Applicant Exhibit A-19,consisting of Justification of Continued Operation Developed to Assist in Evaluation of Splices Utilized in Certain Environmentally Qualified Solenoid ValvesML20094N221 |
Person / Time |
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Site: |
Farley ![Southern Nuclear icon.png](/w/images/1/14/Southern_Nuclear_icon.png) |
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Issue date: |
02/12/1992 |
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From: |
Hairston W ALABAMA POWER CO. |
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To: |
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References |
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CIVP-A-019, CIVP-A-19, NUDOCS 9204060224 |
Download: ML20094N221 (5) |
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Category:EXHIBITS (DOCKETING AND SERVICES BRANCH INFORMATION
MONTHYEARML20118A1461992-05-21021 May 1992 Staff Exhibit S-83,consisting of Graph Re Sandia Test Re Exposure ML20118A1241992-05-21021 May 1992 Applicant Exhibit A-135,consisting of Diagram Re NSS3 Terminal Block Assembly as-built Dimensions ML20118A1481992-05-21021 May 1992 Staff Exhibit S-85,consisting of Paper by J Delmonte Re Plastics in Engineering ML20118A1471992-05-21021 May 1992 Staff Exhibit S-84,consisting of Graph Re 120 Divs 5th,10th Accent by 6 Cycle semi-log ML20118A1231992-05-20020 May 1992 Applicant Exhibit A-129,consisting of Memo Forwarding Record of 920514 Telcon ML20118A1191992-05-20020 May 1992 Applicant Exhibit A-125,consisting of Notes from 871118 Meeting ML20118A1201992-05-20020 May 1992 Applicant Exhibit A-126,consisting of Notes Re Rcw Open Areas ML20118A1221992-05-20020 May 1992 Applicant Exhibit A-128,consisting of Notes Re 871120 Plant Exit Meeting ML20118A1211992-05-20020 May 1992 Applicant Exhibit A-127,consisting of Notes Re 871120 Plant Exit Meeting ML20118A1181992-05-19019 May 1992 Applicant Exhibit A-124,consisting of Rept IPS-107, Test Rept on Electrical Terminations Subjected to Design Basis Accident Environ ML20118A1341992-05-18018 May 1992 Staff Exhibit S-70,consisting of Sys Component Evaluation Worksheet ML20118A1171992-05-18018 May 1992 Applicant Exhibit A-123,consisting of Operator Handbook Re Nuclear Containment Axivane Fan ML20118A1121992-05-18018 May 1992 Applicant Exhibit A-118,consisting of Product Control Document NCBK-04-04 ML20118A1131992-05-18018 May 1992 Applicant Exhibit A-119,consisting of Matl Safety Data Sheet ML20118A1111992-05-18018 May 1992 Applicant Exhibit A-117,consisting of 871109 Notes Re Plant ML20118A1091992-05-18018 May 1992 Applicant Exhibit A-115,consisting of Record of 891121 Telcon Re Okonite Tape Splices ML20118A1051992-05-18018 May 1992 Applicant Exhibit A-112,consisting of Re Closure of Completed License Conditions ML20118A1101992-05-18018 May 1992 Applicant Exhibit A-116,consisting of Drawing 1366C51 Re Electric Heater Wire Bill & Diagram ML20118A1161992-05-18018 May 1992 Applicant Exhibit A-122,consisting of Re Qualification Info ML20118A1391992-05-18018 May 1992 Staff Exhibit S-75,consisting of Table 1 Re Reg Guide Variable Cross Ref to Variable Number ML20118A1401992-05-18018 May 1992 Staff Exhibit S-76,consisting of Paper Entitled, Westinghouse Setpoint Methodology for Control & Protection Sys ML20118A1381992-05-18018 May 1992 Staff Exhibit S-74,consisting of NUREG/CR-3691, Assessment of Terminal Blocks in Nuclear Power Industry ML20118A1321992-05-18018 May 1992 Staff Exhibit S-68,consisting of 900619 Memo Re Plant Tape Splice Test & Info Received from Okonite Re Thermal Properties of Okonite T-95 Splicing Tape ML20118A1431992-05-18018 May 1992 Staff Exhibit S-79,consisting of Info Re Continuous Vs Intermittent Use & Lube Performance ML20118A1451992-05-18018 May 1992 Staff Exhibit S-82,consisting of 831202 Memo Re Composite Audit Rept 83/19 for Plant ML20118A1311992-05-18018 May 1992 Staff Exhibit S-67,consisting of Re Mlea Project 90009 Involving Thermal Behavior of T-95 & Scotch 33 ML20118A1351992-05-18018 May 1992 Staff Exhibit S-71,consisting of EQ Insp Tracking Sheet for Farley Nuclear Plant ML20118A1331992-05-18018 May 1992 Staff Exhibit S-69,consisting of Sys Component Evaluation Worksheet ML20118A1421992-05-18018 May 1992 Staff Exhibit S-78,consisting of Installation & Maint Manual Re Series 800/1000/2000/3000 Axivane Fans ML20118A1151992-05-18018 May 1992 Applicant Exhibit A-121,consisting of Performance Test Data of Limitorque Valve Operator ML20118A1371992-05-18018 May 1992 Staff Exhibit S-73,consisting of NUREG/CR-3418, Screening Tests of Terminal Block Performance in Simulated LOCA Environ ML20118A1361992-05-18018 May 1992 Staff Exhibit S-72,consisting of EQ Insp Tracking Sheet for Farley Nuclear Plant ML20100R4001992-02-21021 February 1992 Applicant Exhibit A-81 Consisting of Rept Entitled, Clarification of Info Re Environ Qualification of Limitorque Motorized Valve Operators ML20100R4051992-02-21021 February 1992 Applicant Exhibit A-82,consisting of Resume for Vs Noonan ML20100R3991992-02-21021 February 1992 Applicant Exhibit A-79,consisting of Resume for PA Dibenedetto ML20100R4281992-02-21021 February 1992 Applicant Exhibit A-110,consisting of Graph of Insulation Resistance & Temp Periods ML20100R4301992-02-21021 February 1992 Applicant Exhibit A-111,consisting of Graph of Total Elapsed Time Re Phase Two of Environ Temp Profile ML20094P3991992-02-20020 February 1992 Applicant Exhibit A-46,consisting of Ltr Confirming Info Previously Provided to Util Re Environmentally Qualified Prototype Testing ML20094N7191992-02-20020 February 1992 Staff Exhibit S-60,consisting of Memo Recommending That Licensees Review Facilities to Determine If Specific Terminal Blocks Used in Low Voltage Application ML20100R4271992-02-20020 February 1992 Applicant Exhibit A-109,consisting of Ltr Forwarding Document on Limitorque Actuator Environ Qualification ML20094N7351992-02-20020 February 1992 Applicant Exhibit A-70,consisting of EQ Action Item Describing Problem & Resolution Status.Related Correspondence ML20094P2021992-02-20020 February 1992 Applicant Exhibit A-23,consisting of Util Environ Qualification Program for Plant ML20094P2281992-02-20020 February 1992 Applicant Exhibit A-29,consisting of Work History & Educational Background for Util Project Engineer ML20094P2331992-02-20020 February 1992 Applicant Exhibit A-30,consisting of Work History & Related Experience of Util Employee ML20094P3621992-02-20020 February 1992 Applicant Exhibit A-36,consisting of Rept Indicating IEEE Std for Qualifying Class 1E Equipment for Nuclear Power Generating Stations ML20094P3651992-02-20020 February 1992 Applicant Exhibit A-38,consisting of Working Specs for Installation of Cables ML20100R3931992-02-20020 February 1992 Applicant Exhibit A-76,consisting of Rept Entitled, Radiation Exposure & Accident Simulation Test Program on Texaco Greases & Oils ML20094P4101992-02-20020 February 1992 Applicant Exhibit A-37,consisting of Excerpts from IEEE Trial Use Std Re General Guide for Qualifying Class One Electric Equipment for Nuclear Power Generating Stations ML20100R3791992-02-20020 February 1992 Applicant Exhibit A-57,consisting of Info Re CR151B Terminal Boards for Control Circuits ML20100R3801992-02-20020 February 1992 Applicant Exhibit A-58,consisting of Sensor Products Qualification Test Summary Rept 1992-05-21
[Table view] Category:LEGAL TRANSCRIPTS & ORDERS & PLEADINGS
MONTHYEARML20196J3291999-06-28028 June 1999 Comment Supporting Proposed Rule 10CFR50 Re Industry Codes & Standards ML20206M7291999-04-30030 April 1999 Comment Supporting Draft RG DG-1083, Content of UFSAR IAW 10CFR50.71(e). Licensee of Listed Plants in Total Agreement with Comments Provided to NRC by NEI HL-5717, Comment Supporting Proposed Rule 10CFR50,52 & 72 Re Changes, Tests & Experiments.Util in Total Agreement with NEI Comments to Be Provided to NRC1998-12-18018 December 1998 Comment Supporting Proposed Rule 10CFR50,52 & 72 Re Changes, Tests & Experiments.Util in Total Agreement with NEI Comments to Be Provided to NRC HL-5715, Comments on Proposed Rule 10CFR50 Re Monitoring Effectiveness of Maint at Nuclear Power Plants.Util Is in Total Agreement with NEI Comments1998-12-14014 December 1998 Comments on Proposed Rule 10CFR50 Re Monitoring Effectiveness of Maint at Nuclear Power Plants.Util Is in Total Agreement with NEI Comments HL-5702, Comment Supporting NEI Comments Totally on Proposed Draft RG DG-4005, Preparation of Supplemental Environmental Repts for Applications to Renew Nuclear Power Plant Ols1998-10-23023 October 1998 Comment Supporting NEI Comments Totally on Proposed Draft RG DG-4005, Preparation of Supplemental Environmental Repts for Applications to Renew Nuclear Power Plant Ols HL-5695, Comment Supporting Nuclear Energy Institute (NEI) Comments on 10CFR50.55(a) Pr, Streamlined Hearing Process for NRC Approval of License Transfers1998-10-13013 October 1998 Comment Supporting Nuclear Energy Institute (NEI) Comments on 10CFR50.55(a) Pr, Streamlined Hearing Process for NRC Approval of License Transfers HL-5690, Comment on Integrated Review of Assessment Process for Commercial Nuclear Plants. Util in Total Agreement with NEI Comments Provided to NRC1998-10-0505 October 1998 Comment on Integrated Review of Assessment Process for Commercial Nuclear Plants. Util in Total Agreement with NEI Comments Provided to NRC HL-5983, Comment on Proposed Rule 10CFR50 Re Reporting Requirements for Nuclear Power Reactors. Snoc in Total Agreement with NEI Comments,To Be Provided to Nrc.Requests That NRC Provide Guidance to Application of NUREG-1022,rev 1 as Listed1998-09-21021 September 1998 Comment on Proposed Rule 10CFR50 Re Reporting Requirements for Nuclear Power Reactors. Snoc in Total Agreement with NEI Comments,To Be Provided to Nrc.Requests That NRC Provide Guidance to Application of NUREG-1022,rev 1 as Listed HL-5682, Comment Opposing Draft NUREG-1633, Assessment of Use of Potassium Iodide (Ki) as Protective Action During Severe Reactor Accidents, & Endorsing Comments Submitted by Nuclear Energy Institute1998-09-15015 September 1998 Comment Opposing Draft NUREG-1633, Assessment of Use of Potassium Iodide (Ki) as Protective Action During Severe Reactor Accidents, & Endorsing Comments Submitted by Nuclear Energy Institute ML20153B2391998-09-15015 September 1998 Comment on Draft NUREG-1633, Assessment of Use of Ki as Protective Action During Severe Reactor Accidents. Endorses NEI Comments HL-5602, Comment Opposing Proposed Rule 10CFR50 Re Industry Codes & Stds1998-04-0303 April 1998 Comment Opposing Proposed Rule 10CFR50 Re Industry Codes & Stds HL-5586, Comment on Proposed Generic Ltr, Year 2000 Readiness of Computer Sys at Npps1998-03-0404 March 1998 Comment on Proposed Generic Ltr, Year 2000 Readiness of Computer Sys at Npps HL-5582, Comment on Draft Reg Guide DG-5008, Reporting of Safeguards Events1998-02-27027 February 1998 Comment on Draft Reg Guide DG-5008, Reporting of Safeguards Events ML20203B9761998-02-23023 February 1998 Order Prohibiting Involvement in NRC Licensed Activities (Effective Immediately).Requires That Mcgriff Be Prohibited from Any Involvement in NRC-licensed Activities for Period of 3 Yrs from Date of Dismissal from SNC on 970305 HL-5564, Comment on Draft NUREG 1555, Updated Environ Standard Review Plan1998-01-30030 January 1998 Comment on Draft NUREG 1555, Updated Environ Standard Review Plan HL-5554, Comment Supporting NEI Comments on PRM 50-63A by P Crane Recommending Emergency Planning Standard for Protective Actions Be Changed to Require Explicit Consideration of Prophylactic Use of Potassium Iodide for General Public1998-01-15015 January 1998 Comment Supporting NEI Comments on PRM 50-63A by P Crane Recommending Emergency Planning Standard for Protective Actions Be Changed to Require Explicit Consideration of Prophylactic Use of Potassium Iodide for General Public HL-5546, Comment Supporting Proposed Rule & Direct Final Rule on 10CFR50.68 & 10CFR70.24, Criticality Accident Requirements1997-12-31031 December 1997 Comment Supporting Proposed Rule & Direct Final Rule on 10CFR50.68 & 10CFR70.24, Criticality Accident Requirements HL-5529, Comment Opposing Rule 10CFR50 Re Codes & Standards,Ieee National Consensus Standard1997-12-0101 December 1997 Comment Opposing Rule 10CFR50 Re Codes & Standards,Ieee National Consensus Standard ML20199J0031997-11-24024 November 1997 Comment Supporting Proposed Rule Re Financial Requirements for Decommissioning Nuclear Power Reactors & Draft RG 1060 HL-5424, Comment on NUREG-1606, Proposed Regulatory Guidance Re Implementation of 10CFR50.59 (Changes,Tests or Experiments). Encourages NRC Not to Abandon 30 Yrs of Effective Implementation of 10CFR.50.59 for New Positions1997-07-0707 July 1997 Comment on NUREG-1606, Proposed Regulatory Guidance Re Implementation of 10CFR50.59 (Changes,Tests or Experiments). Encourages NRC Not to Abandon 30 Yrs of Effective Implementation of 10CFR.50.59 for New Positions ML20148N0741997-06-19019 June 1997 Comment on Proposed Suppl to Bulletin 96-001 Re Control Rod Insertion Problems.Util in Complete Agreement That Incomplete Rcca Insertion Not Acceptable HL-5407, Comment Opposing NRC Proposed Strategies to Address Licensees Need to Establish & Maintain safety-conscious Work Environ1997-05-27027 May 1997 Comment Opposing NRC Proposed Strategies to Address Licensees Need to Establish & Maintain safety-conscious Work Environ ML20132A9171996-11-27027 November 1996 Comment Supporting Draft RG DG-1047, Stds Format & Content for Applications to Renew NPP Ols ML20128M3411996-09-30030 September 1996 Comment on Proposed Generic Communication, Primary Water Stress Corrosion Cracking of Control Rod Drive Mechanism & Other Vessel Head Penetrations ML20116D6491996-07-31031 July 1996 Exemption from Requirements of 10CFR70.24 Re Criticality Monitoring Requirements ML20116G9271996-07-29029 July 1996 Comment Supporting Proposed Rule 10CFR26 Re Mods to Fitness-For-Duty Program Requirements ML20115D1911996-07-0505 July 1996 Comment on Final Rule 10CFR51 Re Environ Review for Renewal of Nuclear Power Plant Operating License.Supports NEI Comments ML20115H1951996-07-0303 July 1996 Comment Supporting Proposed Rule 10CFR50, Reporting Reliability & Availability Info for Risk-Significant Sys & Equipment ML20113C6691996-06-24024 June 1996 Comments on Proposed Rule 10CFR50 Re Financial Assurance Requirements for Decommissioning Nuclear Power Reactors ML20100D1871996-01-29029 January 1996 Comment Opposing Petition for Rulemaking PRM-50-63, Recommending That Planning Std for Protective Actions for General Public Include Stockpile or Predistribution of Ki for Prophylactic Use ML20095D9801995-12-0808 December 1995 Comments on Proposed Generic Communication, Boraflex Degradation in SFP Storage Racks ML20094M9691995-11-13013 November 1995 Comment on Proposed Rules 10CFR60,72,73 & 75, Safeguards for Spent Nuclear Fuel or High-Level Radioactive Waste ML20091Q2711995-08-28028 August 1995 Comment Opposing Review of Revised NRC SALP ML20086N6141995-07-10010 July 1995 Comment on Proposed Generic communication;10CFR50.54(p), Process for Changes to Security Plans W/O Prior NRC Approval. Endorses NEI Comments ML20086M8011995-06-28028 June 1995 Comment on Proposed Review of NRC Insp Rept Content,Format & Style. Util Applauds NRC for Undertaking Endeavor to Make Insp Rept More Effective Tool for Communicating W/Licensees & Public ML20083N4921995-05-0404 May 1995 Comment on Proposed Rule 10CFR50, Primary Reactor Containment Leakage Testing for Water-Cooled Power. Util in Total Agreement W/Nei Comments ML20082K0461995-04-10010 April 1995 Comment on Draft Policy Statement, Freedom of Employees to Raise Safety Concerns W/O Fear of Retaliation. Endorses NEI Comments ML20078J8101995-02-0303 February 1995 Comment Supporting NUMARC Comments on Proposed Rule 10CFR50 Re Shutdown & low-power Operations for Nuclear Power Reactors ML20080G8471995-02-0101 February 1995 Comment on Proposed Rule 10CFR21 Re Procurement of Commercial Grade Items by NPP Licensees.Recommends That New Definitions Be Applicable & Consistent to Licensees Who Hold Other Licenses as Well as Part 50 License ML20085E5381995-01-0505 January 1995 Comment on Proposed Rule 10CFR73 Re Changes to NPP Security Requirements Associated W/Containment Access Control. Supports NEI Comments ML20077F6561994-12-0101 December 1994 Comment on Proposed Generic Ltr Re Reconsideration of NPP Security Requirements for Internal Threat.Util in Total Agreement W/Nei Comments ML20077E9171994-12-0101 December 1994 Comments on Proposed Rule 10CFR2,51 & 54 Re NPP License Renewal,Proposed Revs.Informs That Util in Total Agreement W/Nei Comments to Be Provided to NRC ML20072T6651994-09-0202 September 1994 Comment on Supplemental Proposed Rule 10CFR51 Re Environ Review for Renewal of Operating Licenses.Util in Agreement W/Nei Comments to Be Provided to NRC ML20072K3331994-08-17017 August 1994 Comment Supporting Petition for Rulemaking PRM-9-2 Re Ohio Citizens for Responsible Energy,Inc Petition ML20072B3711994-08-0909 August 1994 Comments on Proposed Rule 10CFR26 Re Consideration of Changes to FFD Requirements.Licensee in Total Agreement W/Nei Comments ML20071H1321994-06-27027 June 1994 Comment Supporting Proposed Rulemaking 50-60 Re Virginia Power;Filing of Petition for Rulemaking ML20069J5901994-06-0909 June 1994 Comment Supporting Proposed Rule 10CFR170 & 171 Re Rev of Fee schedules;100% Fee recovery,FY94 ML20065P4631994-04-25025 April 1994 Comment Supporting Proposed Rule 10CFR50 Re Codes & Stds for Npps;Subsections IWE & Iwl ML20065P4541994-04-0505 April 1994 Comments on Draft NUREG-1022,Rev 1, Event Reporting Sys (10CFR50.72 & 50.73) Clarification of NRC Sys & Guidelines for Reporting. Util in Total Agreement W/Nei Comments ML20064L8671994-03-11011 March 1994 Comment Supporting Proposed Amends to 10CFR20 Re Radiological Criteria for Decommissioning of NRC Licensed Facilities 1999-06-28
[Table view] |
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'92 MAR 13 P12:00 Alabama Nwer NS-87-0229 Justification for Continued Operation-- .o. 33,3 ;
Energized Solenoid Valves In or5 ter N StMit# -i s.amt Environmental Qualification ScopeKKEigff{h 21, 1987 cm. W. G. Hairston. III to Mr. J. D. _ Woodard Ai Vice President.
Nuclear Genc ation b
Enclosed-is a justification for continued operation (JCO)_ developed by -
Nuclear Support to assist FNP in their evaluation of splices utilized in certain environmentally qualifled (EO) solenoid vaives. Alse-enclosed (and referenced in the Nuclear Support input)-is input from Bechtel regarding:
(1) solenoid valves which are deenergized to perform thir accident mitigation function, and-
'(2)-. - EQ solenoid valve coil pigtail splices (terminati ...) located in the Main' Steam Valve Room.- -
The Bechtel assumptionf regarding-the configuration of tne conduit and junction box are believed to be an accurate reflection of the as built condition; however, FNP 3hould evaluate their agreement with walkoown reniti.
-A copy of this' letter should be placed in the Environmental
. Qualification Central File under ASCO Solenotd Valve.
g, s W..G. Hairston, !!!
WGH III/_ JAR: dst-060 Enclosure cc:- Mr. 0.--N. Morey Mr. J. E. Garlington Mr. D.'H.-Jones-Mr. K. C. GanChi File: A-5001:IEB 79-01B 9204060224 920212 PDR -ADOCK 05000348' G PDR
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,,_.., k gg, 9tgc034 oe.200 40< 4 0 JC0.: For Energized Solenoid Yalves In Environmental Qualification S
- 1. N1(2)S31SV0444 BA, BB 445 AA, AB Pressurizer PORV The pressurizer PORVs are normally closed and minimize the potenti the pressurizer safety valves in the event of certain accident scenariosThe .
FNP accident analyses do not take credit for operation of the PORVs (refe APCo' letter tolNRC dat' ed 6-23-82) and' primary system overpressure prote is provi,ded.by the safety valves.
The use'$f the Safety Valves precludes -
exceeding the RCS safety limit as defined in the Technical Specifications. In addition, it should.be noted that the Technical Specifications permit continue operation with both PORVs isolated by block valves with their power removed Furthermore, Technical Specifications even require positive isolation of POR _
vent path should tne PORY be inoperaole. Since the safety function can be satisfied by tne safety valves alone, continued operation is justified.
- 2. Q1(2)M11SV3369 AC, BC, CC 3370 AC, BC, CC Main Steam Isolation Valves (MSIV)
The main steam isolation valves are normally open during power operation. The safety function of the MSIVs is to close to isolate main steam such that accident analysis assumptions are satisfied. In the event >f an HELB in the main stea,m valve room, the ESF actuation sy:',en, would initiate MSIVAs closure.
discussed by Bechtel letter AP-13169 the environmental conditions seen by th circuits in question are not expected to produce failures which would interr power necessary to close the MSIVs.
It should be noted that MSIV closure occurs relatively early in the transients of concern.
If the worst case fault in tL.
circuit to the solenoid valve is postulated after MSIV closure, the fault would be of no concern beccuse the MSly mechanical design precludes the valve from reopecing in a manner that would unisolate a faulted steam generator while the intact steam gnerators are pressurized.
The safety function of thne valves is therefore achieved with the energization of the valves.
r - 20 .40 c0# 9102022 22: 20 60/20 Page 2
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The specific concern for this JC0 is the environmental qualification of-tne electrical cable splice between the solenoid valve end junction box. Given the raceway system configuration, the subject splices are capable of withstanding the expected Main Steam Valve toom environment and will thus be able to function per original design during a steam line or feedwater break accident. In addition, any such exposure would only be for a short period of time. The basis ,
for utilizing' the above information as a part of this justification is contained in the enclosed Bechtel letter AP-13169 dated July 21, 1987. Since the safety
- funct' ion ;is not jeopardized and is satisfied, continued operation u justified.
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Turbine Driven Auxiliary feedwater
- 3. Q1(2)N12SV3235 A, B; :
Pump Main Steas Admission Valvas The turbine driven ' auxiliary feedwater pump main steam admission valves are normally closed except during pump operation wnen the solenoid valves are required to be energized. The safety function of these valves is therefore achieved with the energization of the valves. The specific concern for this JC0 is the environmental aualification of the electrical cable splice between the solenoid valve and junction box. Given the raceway system configuration, tne subject splices are capable of withstaading the expected Main Steam Valve Room environment and will tnus be able to function per original design during a steam line or feedwater breax accident. In addition, any such exposure would only be for a snort period of time. The basis for utilizing the waixdown information as a part of this justification is contained in the enclosed ghtel letter AP-13169 dated July 21, 1987. Since the safety function is not jeopardized and is satisf.ied, continued operation is justified.
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- 4. Q1(2)M235Y3227 AA, BA, CA. AC BC CC Auxiliary Feedwater Control Valves 3228 AA, L' , CA
~
The purpose of these valves is to control auxiliary feedwater flow to the steam generators during normal nd accident conditions. The safety function is for these valves to open and, supply. water to the; steam generator during accident e .
conditions. t On a loss of air these valves fall to the open position.
The safety function of these valves is therefore achieved with the energitation of the valves.. The specific concern for this JC0 is the environmental qualification of'the e'lectrical cable splice between the solenoid valve and junction box.
Given the raceway system configuration, the subject splices are '
capable of withstanding the expected Main Steam Valve Room environment and will thus be able to fun [ction gier original design during a steam line or feedwater breakaccidest. In' add'iti[n, any such exposure would only be for a stort period of tiine.
The basis for. utilizing the walkdown information as a part of this justification'is contained in the enclosed Bechtel letter AP-13169 dit ed July 21, 1987.
Since the safety function is not jeopardized and is satidied, continued operation'is justified.
- 5. Q1(2)P175V3184 Compenent Cooling Water (CCW) to RCP
% Thermal Barrier The CCW to RCP Thermal Barrier valve is normally open ano protects the reactor coolant pump seal from high temperature primary System water.
A diverse method of protecting the RCP seals is by utilizing CVC5 seal injection. The safety function of HV 3184 is to cloca for containment isolation upon a Phase 8 Containment Isolation signal. A Phase B signal also isolates instrument air to containment.
By design, normal loss of instrument air due to bleeding will depressurize the instrument air system inside containment.
HV 3184 will close upon loss of instrument air even with its solenoid valve deenergized. Valve clost.re occurs without opccator action.
Therefore, since valve closure of HV 3184 occurs upon receipt of a Phaso B signal, the safety function is satisfied and continued operation is justified.