Letter Sequence Approval |
---|
|
|
MONTHYEARML20206H1291986-06-17017 June 1986 Clarifies Flow Path Requirements & Acceptable Independence Requirements for RHR Subsystems Per LER 86-03.Plant Meets Limiting Condition for Operation 3.5.2.e If Valves MO-8809 a & B & MO-8812 Locked Open in Modes 1-3 Project stage: Approval ML20210V1941986-09-25025 September 1986 Informs of Results of RCS Thermal Expansion Monitoring Performed During Wk of 860902.Measurements Acceptable.Data Will Be Taken When RCS Temp Reaches 340 F,In Lieu of Holding Temp at 340 F for Analysis & Evaluation Project stage: Other ML20236A0111986-10-15015 October 1986 Notice of Violation & Proposed Imposition of Civil Penalty in Amount of $50,000.Noncompliance Noted:Portions of Two ECCS Subsys Inoperable When Valve MO-8809A Closed & QC Inspector Failed to Follow Procedures Project stage: Other ML20235Z7871986-10-15015 October 1986 Discusses Insp on 860318-0428 & Two Special Insps on 860513- 0612 & 860804-14 & Forwards Notice of Violation & Proposed Imposition of Civil Penalty Project stage: Other ML20214F5771986-11-14014 November 1986 Responds to NRC Re Violations Noted in Insp Repts 50-344/86-10,50-344/86-24 & 50-344/86-32.Corrective Action: New QA Training Procedure Developed.Payment of Proposed Civil Penalty in Amount of $50,000 Also Encl Project stage: Other 1986-11-14
[Table View] |
|
---|
Category:INTERNAL OR EXTERNAL MEMORANDUM
MONTHYEARML20217D1071999-09-16016 September 1999 Provides Proposed Schedule for Review of Trojan License Termination Plan (Ltp),As Committed in 990903 Memo.Project Manager Should Schedule LTP Meeting Near Trojan Site for Late Nov or Early Dec,Based on Region IV Availability ML20216E4091999-09-0303 September 1999 Informs That Staff Has Performed Acceptance Review of Trojan Nuclear Plant License Termination Plan Submitted by Ltr Dtd 990805.NMSS Determined That Licensee Has Provided Sufficient Info for NRC to Proceed with Detailed Review ML20205R4091999-04-16016 April 1999 Informs That LTP for Trojan Nuclear Plant Did Not Provide Sufficient Info to Perform Detailed Review & Waste Mgt Recommends Returning LTP to Licensee So That LTP Can Be Resubmitted as Complete Application ML20195B6401998-11-10010 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Preliminary Plans for Plant Final Site Surveys ML20155G6571998-11-0303 November 1998 Notification of 981119-990331 Meeting with Util in Rockville,Md to Clarify Remaining Technical Issues Associated with Util Application for License to Operate ISFSI at Tpp ML20236S5361998-07-22022 July 1998 Notification of 980812 Meeting W/Portland General Electric in Arlington,Texas to Discuss Status of Decommissioning Activities at Trojan NPP ML20236R6931998-07-15015 July 1998 Notification of 980730 Meeting W/Util to Discuss Request for Addl Info Re Ongoing Review of Portland General Electric Co Request for Approval to Allow one-time Shipment of Trojan Decommissioned Reactor Vessel.Meeting Agenda Encl ML20236R6511998-07-15015 July 1998 Notification of 980730 Meeting W/Listed Participants in Kelso,Wa Re Proposed Request from Portland General Electric Co for Approval to Allow one-time Shipment of Plant Decommissioned Reactor Vessel.Meeting Agenda Encl ML20248L4691998-03-17017 March 1998 Notifies of in-house Research Project Re Digital I&C in NPP & Forwards Technical Training Div (TTD) ML20216E7421998-03-0606 March 1998 Notification of 980318 Meeting W/Portland General Electric in Rockville,Maryland to Discuss Proposed Shallow Land Disposal of Trojan Reactor Vessel ML20199D4951998-01-26026 January 1998 Notification of Licensee Meeting W/Util on 980209 in Arlington,Tx to Discuss Changes to Protected Area for Plant to Facilitate Ongoing Decommissioning of Site ML20199G1121998-01-20020 January 1998 Submits Addl Views on Proposal to Dispose of Trojan Reactor Vessel,Per SECY-97-244 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20141G2911997-05-15015 May 1997 Forwards Page A-25 of Rev 5 to PGE-1060, Tnp Permanently Defueled Emergency Plan ML20137W9801997-04-16016 April 1997 Notification of Significant Licensee Meeting W/Util on 970508 in Rockville,Md to Discuss Plans for Decommissioning of Plant ML20137H2231997-03-31031 March 1997 Forwards Info in Support of Pnl Modeling for Fgeis Final Rule on Radiological Criteria for License Termination ML20135B1941997-01-30030 January 1997 Responds to Re Util Position Re Potential for Ash Fall at Trojan Site ML20138J2731997-01-21021 January 1997 Submits Comments on 970113-16 QA Insp of Sierra Nuclear Corp in Scott Valley,Ca ML20134B6001997-01-13013 January 1997 Provides Meeting Minutes from NRC Insp 97-201 Exit Meeting Re Insp of Trojan'S QA Program for Isfsi,From 970107-09 ML20133N2821997-01-0808 January 1997 Requests Comments on Poge Position Re Potential for Ashfall at Trojan Site ML20135B8581996-12-0303 December 1996 Requests Guidance on Use of 10CFR71.41(c) Per Licensee Request for Authorization to Transport Reactor Vessel as Type B Package ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20237F1891996-01-22022 January 1996 Notification of 960131 Meeting W/Util in Rockville,Md to Discuss Planned Removal of Plant Pressure Vessel ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20057B6071993-09-16016 September 1993 Notification of 930928 Meeting W/Util in Rockville,Md to Discuss Status of Decommission Activities & Physical Security ML20057A6651993-08-27027 August 1993 Forwards Notice of Consideration of Issuance of Amend to License NPF-1 & Proposed NSHC Determination & Opportunity for Hearing ML20056E5331993-08-16016 August 1993 Notification of 930901 Mtg W/Util & State of or in Rainier, or to Discuss Proposed Studies of Plant Sys at Plant ML20056E4451993-08-0606 August 1993 Notifies of 930812 Meeting W/Util in Rockville,Md for Presentation on Plant Decommissioned TS ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20128G0061993-02-0101 February 1993 Notifies of Cancelled 930210 Meeting W/Technical Analysis Corp to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127L9741993-01-22022 January 1993 Notification of 930204 Meeting W/Util in Rockville,Md to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127J7691993-01-15015 January 1993 Discusses Interim Plugging Criteria for Util & Provides Discription of Core Damage Frequency Derivation & Present RES Plans for Addl Work on Steam Generator Tube NDE That RES Intends to Do This Year ML20127E7821993-01-11011 January 1993 Notification of Significant Licensee Meeting W/Util on 930120 to Discuss Shutdown Plans & Decommissioning Strategies for Facility ML20127A5381993-01-0707 January 1993 Discusses QC Concerns W/Mine Safety Appliances Co Full Face Negative Pressure Respirators (Ultra View & Ultra Twin) W/Potential 10CFR21 Implications ML20127F4461993-01-0707 January 1993 Revised Notification of Significant Meeting W/Util on 930202 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Department at Plant ML20127A5701993-01-0505 January 1993 Provides Position on Interim Plugging Criteria for Plant ML20126G9861992-12-22022 December 1992 Notification of Significant Licensee Meeting W/Util on 930113 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Dept at Plant ML20126F4821992-12-18018 December 1992 Notification of Cancellation of 921230 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109 primary-to-secondary SG Tube Leak Event & Recent Issues Raised Re Interim Plugging Criteria ML20126E6501992-12-18018 December 1992 Notification of or Energy Facility Siting Council Special Meeting & Hearing on 930105 & 06 in Portland,Or to Discuss Tnp SG Tube Cracking Issue,Interim SG Tube Plugging Criteria & Issues from Current Forced Outage.Agenda Encl ML20126F4271992-12-18018 December 1992 Notification of 921230 Meeting W/Util in Rockville,Md to to Discuss Steam Generator Insp Program & Results as Consequence of primary-to-secondary Steam Generator Leak Event on 921109 ML20126E7641992-12-16016 December 1992 Notification of 921223 Meeting W/Util in Rockville,Md to Discuss Steam Generator Insp Program & Results as Consequence of 921109 primary-to-secondary Steam Generator Tube Leak Event ML20126F4651992-12-16016 December 1992 Cancelled Notification of 921223 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109,primary-to-secondary SG Tube Leak Event ML20125C7641992-12-0909 December 1992 Discusses Technical Aspects of Rationale Used to Support Steam Generator Tube Interim Plugging Criteria for Plant & Independent Conclusions on Viability of Independent Plugging Criteria for One Fuel Cycle ML20126F4711992-12-0707 December 1992 Forwards Draft Rept of RES Position on Steam Generator Tube Integrity ML20126E5221992-11-30030 November 1992 Informs Staff Revised Prioritization Will Be Forwarded for Further Comments in Response to 921124 Memo Re GI 163, Multiple Steam Geneator Tube Leakage ML20125A6311992-11-25025 November 1992 Notification of 921201 Meeting W/Util to Discuss Assessment of Recent SG Tube Leak ML20128C3491992-06-16016 June 1992 Discusses Proposal of New Generic Issue, Multiple SG Tube Leakage, as Resolution to DPO Received Addressing Operation of SGs W/Microscopic Tube Wall Cracks.Dpo Encl ML20128C3141992-03-27027 March 1992 Submits Analysis, Safety Issue Re Continuous Operation W/ Degraded SG Tubes, Indicating Core Melt Probability Frequency of 10 -4/Ry W/Containment Bypass NUREG-5055, Notification of 901017 Meeting W/Util in Rockville,Md,To Discuss Proposed Mods to Control Bldg Per NUREG-50551990-10-10010 October 1990 Notification of 901017 Meeting W/Util in Rockville,Md,To Discuss Proposed Mods to Control Bldg Per NUREG-5055 ML20059C1331990-08-21021 August 1990 Notification of Enforcement Conference 90-143 W/Util on 900830 to Discuss Violation Noted During Special Security Insp 1999-09-03
[Table view] Category:MEMORANDUMS-CORRESPONDENCE
MONTHYEARML20217D1071999-09-16016 September 1999 Provides Proposed Schedule for Review of Trojan License Termination Plan (Ltp),As Committed in 990903 Memo.Project Manager Should Schedule LTP Meeting Near Trojan Site for Late Nov or Early Dec,Based on Region IV Availability ML20216E4091999-09-0303 September 1999 Informs That Staff Has Performed Acceptance Review of Trojan Nuclear Plant License Termination Plan Submitted by Ltr Dtd 990805.NMSS Determined That Licensee Has Provided Sufficient Info for NRC to Proceed with Detailed Review ML20205R4091999-04-16016 April 1999 Informs That LTP for Trojan Nuclear Plant Did Not Provide Sufficient Info to Perform Detailed Review & Waste Mgt Recommends Returning LTP to Licensee So That LTP Can Be Resubmitted as Complete Application ML20195B6401998-11-10010 November 1998 Notification of 981119 Meeting with Util in Rockville,Md to Discuss Preliminary Plans for Plant Final Site Surveys ML20155G6571998-11-0303 November 1998 Notification of 981119-990331 Meeting with Util in Rockville,Md to Clarify Remaining Technical Issues Associated with Util Application for License to Operate ISFSI at Tpp ML20236S5361998-07-22022 July 1998 Notification of 980812 Meeting W/Portland General Electric in Arlington,Texas to Discuss Status of Decommissioning Activities at Trojan NPP ML20236R6511998-07-15015 July 1998 Notification of 980730 Meeting W/Listed Participants in Kelso,Wa Re Proposed Request from Portland General Electric Co for Approval to Allow one-time Shipment of Plant Decommissioned Reactor Vessel.Meeting Agenda Encl ML20236R6931998-07-15015 July 1998 Notification of 980730 Meeting W/Util to Discuss Request for Addl Info Re Ongoing Review of Portland General Electric Co Request for Approval to Allow one-time Shipment of Trojan Decommissioned Reactor Vessel.Meeting Agenda Encl ML20248L4691998-03-17017 March 1998 Notifies of in-house Research Project Re Digital I&C in NPP & Forwards Technical Training Div (TTD) ML20216E7421998-03-0606 March 1998 Notification of 980318 Meeting W/Portland General Electric in Rockville,Maryland to Discuss Proposed Shallow Land Disposal of Trojan Reactor Vessel ML20199D4951998-01-26026 January 1998 Notification of Licensee Meeting W/Util on 980209 in Arlington,Tx to Discuss Changes to Protected Area for Plant to Facilitate Ongoing Decommissioning of Site ML20199G1561998-01-22022 January 1998 Staff Requirements Memo Re SECY-97-244, Waste Classification of Plant Reactor Vessel ML20199G1121998-01-20020 January 1998 Submits Addl Views on Proposal to Dispose of Trojan Reactor Vessel,Per SECY-97-244 ML20211M5671997-10-0303 October 1997 Forwards Regulatory Documents Comprising Regulatory History of Notice of Proposed Rulemaking Entitled Financial Assurance Requirements for Decommissioning Nuclear Power Reactors, Which Amended 10CFR50,published in Fr on 970910 ML20216F2611997-08-26026 August 1997 Staff Requirements Memo Re SECY-97-164, Shipment of Decommissioned Reactor Vessel,Containing Irradiated Internals,From Trojan Nuclear Plant to Hanford Nuclear Reservation,Richland,Wa ML20141G2911997-05-15015 May 1997 Forwards Page A-25 of Rev 5 to PGE-1060, Tnp Permanently Defueled Emergency Plan ML20137W9801997-04-16016 April 1997 Notification of Significant Licensee Meeting W/Util on 970508 in Rockville,Md to Discuss Plans for Decommissioning of Plant ML20137H2231997-03-31031 March 1997 Forwards Info in Support of Pnl Modeling for Fgeis Final Rule on Radiological Criteria for License Termination ML20135B1941997-01-30030 January 1997 Responds to Re Util Position Re Potential for Ash Fall at Trojan Site ML20138J2731997-01-21021 January 1997 Submits Comments on 970113-16 QA Insp of Sierra Nuclear Corp in Scott Valley,Ca ML20134B6001997-01-13013 January 1997 Provides Meeting Minutes from NRC Insp 97-201 Exit Meeting Re Insp of Trojan'S QA Program for Isfsi,From 970107-09 ML20133N2821997-01-0808 January 1997 Requests Comments on Poge Position Re Potential for Ashfall at Trojan Site ML20135B8581996-12-0303 December 1996 Requests Guidance on Use of 10CFR71.41(c) Per Licensee Request for Authorization to Transport Reactor Vessel as Type B Package ML20134D7161996-10-24024 October 1996 Requests That Encl Internet Mail Received from PM Blanch,Dtd Through 960930,be Placed in Pdr.No Distribution Outside of PDR Necessary ML20237F1891996-01-22022 January 1996 Notification of 960131 Meeting W/Util in Rockville,Md to Discuss Planned Removal of Plant Pressure Vessel ML20211M6231994-11-30030 November 1994 Provides Info to Commission on Status of Rulemaking Activities Re Power Reactor Decommissioning Cost Issues,Per 930714 SRM ML20057B6071993-09-16016 September 1993 Notification of 930928 Meeting W/Util in Rockville,Md to Discuss Status of Decommission Activities & Physical Security ML20057A6651993-08-27027 August 1993 Forwards Notice of Consideration of Issuance of Amend to License NPF-1 & Proposed NSHC Determination & Opportunity for Hearing ML20056E5331993-08-16016 August 1993 Notification of 930901 Mtg W/Util & State of or in Rainier, or to Discuss Proposed Studies of Plant Sys at Plant ML20056E4451993-08-0606 August 1993 Notifies of 930812 Meeting W/Util in Rockville,Md for Presentation on Plant Decommissioned TS ML20056E4571993-08-0505 August 1993 Forwards Technical Review Rept Re, Tardy Licensee Actions Initiated Because of Delayed Replacement of Batteries in Uninterruptible Power Supplies at Plant ML20128G0061993-02-0101 February 1993 Notifies of Cancelled 930210 Meeting W/Technical Analysis Corp to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127L9741993-01-22022 January 1993 Notification of 930204 Meeting W/Util in Rockville,Md to Discuss Shutdown Plans & Decommissioning Strategies for Plant ML20127J7691993-01-15015 January 1993 Discusses Interim Plugging Criteria for Util & Provides Discription of Core Damage Frequency Derivation & Present RES Plans for Addl Work on Steam Generator Tube NDE That RES Intends to Do This Year ML20127E7821993-01-11011 January 1993 Notification of Significant Licensee Meeting W/Util on 930120 to Discuss Shutdown Plans & Decommissioning Strategies for Facility ML20127A5381993-01-0707 January 1993 Discusses QC Concerns W/Mine Safety Appliances Co Full Face Negative Pressure Respirators (Ultra View & Ultra Twin) W/Potential 10CFR21 Implications ML20127F4461993-01-0707 January 1993 Revised Notification of Significant Meeting W/Util on 930202 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Department at Plant ML20127A5701993-01-0505 January 1993 Provides Position on Interim Plugging Criteria for Plant ML20126G9861992-12-22022 December 1992 Notification of Significant Licensee Meeting W/Util on 930113 to Discuss One Violation of 10CFR50.7(f) Identified During OI Investigation of Security Dept at Plant ML20126E6501992-12-18018 December 1992 Notification of or Energy Facility Siting Council Special Meeting & Hearing on 930105 & 06 in Portland,Or to Discuss Tnp SG Tube Cracking Issue,Interim SG Tube Plugging Criteria & Issues from Current Forced Outage.Agenda Encl ML20126F4271992-12-18018 December 1992 Notification of 921230 Meeting W/Util in Rockville,Md to to Discuss Steam Generator Insp Program & Results as Consequence of primary-to-secondary Steam Generator Leak Event on 921109 ML20126F4821992-12-18018 December 1992 Notification of Cancellation of 921230 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109 primary-to-secondary SG Tube Leak Event & Recent Issues Raised Re Interim Plugging Criteria ML20126E7641992-12-16016 December 1992 Notification of 921223 Meeting W/Util in Rockville,Md to Discuss Steam Generator Insp Program & Results as Consequence of 921109 primary-to-secondary Steam Generator Tube Leak Event ML20126F4651992-12-16016 December 1992 Cancelled Notification of 921223 Meeting W/Util in Rockville,Md to Discuss SG Insp Program & Results as Consequence of 921109,primary-to-secondary SG Tube Leak Event ML20125C7641992-12-0909 December 1992 Discusses Technical Aspects of Rationale Used to Support Steam Generator Tube Interim Plugging Criteria for Plant & Independent Conclusions on Viability of Independent Plugging Criteria for One Fuel Cycle ML20126F4711992-12-0707 December 1992 Forwards Draft Rept of RES Position on Steam Generator Tube Integrity ML20126E5221992-11-30030 November 1992 Informs Staff Revised Prioritization Will Be Forwarded for Further Comments in Response to 921124 Memo Re GI 163, Multiple Steam Geneator Tube Leakage ML20125A6311992-11-25025 November 1992 Notification of 921201 Meeting W/Util to Discuss Assessment of Recent SG Tube Leak ML20128C3491992-06-16016 June 1992 Discusses Proposal of New Generic Issue, Multiple SG Tube Leakage, as Resolution to DPO Received Addressing Operation of SGs W/Microscopic Tube Wall Cracks.Dpo Encl ML20128C3141992-03-27027 March 1992 Submits Analysis, Safety Issue Re Continuous Operation W/ Degraded SG Tubes, Indicating Core Melt Probability Frequency of 10 -4/Ry W/Containment Bypass 1999-09-03
[Table view] |
Text
, .
I 1
June 17, 1986 Docket No. 50-344 DJSTRIBUTION
\ Docket File NRC PDR Local NRC PAD- 3 Rdg.
MEMORANDUM T0: Dennis F. Kirsch Division Director K. Johnston Division of Reactor Safety Projects, RV T. Chan C. Vogan FROM: Steven A. Varga, Project Director S. Varga PWR Projects Directorate #3
SUBJECT:
CLARIFICATION ON TROJAN TECHNICAL SPECIFICATION 3.5.2, FLOW PATH REQUIREMENTS FOR THE RESIDUAL HEAT REMOVAL On March 31, 1986, Portland General Electric (PGE) issued Licensee Event Report (LER) No. 86-03 for the Trojan Nuclear Plant. LER 86-03 reported that valve M0-8809A (RHR pump discharged valve / cold leg injection) was taken out of service for preventive maintenance while Trojan was at 100% power. LER 83-03 stated that removal of this valve from service degraded the ECCS injection function of the RHR system based on the analysis in the UFSAR and that TS 3.5.2 "ECCS Subsystems - Tavg greater than or equal to 350 F" had been incorrectly interpreted and the interpretation had been incorporated in plant maintenance procedures.
By memorandum dated May 19, 1986, you requested that NRR provide clarification regarding what are the flow path requirements and minimum acceptable independence requirements for each RHR subsystem.
A. RHR Flow Path Requirements TS 3.5.2 requires two independent ECCS subsystems to be operable, each subsystem being comprised of "an operable flow path capable of taking suction from the RWST on a SI signal and transferring suction to the containment sump during recirculation phase of operation." One subsystem can be inoperable for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> in Mode 1. As noted in the LER, the licensee interpreted this as allowing M0-8809A to be taken out of service for up to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />. However, with M0-8809A closed, low head SI flow to RCS loops 1 & 2 is isolated.
The Tro.ian ECCS design assumes low head SI flow to all four loops during the injection phase of a LOCA. Therefore, an operable flow path would require M0-8809 A and B to be open during Modes 1, 2, and 3. With M0-8809A closed, Trojan did not meet TS 3.5.2.
8606250536 860617 PDR ADOCK 05000344 S PDR
B. RHR Independence Requirements A review of Figure 5.4-7 in the Trojan FSAR would indicate that the Trojan low head SI system lacks redundancy not only with regard to valves M0-8809 A & B but also with regard to RHR pump suction isolation valve M0-8812.
However, FSAR Section 6.3.3.13.1 indicates that valves M0-8809 A & B and M0-8812 are normally open, with control power lockout provided in the control room, thus effectively provided double isolation of the control power. Therefore; two independent spurious events would be required to energize the contactor coil, thereby causing unintentional valve operation. Testing of control circuitry would not change the valve position provided that the control circuit and lockout feature are intact.
This design meets Branch Technical Position PSB BTP .18, " Application of the Single Failure Criterion to Manually-Controlled Electrically-Operated Valves."
We therefore conclude that the Trojan design meets the intent of LC0 3.5.2.e providing valves M0-8809 A & B, and M0-8812 are maintained in the locked open position during Modes 1, 2, and 3.
Steven A. Varga, Director PWR Directorate #3 Division of PWR Licensing-A, NRR i
I
/
- SEE PREVIOUS PAGE FOR CONCUR PAD-3* PAD-3 PAD- - .
i C. Vogan K. slohns on T. Chan S. V ga 06/11/86 06/4/86 06/4/86 06f 6
i 7_
Section 6.3.3.13.1 indicates that valves M0-8809 A & B and M0-8812 are normally open, with control power lockout provided in the control room, thus ffectively providing double isolation of the control power. Therefore, two i ependent spurious events would be required to energize the contractor coil, thereby causing unintentional valve operation. Testing of control circy'itry would not <
change the valve position providing that.the control circuit an'd lockout feature are intact. ThisdesignmeetsBranchTechnicalPosiyionPSBBTP18,
" Application of the Single Failure Criterion to Manually-Controlled Electrically-Operated Yalves." /
We therefore conclude that the Trojan design meets the ntent of LCO 3.5.2.e providing valves M0-8809 A & 3, and M0-8812 are maint ned in the locked open position during Modes 1, 2, and 3.
Steven A. Vayga, Director PWR Directov ate #3 Division f PWR Licensing-A, NRR l
/
/
t PAD-3 b PAD 3 PAD-3 PAD-3 C. Vogan K Johnston T. Chan S. Varga 06/8/86 / /86 06/ /86 06/ /86 i
- - - _ - - _ - _ _ _ - , - - _ . . _ . _ - - _ . _ , ,_ . . , _ _ _ , , , , , _ _ _ . __ _ , ,