMERGEt!CY COORDINATOR conducted sufficient status briefings of his personnel to assure they were adequately informed. The item is CLOSED.
- 6. (CLOSED) Open Item (382/8410-24)- The inspector noted that procedure EP-2-101 specifies the assembly point for the Fire Brigade and the Emergency First Aid Team as the +7 ft. elevation. .It was noted during the exercise that the Search of Rescue Team assembled in the OSC and the Emergency First Aid Team assembled at the +7 ft elevation. The item is CLOSED.
- 7. (CLOSED) Open Item (382/8410-25) The inspector noted that procedure EP-2-101-instructs both the operations personnel and the Radiological Controls Coordinator to ensure that health physics coverage is provided for the Fire Brigade. Briefings given to the Search and Rescue Team in the OSC include'd having them report to the H.P. access control point at the -4 ft, elevation which they did. The item is CLOSED.
16
. - - . , - . - , , . , .-r , -- ~ , . - ,e , - - -
\
i
- 8. (CLOSED) Open Item (382/8410-26) The inspector noted that status board drawings of the +7 ft. elevation and several other locations in.both the reactor auxiliary building and the reactor containment building were available in the OSC. The item is CLOSED.
- 9. (CLOSED) Open Item (382/8410-27) :The. inspectors noted that procedure EP-2-060 includes an equipment inventory sheet. Kits were inventoried during the exercise using the checklist to account for the equipment.
The item is closed.
- 10. .(CLOSED) Open Item (382/8410-28) The inspector noted that the security / accountability desk was located near the entrance to the OSC during the exercise. The item is CLOSED.
- 11. (CLOSED) Open item (382/8410-29) ~The inspector noted that the OSC roster board has been divided into several sections which included electrical, mechanical, health physics, instrumentation and control, operation's, chemistry and other. The item is CLOSED.
- 12. (CLOSED) Open Item (382/8410-30) The inspector noted that procedure EP-2-034 requires surveys of occupied areas onsite such as the OSC and E0F. The OSC locker contained equipment and instrumentation needed for measuring dose rates, taking of air samples and analyzing air samples.
The item is CLOSED.
17
- 13. (CLOSED) Open Item (382/8525-01). The licensee reported that corrective action for this item had'been completed as of December 30, 1985. During the annual exercise conducted on October 15, 1986, the NRC inspector noted that this requirement is supported in each of the procedures for the four emergency classifications, specifically, EP-1-010, 020, 030, and 040. It was further observed during the exercise that notification of NRC-Headquarters was completed (for the NOVE) at 0812, 31 minutes following the declaration of the NOUE at 0741. No further notifications
.were made (per NRC-HQ request) until exercise termination. The' item is CLOSED.
- 14. (CLOSED) Open Item (382/8525-02). The licensee reported that corrective act' ion (procedure revisions) would be completed as of March 3, 1986. A review of the four emersency classification procedures, EP-1-010, 020, 1 030, and 040, confirmed that these procedures now reflect adequate support for providing periodic updates to state and local agencies at regular intervals, nominally 30 minutes. Observations during the annual exercise conducted on October 15, 1986, substantiated that periodic updates were provided. The item is CLOSED.
i
- 15. Improvement Items listed in Report 50-382/85-25 were reviewed with the I
following observations:
- The' communicator's telephone was located in an area accessible to him.
However, there was not a dedicated instrument for the HOT LINE. Rather, the H0T LINE was one of six lines available on that instrument.
18 -
L
- The Shift Supervisor was observed making some degree of use of other station personnel in filling out forms, etc. In any case, such duties as he did retain himself did not appear to degrade or dilute the performance' of his primary duties.
- The Resource Book was reviewed and found to contain a note alerting communicators that the Louisiana Nuclear Energy Division (LNED) telephone number shown is for normal working hours, with . supplementary information regarding off-hours notification of LNED to be done by Louisiana Office of Emergency Preparedness (L0EP). A discussion with the assigned communicator confirmed his understanding of this arrangement.
e- The communicator assigned in'the Control Room to make the state and local notifications also performed the 10 CFR 50.72 communication requirement.
This kept him very busy, but in this instance he was able to complete. all required notifications as specified.
19
ATTACHMENT 2 EXERCISE SCENARIO The exercise scenario was reviewed to determine if provisions had been made to exercise the-licensee's emergency preparedness organization in accor-dance with the requirements of 10CFR 50 Appendix E-Section F and the guidance contained in NUREG 0654 Section 11.n. The review included an evaluation'of
..the adequacy of both the operational and radiological aspects of the scenario.
. Specific areas reviewed included the objectives, controller messages, plant-parameter data, sequence of events, onsite and offsite radiological data. The results of the review are as follows:
- The scenario contained a narrative summary of everits which occurred and the rationale behind the events;
- Scenario messages were adequate to maintain the scenario timeline; e The plant parameter data and radiological data were adequate to support the sequence of events;
- The scenario challenged the operations personnel's capability for emergency detection, classification and subsequent notifications.
OPERATIONAL SUPPORT CENTER The Operational Support Center (OSC) was activated in a timely manner.
Solutions to problems in the plant were pursued aggressively and effective use of the OSC resources was demonstrated. Status boards were maintained with the current conditions. Communication with the control room and the TSC were very good however the noise icvel during PA announcements was excessive. Personnel 20
c accountability in the OSC was effectively maintained. Reentry teams were briefed on the radiological conditions that could be anticipated.
The following are recommended improvement items:
e The inplant radiological conditions encountered by the majority of the reentry teams did not challenge the health physics staff's abi'.ity to pre-plan for an activity where personnel could receive a significant dose. Future health physics drill scenarios should contain radiological conditions that will challange the health physics staff.
- The Emergency Team Briefing Sheets should allow for an approval signature by either the OSC Supervisor or the Radiological Controls Coordinator.
Training should be provided for OSC personnel to ensure the forms are filled out completely.
- The telephones in the OSC should have an indicating light to facilitate identifying which phone is ringing.
- The use of headsets by communicators and reducing the volume of the P.A.
system in the OSC supervisors offices are recommended due to the noise level during P.A. announcements in the OSC.
-e The criterion for OSC activation contained in EP-2-101 should be modified to reflect the minimum staffing levels contained in Table 5-1 of the Emergency Plan.
21
e A checklist should be developed for use by the OSC supervisor during activation of the OSC.
- A continuous air monitor should be placed in operation in the.0SC.
No violations or deviations were identified.
CONTROL ROOM Initial conditions were provided to the control room staff assigned as exercise participants at 0645, and included the following:
- a. The plant had been operating at an almost constant 100% power for the past 30 days after a refueling outage.
- b. "A/B" charging pump was out of service due to severe packing gland leaks.
Packing on order,
- c. "A/B" HPSI pump out of service due to bearing failure. . Expect replacement parts 10/16/86.
- d. "B" Emergency Diesel Generator out of service due to a turbo-charger bearing failure.
- e. "A" Emergency Feedwater Pump'was operable, but operating in the " alert" range for vibrations.
- f. "B" LPSI Pump out of service for oil change and lubrication; surveillance expected to complete by about 0930.
The exercise began at 0735 when a seismic event was felt in the plant and corroborated by a seismic _ event alarm actuation and by the Strong Motion Accel-22
erograph system showing the yellow event alann illuminated. The licensee de-clared a Notification of Unusual Event and made the appropriate notifications, while at the same time initiating a plant walk-down for damage assessment.-
The walk-down revealed, at about 0820, that the discharge piping on the "A" Low Pressure Safety' injection (LPSI) Pump had been cracked and the leakage had sprayed onto the pump motor. A weld repair was required, and in the interim
.both LPSI pumps would be out of service. As a result the licensee declared an ALERT at 0838. Again, notifications were made.
Another casualty of the earthquake, but not observable during the walk-down, was the containment vacuum relief isolation valve, CVR 201, which moved of f its seat but continued to indicate closed on the Reactor Control Panel. Th>t breach of containment did not become evident until later in the exercise.
The Technical Support Center (TSC) was activated and the Shift Supervisor (S/S) relieved as Emergency Coordinator (EC) at 0905.
The "B" LPSI pump was returned to service at 0925, but at 0940 a total loss of AC power occurred, commencing with a loss of off-site power and compounded by failure of the "A" Emergency Diesel Generator output breaker to close after the diesel started. A station black-out resulted and at 0950 the licensee declared a SITE AREA EMERGENCY.
i At 1011 the "A" Emergency Diesel Generator output breaker was closed which restored power to some systems and components.
At 1018 the Emergency Feed Water (EFW) pump "A" was reported failed; at 1054 the "A/B" EFW Pump overspeed and tripped. With levels dropping in both steam generators the licensee declared a GENERAL EMERGENCY at 1103 based on a degrading core sequence and loss of all feedwater capability. Subsequently 23
both steam generators boiled dry about 1216 and Reactor Coolant System (RCS) i pressure commenced increasing. At 1225, almost simultaneously with restoration and restart of A" EFW Pump, the pressurizer relief valve lifted, then failed to reseat.
At'about 1230 the quench tank rupture disk ruptured, relieving the quench tank to containment atmosphere, then through the previously described failed containment vacuum relief valve, and the Shfeld Building Ventilation System to atmosphere. This release continued until the containment vacuum relief valve was closed at 1433.
With "A" EFW Pump operating and feeding a steam generator, a controlled cooldown was initiated.
At about 1305 a medical einergency occurred, a simulated heart attack and subsequent' contamination. The injured victim was administered emergency first aid and evacuated to West Jefferson General Hospital where he was treated and decontaminated.
With the release terminated the basic exercise was terminated at 1524. A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> time jump was' simulated and recovery planning was conducted.
The NRC inspectors observed that control room personnel consulted appropriate (CONTROLLED COPY) procedures for the events. Initial notifications to the Louisiana Office of Emergency Preparedness (L0EP) and to both Parishes were made within 15 minutes after the events were classified.
Subsequent follow-up~ notifications were made as specified in the procedures.
Initial notification to NRC Headquarters was at 0812, 31 minutes after NOUE classification. Control Room operators exhibited professionalism, an excellent attitude, and good foresight. Bound logs were used and were well-kept.
24
r
'The following improvement items are recommended:
- When notifications are nade to Parishes and state agencies the communi-cator should exercise care to differentiate between the pre-established call back numbers, and a number which can be used for obtaining aupli-fying information in the event the dedicated hot line is lost or that additional information is required. Communicators should be instr ucted not to refer to a number provided as a " verification" or " validation" call back number. If an agency desires to validate a suspected bogus call they should use the number previously provided to them.
- Make procedural provisions for establishing a radiological check point at the entrance to the CONTROL ROOM /TSC area to guard against contamination of those areas by persons entering who may have become contaminated enroute. An arrangement similar to that used at the EOF would appear adequate.
.The following negative observations were made:
o The leak / crack on the discharge piping from "A" LPSI Pump was reported at 0820. The Emergency Coordinator did not declare an ALERT until 0828, 18 minutes later. This time delay appeared excessive.
e One item of prompting was noted at 0748 when a monitor was heard to suggest to the communicator that "this would be a good time to try out your answering system". When the communicator asked the monitor if he should make the tape the monitor indicated that he should. Whether or not the communicator would have taken this action without the prompt is unknown.
- A minor delay in accountability occurred when the Shift Supervisor was mistakenly led to believe that the shift Nuclear Auxiliary Operators who 25
V were out in the plant were not required to check in for accountability.
The delay this created impacted adversely on achieving timely accountability. (0BJECTIVE A.1.q. refers).
No violations or deviations were identified.
26
.. . . -