ML20070L991
| ML20070L991 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 01/03/1983 |
| From: | Gucwa L GEORGIA POWER CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| REF-SSINS-6820, REF-SSINS-SSINS-6 IEB-79-01B, IEB-79-1B, TAC-42505, TAC-42506, TAC-49317, NUDOCS 8301120177 | |
| Download: ML20070L991 (108) | |
Text
-p-Georg3 Power Company 333 Piedmont Avenue Atlanta. Georgia 3%C8 "
Telephone 404 523-7020 Maihng Address Post Othee Bcx 4545 Atlanta. Geergia 30302 Georgia Power OY '
the southem electoc system J. T. Beckham, Jr.
Vce President and General Manacer Nuclear Generat or' Director of Nuclear Reactor Regulation U. S. Nuclear Regulatory Comission Washington, D. C.
20555 NIC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EDNIN I. HAICH NUCLEAR PIANT UNITS 1, 2 ELECTRICAL EQUIPMENT QUALIFICATION STATUS Gentlemen:
In accordance with Georgia Power Company's (GPC) policy to periodically apprise the Nuclear Regulatory Comission (NRC) of our efforts to comply with the requirements of I&E Bulletin 79-OlB, GPC subnits the follow #ng information.
Enclosed with this submittal are updaed pages for the 'GPC Response to NBC I&E Bulletin 79-01B for Plant Hatch" dated November 1, 1980. This is not, however, a complete update of the entire response; that will be provided upon final completion of this program.
In a letter to the NBC dated November 16, 1981, GPC comitted to canplete the Hatch qualification program by the end of the outages tentatively scheduled for the spring of 1983 for Unit 2 and for the spring of 1984 for Unit 1.
GPC reaffirms this comitment and subnits the enclosed open item status reports as a schedule for meeting these dates.
In addition, completed work has been highlighted on these pages for ease of identification.
The NRC staff report, "Rulemaking Issue", dated May 24, 1982 (SECY 82-207) suggested that electrical equipnent in mild environment areas should be subject to "QA requirements" as opposed to " qualification requirements."
Therefore, GPC has deferred the completion of the Hatch mild environment qualification programs until publication of the final rule on this issue.
However, the mild environment equipnent lists have been completed so that a complete surveillance and maintenance program can be provided for this equipment.
GPC believes that the present Hatch QA program aided by this equipnent list would be able to provide full compliance with the final rule if it is approved as proposed by the NBC staff.
Oh 8301120177 830103
,PDR ADOCK 05000321
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. Georgia lbwer A Director of' Nuclear Reactor Regulation U. S. Nuclear Regulatory Connission Washington, D. C.
20555 January 3, 1983 Page Two-If you have. any questions regarding this issue, please contact this office.
Very truly yours,
/7gs;
- c. T. c o a Chief Nuclear Engineer CBS/mb Enclosure xc:
J. T. Beckham, Jr.
!!. C. Nix, Jr.
Senior Resident Inspector J. P. O'Reilly (NIC-Region II) f f
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EDWIN 1. -HATCH NUCLEAR PIANT UNIT 1 SECTION B.3.2.2
SUMMARY
OF OUTSTANDING ITDIS NUCLEAR STEAM SUPPLY SYSTEM COMPONEIGS This section sunnarizes the status of the qualification efforts for equip-ment with outstanding items identified on the System Component Evaluation Work Sheets for t.he Nuclear Steam Supply System Components.
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RHR AND CORE SPRAY PUMP MOTORS TheRHkandCoreSprayPumpmotorswereidentifledasopenitemsinpreviousIEB m er - ~.-- --
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The System Component Evaluation Work Sheets have been revised accordingly.
Applicable Equipment E11-C002A,B,C,D E21-C001A,B 1
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HPCI' TURBINE C0!GROLS Information is presently not available to demonstrate complete acceptability of the HPCI Turbine Controls (E41-C002). General Electric has provided Georgia Power Company with partial qualification test data, but supplementary infor-mation will.be needed to qualify the equipment for aging and radiation. A walkdown of the HPCI Turbine was completed the week of March 22, 1982 and an analysis is presently being performed to qualify the individual components for aging ari radiation. This analysis is scheduled for completion by l
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, 1 ANALOG TRANSMITTER TRIP SYSTEM Information.is presently not available to demonstrate complete acceptability of.the equipment listed.
The' equipment will be replaced with an Analog Transmitter Trip System' (ATTS).
The equipment is' presently undergoing qualification testing to IEEE-323-1974/NUREG-0588, Category I.
Qualification of ATTS equipment will be achieved in two (2) phases.
Phase I will qualify the equipment for a qualified life of 2-5 years, which will be completed prior to delivery.
Phase II will qualify the ATTS equipment for a 40 year life'and will be completed
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prior to end of'the 2-5 year qualified life.
Design Change Request (DCR)81-138 has been issued to facilitate this change.
Installation of the ATTS is scheduled for the Unit 1, Fall 1984, refueling outage.
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Applicable Equipment - Analog Transmitter Trip System MPL NO.
MPL NO.
B21 N006a B21 NO36 B21 N006B B21 NO37 B21 N006C B21 N042A B21 N006D B21 N042B B21 N007A C71 N002A B21 N007B C71 N002B B21 N007C C71 N002C B21 N007D C71 N002D B21 N008A
' Ell N002A B21 N008B Ell N002B B21 N008C Ell N010A B21 N008D E11 N010B B21 N009A E11 N010C B21 N009B Ell N010D B21 N009C Ell N011A B21 N009D E11 N011B B21 N017A Ell N011C B21 N017B E11 N011D B21 N017C Ell N016A B21 N017D E11 N016B B21 N021A Ell N016C B21 N021B Ell N016D B21 N021C Ell N020A B21 N021D Ell N020B B21 N021E E11 N020C B21 N021F Ell N020D B21 N024A Ell N021A B21 N024B E11 N021B B21 N025A E21 N008A B21 NO2SB E21 N008B B21 N026A E21 N006A B21 N026B E21 N006B B21 NO31A E21 N009A B21 NO31B E21 N009B B21 NO31C E41 N001A*
B21 NO31D E41 N001B*
E41 N001C*
E41 N001D*
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MPL NO.
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B21 N010A E51 N026A E41 N005*
B21 N010B E51 NO26B E41 N006*
B21 N010C E51 N026C E41 N008*
B21 N010D E51 NO26D E41 N010*
B21 N011A E51 N027A E41 N012A*
B21 N011B E51 NO27B E41 N012B*
B21 N011C E51 NO27C E41 N012C*
B21 N011D E51 N027D E41 N012D*
B21 N012A G31 N016A E41 N015A*
B21 N012B G31 N016B E41 N015B*
B21 N013A G31 N016C E41 N017A*
B21 N013B G31 N016D E41 N017B*
B21 N013C G31 N016E E41 N027*
B21 N013D G31 N016F E51 N012A*
G31 N022A E51 N012B*
G31 N022B E51 N012C*
G31 N022C E51 N012D*
G31 N022D E51 N017*
E41 NO30A G31 N022E E51 N018*
E41 NO30B G31 N022F E51 N019A*
E41 N046A G31 N023A E51 N019B*
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E51 N019C*
G31 NO23C E51 N019D*
G31 N023D G31 N012 G31 N023E G31 NO36 G31 N023F G31 N041 E51 NO23A E51 N023B E51 N025A E51 N025B E51 N025C E51 N025D B21 N012C B21 N012D B21 N027 C32 N005A,B E21 N003A,B Ell N015A,B
- Early hPCI/RCIC equipment.
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NAIN STEAM ISOLATION VALVE (MSIV) PILOT SOLENOIDS I
Information is presently not a ?ailable to demonstrate complete acceptability of MSIV pilot solenoids B21-F022A,B,C&D and B21-F028A,B C&D. Data on these solenoid valves is available for IDCA environment testing. An analysis is being performed to qualify these solenoid valves for radiation and aging.
This analysis will be completed by March 31, 1983.
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AUTOMATIC DEPRFaSURIZATION SYSTEM (ADS) SOLENOID VALVES ADS Solenoid Valves B21-F013A,C E.F J,K&L were identified as open items in the previous IEB 79-01B submittals. -
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The System Component Evaluation Work Sheets have been updated accordingly.
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s-VALVE N0 TOR OPERATOR Information is presently not available to demonstrate complete acc6ptability of the valve Motor Operators listed.
Qualified replacements were purchased on purchase orders PEHA-192 and PEHA-199. Installation is scheduled for the Unit 1, Fall, 1982 refueling outage.
APPLICABLE EQUIPMENT E41-HOV F011 E41-MOV F012 e
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s-CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT (HCU) SOLENOIDS HCU Solenoids Cll-Dil7 and D118 were considered open items in the IEB 79-01B submittal..
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Information is presently not available to demonstrate complete a::ceptability
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of the Scram Volume Discharge Pilot Solenoid Valve C11-F009. A qualified
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ASCO NP Series replacement has been purchased on PEHA-50. Design Change I
Request (DCR)79-459 has been issued to facilitate this change. Installation is scheduled for the Unit 1. Fall,91982 refueling outage.
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hAIN STEAM ISOLATION VALVE (MSIV) LIMIT SWITCHES 4.
Qualified NAMCO EA 740 Limit Switches are installed on B21-F022A,B,C&D; however, the installation presently does not include required cable seals tfjimul[tetestconditions. The cable seals and limit switches with a longer
. qualified life will be installed during the Unit 1, Fall,1982 refueling outage.
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e INSTRUMENT CABLE (PANEL INTERNAL WIRING)
During a review of documentation and during a site walkdown, some unidentified wiring was discovered in the G.E. supplied local racks.
The applicable wiring wf.11 be replaced during installation of the Analog Transmitter Trip System.
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EDWIN I. HATCH NUCLEAR PLANT UNIT 1 SECTION B.3.2.1 SU) MARY OF OUTSTANDING ITIMS BALANCE OF PLANT COMPONENTS This section sununarizes the status of the qualification plans for equipment with outstanding items identified on the System Component Evaluation Work Sheets for the Balance of Plant Components.
It should be noted that some equipment in the Balance of Plant Scope is being replaced as part of the General Electric Analog Transmitter Trip System Program. This equipment is shown in Section B.3.2.2, Summary of Outstanding Items for Nuclear Steam Sdpply System Equipment.
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DC MOTOR STARTER R27-S035 This starter was identified as an open item in the previous IEB 79-01B
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submittals.
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DC }cr0R CONTROL CENTER R24-S021 This Motor control Center was identified as an open item in the previous IEB 79-01B submittals. The power and control for the applicable equipment, valves E51-F008 and F013, have been relocated to local starter R24-S021A.
Local starter R24-S021A is qualified for its environment; therefore,
{$g R24-S021A has been added to the submittal, shown as qualified, and R24-S021 has been deleted.
NOV 2 41952 2
4, t VALVE MfYrOR OPERATORS Information is presently not available to demonstrate complete acceptability of the Valve Motor Operators listed. Qualified replacements were purchased on purchase orders PEHA-192 and PEHA-199.
Installation of the replacement valve motor operators is scheduled for the Unit 1, Fall, 1982 refubling outage.
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APPLICABLE EQUIPMENT - VALVE MOTOR OPERATORS B21-MOV-F019 E11-MOV-F004D -
E11-MOV-F008 E11-MOV-F009 Ell-MOV-F021A Ell-MOV-F021B Ell-MOV-F022 E11-MOV-F028A,B Ell-MOV-F075A E21-MOV-F004A E21-MOV-F004B E21-MOV-F005A E21-MOV-F005B E41-MOV-F001 E41-MOV-F003 E41-MOV-F006 E41-MOV-F007 E41-MOV-F041 E51-MOV-F008 i
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E51-MOV-F031 G31-MOV-F001 G31-MOV-F004 PS2-MOV-F875 E11-MOV-F026A 3A NOV 2 41982
INSTRUMElfr CABLE M2-16. N1-4. H1-16, M5-20 and N3-03 Instrument Cable Types M2-16, N1-4, H1-16, MS-20 and N3-03 will be replaced by qualified Cable Types M08 (Brand Rex),.N01 (Brand Rex), H04 (Anaconda, FREP), M19 (Brand Rex), and N09(Anaconda) respectively.
Design Change Request-(DCR)80-430 has been issued to facilitate this chanke-Installation of the replacement cable is scheduled for the Unit 1.Fa11, 1982 refueling outage.
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INSTRUMENTATION CABLE N3-04 As a re~sult of the EOP review, cable type N3-04 has been added to the IEB 79-01B submittal. Documentation has been received which qualifies this instrumentation cable.
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,o VAIf0R SOLENOID VALVES (TMI)
The Valcor Solenoid Valves listed below were purchased for TMI purposes on PEH 2-6957. The valves were tested to IEEE 323-1974, but coments on the test report have not yet been resolved by the Vendor. The valves will be delivered af ter all coments on the test report have been resolved.
Installation is scheduled for the Unit 1, Fall,1982 refueling outage.
Applicab.1e Equipment B21-SV F111 B21-SV F112 E41-SV F121 E41-SV F122 6
N O V 2., 1982
1-I STATIC O RING PRESSURE SWITCHES (THI)
Information is presently not available to demonstrate complete acceptability of the pressure ewitches listed below. The components will be replaced by Qualified Pressure Controls,-Inc. A17-1P Pressure Switches. The switches were ordered on PEHA-52, and have been delivered to the jobsite. Design Change Request (DCR)79-436 has been issued to facilitate this change.
Instal-lation of the qualified pressure switches is scheduled for Unit 1 Fall,1982 refueling outage.
Applicable Equipment B21-PS N301A,B,C,D,E,F G,H,J,K,L l
7 NOV 2 4 f982
LIMIT SWITCHES (GENERIC)
Information is not presently available to demonstrate complete acceptability of the limit switches listed. Qualified Limit.9 witches, NAMCO EA 180 Series and EA 740 Series with operating lever assemblies, were ordered on PEHA-91.
Limit switch mounting brackets were ordered on PEHA-75 (Fisher Actuators),
PEllA-104 (Crane Valves), and PEHA-133 (Bettis Actuators) and have been,
shipped to the jobsite. Design Change Request (DCR)80-203 has been issued to facilitate this change. Installation of the qualified equipment is scheduled for the Unit 1 Fall, 1982 refueling outage.
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Applicable Equipment - Limit Switches MPk_]Ih MPL No.
MPL No.
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B31-F019 P33-F014 M3
,Miel P33-F015 T48-F310 E11-F065A P41-F066 T48-F311 E11-F065B P41-F067
^MN E11-F065G P70-F002 T48-F319 E11-F065D P70-F003 T48-F320 E21-F006A P70-F004 y
E21-F0068 P70-F00 E21-F019A T481F E21-F019B E21-F037A T41-F023B J
E21-F037B T41-F031A i,M.
iM3 T41-F031B T48-F332A E41-F026 T41-F032A T48-F332B
( M W E f4 T41-F0328 T48-F333A E41-F029 7
T48-F3338 (M3%
h T48-F334A E51-F003 T46-F001A T48-F334B G11-F003 T46-F001B T48-F335A G11-F004 T46-F002A T48-F335B (StaM191W T46-F002B E11-F122A,B G11-F020 T46-F003A C51-F011 P33-F002 T46-F003B G51-F012 P33-F003 T46-F004A G51-F013 (53SiWO4?M T46-F004B G51-F021 P33-F006 T46-F005
- T41-F040A,B P33-F007 M j$
P33-F010 T48-F104
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P33-F012 rlM$
b kneenaal T48-F307 T48-F308 YfN5Ed'isitchiis3haWMIFEp15Eef u n ua-wa a. u s a s is.-; A s - A A,_.
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- Equipment has not been delivered but will be O site in time for Fall 1982 outage.
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Information is presently not available to demonstrate complete acceptability of the pilot solenoid valves listed. Qualified ASCO NP series pilot sole-noids were purchased on PEHA-50 and have been delivered to the jobsite.
Design Change Request (DCR)79-459 has been issued to incorporate this change. Installation of the replacement solenoid valves is scheduled for the Unit 1, Fall, 1982 refueling outage.
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Applicable Equipment - Pilot Solenoid Valves MPL No.
MPL No.
NFL No, B31-F019 P33-F014 T46-F005 B31-F020 P33-F015 W
E11-F051A T48-F104 E11-F051B y
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J E11-F053B E11-F065A E11-F0658 (M830SRpB91!
[T48-307
-F037A E11-F065C P41-F037C T48-F308 E11-F065D T
(368!GMD*)
E21-F006A T48-F310 E21-F006B
[EM=pSNS T48-F311 E21-F019A P41-F040A (MS=WMS*)
E21-F019B P41-F040B T48-F319 E41-F025 P41-F066 E41-F026 P41-F067
%T48-F320@
E41-F028 P70-F002 h.
~A E41-F029 P70-F003 "T48-F324
.f E41-F051 P70-F004 E368EN5 E51-F003 P70-F005 L368=836 i
G11-F003 T'T41pF0113 '
(548-73R7 G11-F004 W
T48-F332A G11-F019 T41-F023B.
T48-F332B G11-F020 T41-F031A T48-F333A P33-F002 T41-F031B T48-F333B P33-F003 T41-F032A T48-F334A P33-F004 T41-F032B T48-F334B P33-F006 fT41MC T48-F335A g19158443$
T48-F335B P33-F007 3
P33-F010 T46-F001A E11-F122A,B P33-F011 T46-IT01B G51-F011 P33-F012 T46-F002A G51-F012 T46-F002B G51-F013 G51-F021
- T41-F040A',B hf*
- Equipment has not been delivered but will be @ the site in time for outage.
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RADIATION SENSORS AND CABLE (TMI)
Information is not available to demonstrate complete acceptability of radiation sensors D11-RE NO22A&B.(including cables J2-03 and J2-04).
The TMI purpose of these components are served by D11-RE N003A,B, Victoreen Model 877-1, with associated Model 878-1-5 cable. The equipment was purchased on PEHA-342. Design Change Request 79-445 has been issued to facilitate this change.-
These radiation sensors and cable are scheduled for installation during the Unit 1, Fall, 1982 refueling outage.
10 NOV 2 41982
H 0 ANALYZERS 2 2 Documentation is not available to demonstrate complete acceptability of the H 0 Analysers (P33-P001A,5). Qualified replacement analyzers were pur-2 2 chased on purchase order PEHA-324 and is scheduled for delivery in November, 1982. Design Change Request (DCR)81-132 has been issued to facilitate these changes. Installation is scheduled for Unit 1, Fall,1982 refueling outage.
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P GE/MAC POWER SUPPLIES Information is not available to demonstrate complete acceptability of the CE/MAC Power Supplies listed. The circuits for these components will be relocated to Class IE power supplies (Foxboro type N)' in the Main Control' Room (mild environment). Replacement power supplies have been ordered on PEHA-49. Design Change Request (DCR)79-439 and 80-412 have been issued to incorporat.
this change. Installation of this equipment is scheduled for the Unit 1 Fall, 1982 refueling outage.
Applicable Equipment T48-E/S K007A,B T48-E/S K008A,B T48-E/S K009B T48-E/S K019A,B T48-E/S K020A,B T48-E/S K001 i
12 NOV 2.,;gg
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TRANSMITTERS (TMI)
Information is not presently available to demonstrate complete acceptability of the transmitters listed. Qualified Rosemount 1153B Series Transmitters have been ordered on PEHA-44. Design Change Requests (DCR)79-439 and 80-412 have been issued to facilitate these changes.
Installation of the replacement transmitters,is scheduled for the Unit 1, Fall, 1982 refueling outage.
Applicable Equipment T48-PT N008B **
T48-PT N009B**
T48-PT N010A,B T48-PT N020A,B T48-PT N003A,B*
T48-LT N021A,B T48-PT N001 T46-DPT N005B,C
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- T48-PT N003A,B is new equipment, purchased for TMI purposes.
- Tag number T48-PT N008B will be replaced by tag number T48-PT N023A. Tag number T48-PT N009B will be eplaced by tag number T48-PT N023B.
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r-BR_00KS FLOW INDI_C_ATOR TRANSMITTERS AND POWER SUPPLIES Information is presently not available to demonstrate complete acceptability of the Flow Indicator Transmitters and Power Supplies listed. These instru-ments are part of a, control loop for T48-HOV F112A, B which is being replaced by a needle valve. Once the needle valve is installed and the control circuit is disconnected, these flow transmitters and power supplies will be deleted from IEB 79-01B. Design Change Request (DCR)81-196, Rev. 2 has been issued to facilitate this change.
This equipment is scheduled for installation during the Fall-1982 outage, however, due to delivery problems, the completion of the work may be delayed until the Fall 1984 outage.
Applicable Equipment T48-F1T N014A,B T48-E/S K011A,B NOV 241982 14
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VALVE HYDRAULIC OPERATORS Information is presently not available to demonstrate complete acceptability of Valve Hydraulic Operators T48-HOV F112A and B.
The valves will be replaced by manual needle valves set at the required flow rate.
Design Change Request (DCR)81-196, Rev. 2 has been issued to facilitate this change. Present forecasts are for the equipment to be replaced during the Unit 1, Fall,1982 refueling outage. T48-F112A,B will then be deleted from 79-01B since it will be a piece of mechanical equipment.
Delivery problems may cause the completion of this work to be postponed until the Fall 1984 outage.
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DISTRIBifrION PANEIS R24-S011/S012 AND DRY 'IYPE TRANEFORMERS R11-5039/SO40 Information is presently not available to demonstrate complete acceptability of the control power feeds to the H 0 Analyzer Panels (P33-P001A,B). The 22 existing control power feeds will be spared out and qualified ones will be added. This change will be completed as part of the H &0 Analyzer Design 2
2 Change Request (DCR) Package.
V0V 2 4 tseg 16
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- PRESSURE & DIFFERENTIAL PRESSURE SWITCHES-There is presently not enough information to demonstrate complete acceptability of switches listed below. These switches are being replaced by qualified Rosemount transmitters which were ordered on purchase order PEHA-44. Design Change Request (DCR)81-196 has been issued to facilitate this change.
Installation is scheduled for the Unit 1, Fall,1982 refueling outage, however, due to delivery problems, the completion of this work may be delayed until the
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Fall 1934 outage.
Applicable Equipment T48-DPS N210 T48-DPS N211 PS2-PS N021 O
e NOV 2 41982 17
.. '. '.-*I TDI LEMENTS v
There is presently not enough information to demonstrate complete acceptability of the temperature elements listed below.
These temperature elements are being-replaced by qualified PYC0 RTDS which were ordered on purchase order PEHA-102,
' Design Change Request (DCR)81-196 has been issued to facilitate this change, Installation is scheduled for the Unit 1. Fall,,1982 refueling outage, however,
-due to delivery problems, the completion of this work may be delayed until the Fall 1984 outage.
et Applicable Equipment T48-TE N009A,B,C D T47-TE N005 T47-TE N008 y
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TEMPERATURE INDICATING SWITCHES There is presently not enough information to demonstrate complete acceptability of the temperature indicating switches listed below. These temperature indicating switches are being replaced by qualified PYC0 RTDS which were ordered on purchase order PEHA-44. Design Change Request (DCR)81-196 has been issued to facilitate this change installation is. scheduled for the Unit 1, Fall,1982. refueling outage, however, due to delivery problems the completion of this work may be delayed until the Fall 1984 outage.
Applicable Equipment T41-TIS N019A,B T41-TIS N020A,B T41-TIS N021A,B T41-TIS N022A,B e
i 19 NOV 2 4 M92 i
t f
r s-EDWIN I. HATCH NUCLEAR PLANT UNIT 2 SIX: TION B.3.2.2
SUMMARY
OF OUTSTANDING ITEMS NUCLEAR STEAM SUPPLY SYSTEM COMPONENTS 1
This section summarizes the status of the qualification efforts for equip-ment with outstanding items identified on the System Component Evaluation Work Sheets for the Nuclear Steam Supply System Components.
i N O V k.
- 1982
RHR AND CORE SPRAY PUMP MOTORS TheRHNandCureSprayPumpMotorswereidentifiedasopenitemsinpreviousIEB 79-01B submittals.
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The System Component Evaluation Work Sheets have been revised accordingly.
Applicable Equipment 2 E11-C002A, B,C,D 2 E21-C001A,B i
1 I
1 N O V 2 4 1992
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t Information is presently not available to 'de'noaytrate complet$:Ac uPtsbility e
3 4
of the HPCI Turbine Controls (2E41-c002). General Electric.his provided Georgia '
i 1
c Power Company with partial qualificat' ion test detsp but su' planentary idforma-p tion will be needed to qualify the equipment for aging and radiecion. A walkdor.1 of the HPCI Turbine was completed the week of March 22, 1987, and an; analysis,
'f s i-1 is presently being performed to qualify the individ'ual ccmponente for aging i
/
r and radiation. This analysis is scheduled for completion by Oc.tober^ 31,1982.
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/ITI,0MATIC DEPRESSURIZATION SYSTDI (ADS) SOLENOID VALVES L
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olenoid Valves 2B21-F013A,C,E,H,K,L,M were identified as open items in ADS the previour. IEB 79-01B submittals. g f i
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The System Component Evaluation Work. Sheets have been updated accordingly.
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D 2 1932
ANALOG TRANSMITTER TRIP SYSTDI Informa' tion is presently not available to demonstrate complete acceptability of tLa equipment listed. The equipment will be replaced with an Analog Trans-mitter Trip System (ATTS). A letter of intent has been issued to the supplier (G.E.) for purchase of the system (April 22, 1981). The equipment is presently undergoing qualification testing to IEEE 323-1974/NUREG-0588, Category I.
Qualification of ATTS equipment will be achieved in two (2) phases. Phase I will qualify the equipment for a qualified life of 2-5 years, which will be complete prior to delivery. Phase II will qualify the ATTS equipment for a 40 year life and will be completed prior to end of the 2-5 year qualified life.
Design Change Request (DCR)81-139 has been issued to facilitate this change.
Installation is scheduled for the Unit 2, Spring, 1983 refueling outage.
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NOV 2 41982
l :.
APPLICABLE EQUIPMENT - ANALOG TRANSMITTER TRIP SYSTEM MPL NO.
MPL NO.
2B21-N006A 2C71-N002C 2B21-N0065 2C71-N002D 2821-N006C 2E11-N002A 2B21-N006D 2E11-N002B 2B21-N007A 2E11-N010A 2B21-N0078 iE11-N0108 2821-N007C 2E11-N010C 2B21-N007D 2E11-N010D 2B21-N008A 2E11-N011A 2B21-N008B 2E11-N0118 2B21-N008C 2E11-N011C 2B21-N008D 2E11-N011D 2821-N009A 2E11-N016A 2821-N009B 2E11-N016B 2B21-N009C 2E11-N016C 2B21-N009D 2E11'N016D 2B21-N017A 2E11-N020A 2B21-N017B 2E11-N020B 2821-N017C 2E11-N020C 2B21-N017D 2E11-N020D 2B21-N021A 2E11-N021A 2B21-N021B 2E11-N021B 2B21-N021C 2E21-N006A 2B21-N021D 2E21-N006B 2B21-N021E 2E21-N008A 2B21-N021F 2E21-N008B 2B21-N024A 2E21-N009A 2B21-N024B 2E21-N009B 2B21-N025A 2E41-N001A 2B21-N025B 2E41-N001B 2B21-N026A 2E41-N001C 2B21-N026B 2E41-N001D 2B21-NO31A 2E41-N004 2821-N031B 2E41-N005 2B21-NO31C 2E41-N006 2B21-NO31D 2E41-N008 2B21-NO36 2E41-N010 2821-NO37 2E41-N012A 2B21-N042A 2E41-N012B 2821-N0428 2E41-N012C 2C71-N002A 2C71-N002B 2B21-K027 2B21-N051A,B 2E21-N003A,B 4A NOV24 Gd2
- APPLICABLE EQUIPMENT - ANAIAG TRANSMITTER TRIP SYSTEM MPL NO.
MPL, NO.
2B21-N013A 2E41-N015A 2B21-N0138 2E41-N0155 2B21-N013C 2E41-N017A 2B21-N013D 2E41-N017B 2E41-N030A 2E41-N027 2E41-N030B 2E51-N012A 2E41-N046A 2E51-N012B 2E41-N046B 2E51-N012C 2E51-N012D 2E51-N017 2E51-N018 2E51-N019A 2E51-N023A 2E51-N019B 2E51-N023B 2E51-N019C 2E51-N025A 2E51-N019D 2E51-N025B 2G31-N012 2E51-N025C 2G31-NO36 2E51-N025D 2G31-N041 2E51-N026A 2E32-N050 2E51-N026B 2E32-N051B 2E51-N026C 2E32-N051F 2E51-N026D 2E32-N051K 2E51-N027A 2E32-N051P 2E51-N027B 2E32-N058 2E51-N027C 2E32-N060 2E51-N027D 2E32-N061B 2G31-N016A 2E32-N061F 2G31-N016B 2E32-N061K 2G31-N016C 2E32-N061P 2G31-N016D 2G31-N016E j
2G31-N016F 2B21-N010A 2G31-N022A 2B21-N010B 2G31-N0228 2B21-N010C 2G31-N022C 2B21-N010D 2G31-N022D 2B21-N011A 2G31-N022E 2B21-N011B 2G31-N0*2F 2B21-N011C 2G31-N023A 2B21-N011D 2G31-N023B 2B21-N012A 2G31-N023C 2B21-N012B 2G31-N023D 2B21-N012C 2G31-N023E 2B21-N012D 2G31-N023F
' 2 : tis 2 4B
VALVE MOTOR OPERATOR Information is presently not available to demonstrate complete acceptability of the following valve motor operators:
2B31-MOV-F031A 2B31-MOV-F031B 2E41-MOV-F011 2E41-MOV-F012 Qualified replacements were purchased on PEHA-192 and PEHA-199. The replacements are scheduled for installation during the Unit 2, Spring,1983 refueling outage.
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NOV 2 41982 5
CONTROL ROD DRIVE HYDRAULIC CONTROL UNIT (HCU) SOL 50 IDS HCU Solenoids 2C11-D117 and D118 are presently considered open items in the IEB 79-01B submittal.
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6 NOV 241.392
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SCRAM VOLUME DISCHARGE PITAT SOLENOID Information is presently not available to demonstrate complete acceptability of the Scram Volume Discharge Pilot Solenoid Valve 2C11-F009. A qualified ASCO NP Series replacement has been purchased on PEH2-5744. Design Change Request (DCR)79-460 has been issued to facilitate this change. TTlity;
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_ vatse assitestattadid,rt=8;the thatt.E tag The system component evaluation worksheet will be revised to reflect this change.
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NOV 2 41982
WIN STEAM ISOLATION VALVE PILOT SOLENOIDS Information is presently not available to demonstrate complete acceptability of 2B21-F022A,B,C&D and 2B21-F028A,B,C&D. Replacements have been ordered on PEH2-5744. Design Change Request (DCR)79-460 has been issued to facilitate
. - - ~ _ _
this change.TW,^6DMEMW11pos spesejinstsiled during %
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- k.M j k @,11983l.1tefuelinglestage. The system component evaluation worksheets will be revised to show this change.
8 N O V 2 4 19 92
,v-HAIN STEAM ISOLATION VALVE (MSIV) LIMIT SWITCHES Qualified NAMCO EA 740 Limit Switches are installed on 2B21-F022A,B,C&D and 2B21-F028A,B,C&D; however, the installation did not include required cable seals to simulate test conditions. i
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The system component evaluation worksheets 8ib4_.w-uma-a_
will be revised to refelet this change.
NOV 2 4 ;42 9
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MAIN STEAM ISOIATION VALVE (MSIV) LEAKAGE CONTROL SYSTEM BLOWER MOTORS Information is presently not available to demon-trate complete acceptability
~
of motors 2E32-C001 and 2E32-C002A,E. Qualification documentation is being provided by General Eeletric Company, which will satisfy the qualification requirements for this equipment. An environmental qualification report evaluation will be filled out and the system component evaluation worksheets revised upon receipt of this documentation.
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MAIN STEAM ISOLATION VALVE (MSIV) LEAKAGE CONTROL SYSTDI FLOW ELEMENTS Information is presently not available to demonstrate complete acceptability of 2E32-FE N006B,F,K&P. Qualification testing was performed on this,
equipment;butsufficienttestdataforagingand[adiationisnotavailable.
A material analysis is being performed to qualify the flow element for aging and radiation.. Completion of this analysis is scheduled for early 1983.
9 a
e 11 4 1982
1-no.
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MAIN STEAM ISOLATION VALVE (MSIV) LEAKAGE CONTROL SYSTEM HEATERS Information was not available to demonstrate complete acceptability of Heaters 2E32-D001.B F,K,P.
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EDWIN I. HATCH NUCLEAR PIANT UNIT 2 SECTION 3.3.2.1
SUMMARY
OF OUTSTANDING IT1!MS BAIANCE OF PIANT COMPONENTS This section sumarizes the status of the qualification plans for equipment with outstanding items identified on the System Component Evaluation Work Sheets for the Balance of Plant Components.
It should be noted that some equipment in the Balance of Plant Scope is being replaced as part of the General Electric Analog Transmitter Trip System Program. This equipment is shown in Section B.3.2.2, Summary of Outstanding Items for Nuclear Steam Supply System component.
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NOV 2 4 0 92
D.C. MOTOR STARTER 2R27-SO93 This starter was identified as an open item in the previous IEB 79-01B n.
submittals.
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relocation
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VALVE M(yIOR OPERATORS Information is presently not available to demonstrate complete acceptability,
of the Valve Motor Operators listed. Qualified replacements were purchased on purchase orders PEHA-192 and PEHA-199. The replacements are scheduled for installation during the Unit 2 Spring, 1983 refueling outage.
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APPLIC_A_BLE EQUIPMENT - VALVE MOTOR _ OPERATORS 2E11-MOV-F003A 2E11-MOV-F008 2E11-MOV-F015A 2E11-MOV-F015B 2E11-MOV-F016A 2E11-M0V-F016B 2E11;MOV-F021A 2E11-MOV-F021B l
2E11-MOV-F028A,B 2E11-MOV-F075B 2E21-MOV-F004A 2E21-MOV-F004B 2E21-MOV-F005A 2E21-MOV-F005B 2E32-MOV-F002B,F,E,P 2E32-MOV-F006 2E32-MOV-F007 2E32-MOV-F008 2E32-MOV-F009 2E41-MOV-F004 2E41-MOV-F006 2E41-MOV-F008 2E41-MOV-F042 2E51-MOV-F013 2E51-H0V-F031 2PS2-MOV-F565 2B21-H0V-F016 2E41-MOV-F007 I
2E11-MOV-F007A,B 2E11-MOV-F027A I
2A NOV 2 41992
TRANSMITTERS (TMI)
Information is not presently available to demonstrate complete acceptability of the transmitters listed. Replacment qualified Rosemount 1153B Series.
Transmitters have been ordered on PEH2-511. Design Change Requests (DCR)79-440 and 81-22 have b'een issued to facilitate these changes.
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a The system component evaluation worksheets will be revised to show this change.
Applicable Equipment t
2T48-LT N010A l
l 2T48-PT NO20A,B l
2T48-PT N003A,B*
2T48-LT N021A 2T48-PT N023A,B F
2T48-PT N003A,3 is new equipment purchased for TMI purposes.
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VAILOP. SOLEN 0ID VALVES (TMI)
The Val or Solenoid Valves listed below were purchased for TMI purposes on PEH 2-6957. The valves were tested to IEEE 323-1974, but final comments on the test report have not yet been resolved,by the Vendor. The valves will be delivered after all comments on the test report have b'een r; solved.
Instal-lation is scheduled for the Unit 2. Spring, 1983 refueling outage.
Applicable Equipment-2B21-SV Fill 2B21-SV F112 2E41-SV F121 2E41-SV F122 e
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T 8
4
_ STATIC 0 RING PRESSURE SWITCHES (TMI)
Information is presently not available to demonstrate complete acceptability of the pressure switches listed below. The components will be replaced by Qualified Pressure Controls, Inc. A17-1P Pressure Switches which were ordered on PEH2-6924 and have been delivered to the jobsite. Design Change Request (DCR)79-437 has been issued to facilitate this change.
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The system component evaluation vorksheets will be
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revised to show this change.
Applicable Equipment 2B21-PS N301A,B.C,D,E,F,G,H,K,L,M f
5 NOV 2 41982
.t LIMIT SWITCHES (CENERIC)
Information is not presently available to demonstrate complete acceptability of the limit switches listed. Qualified Limit. Switches, NANCO EA 180 Series and FA 740 Series with operating lever assemblies, were ordered on PEH2-6956 Limit switch mounting brackets were ordered on PEH2-270 (Fisher Actuators),
PEHA-134 (Bettis Actuators), and PEHA-132 (Masoneilan actuators) and have been shipped to the jobsite. Design Change Request (DCR)80-204 has been issued to facilitate this change.
The system component evaluation worksheets will be revised to show this chans,e.
The valves marked with a double asterisk (**) do not have qualified limit switches delivered to the site. Equalified limit switches & brackets will be ordered and installed after receipt @ the site,but installed no later than the unit 2 spring 1983 refueling outage.
6 NOV 2 4 ua2
i Applicable Equipment - 14mit Switdbes MPL No.
MPL No.
MPL No.
2B21-F076A 2P33-F011 2T48-F324 2B21-F0768 2F33-F012 2T48-F325 2821-F077A 2P33-F013 2T48-F326 2B21-F0778 2P33-F014 2T48-F327 2331-F019 2P33-F015 2T48-F332A 2831-F020 2P41-F066 2T48-73328 2D11-F050 2 P41-F067 2T48-F333A 2D11-F051 2P70-F001 2T48-F333B 2D11-F052 2P70-F002 2T48-F334A 2D11-F053 2P70-F003 2T48-F334B 2E11-F065A 2P70-F004 2T48-F335A 2 11-F0653 2P70-F005 2T48-F335B 2E11-F065C 2T41-F003B 2T48-F338 2E11-F065D 2T41-F011B 2T48-F339 2E21-F019A 2T41-F023A 2T48-F340 2 E21-F0193 2T46-F001B 2T48-F341 2541-F025 2T48-F103 2E11-F12 2A,B 2 E41-F026 2T48-F104 2E21-F037A,B 2 E41-F028 2T48-F113 2T48-F361A,B 2E41-F029 2T48-F114 2T48-F362A,B 2E41-F051 2T48-F115 2T48-F364A,B 2 E51-F003 2T48-F116 2T48-F363A 2G51-F017 2T48-F118A 2T48-F363B 2P33-F002 2T48-F1185 2G51-F011 2 P33-F003 2T48-F307 2G51-F012
- 2E11-F041A,B,C,D 2T48-F319 2T48-F209 *
- 2E 11-F040A, B,C,D 2T48-F322 2T48-F212 *
- These limit switches were previously thought to be qualified but were discovered not to be.
Replacements were purchased and installed during the Unit 2, Spring, 1982 refueling outage.
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- See sheet 6 for explaination.
6A NOV i s 333g i
.t PITET SOLENOID VALVES (GENERIC)
Information is presently not available to demonstrate complete acceptability of the pilot solenoid valves listed. Qualified ASCO NP series pilot erle-s noids were purchased on PEH2-5744 and have been delivered to the jobsite.
Design Change Request (DCR)79-460 has been issued to incorporate this change.
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The valves marked with an asterisk (*) do not have qualified solenoid valves delivered to the site. Equalified solenoid valves will be ordered and installed after receipt @ the site, but installed no later than the Unit 2, spring, 1983 refueling outage.
7 V 2 4 199P
r APPLICABIZ F.QUIPMENT - PIIDT SOLENDIDS MPL EL MFL 100.
WPL NO.
2B31-F019 2G51-F013 2T41-F023A 2831-F020 2P33-F002 2T46-F0018 2D11-F050 2P33-F003 2T48-F103 2D11-F051 2P33-F004 2T48-F104 2D11-F052 2P33-F005 2T48-F113 l
2D11-F053 2P33-F006 2T48-F114 2E11-F051A 2P33-F007 2T48-F115 2E11-F051B 2P33-F010 2T48-F116 2E11-F053A 2P33-F011 2T48-F118A 2E11-F053B 2P33-F012 2T48-F118B 2E11-F065A 2P33-F013 2T48-F209 2E11-70653 2P33-F014 2T48-F210 2E11-F065C 2P33-F015 2T48-F211 2E11-F065D 2P41-F035A 2T48-F212 2E21-F019A 2P41-F035B 2T48-F307 2E21-F019B 2P41-F036A 2T48-F308 2E41-F025 2P41-F036B 2T48-F309 2E41-F026 2P41-F037A 2T48-F310 2E41-F028 2P41-F037B 2T48-F311 2E41-F029 2P41-F037C.
2T48-F318 2E41-F051 2P41-F037D.
2T48-F319 2E51-F003 2P41-F059A 2T48-F320 2G11-F003 2P41-F089B.
2T48-F321 2G11-F004 2P41-F040A 2T48-F322 l
2G11-F019 2P41-F040B 2T48-F324 2G11-F020 2P41-F066 2T48-F325 2G51-F011 2P41-F067 2T48-F326 2G51-F012 2P70-F001 2T48-F327 2B21-F076A 2P70-F002 2T48-F332A 2B21-F076B 2P70-F003 2T48-F332B 2B21-F077A 2P70-F004 2T48-F333A 2B21-F077B 2P70-F005 2T48-F333B
- 2E11-F213' 2T41-F003B 2T48-F334A
- 2E11-F214 2T41-F011B 2T48-F334B
- 2E11-F215 2E11-F122A,B 2T48-F335A
- 2E11-F216 2E21-F037A,B 2T48-F335B
- 2P33-F017 2T48-F370 2T48-F374 2T48-F371 2T48-F375 2T48-F372 2T48-F376-2T48-F377 2T48-F378 2T48-F379 2T48-F380 2G51-F017 7A NOV 2 4 1982
RADIATION SENSORS AND CABLE (TMI)
Information is not available to demonstrate complete acceptability of radiation sensors 2D11-RE NO22A&B and associated cable J03 and J04. The TMI purpose of these components will be served by 2D11-RE N003A,B, Victoreen Model 877-1, with associated Model 878-1-5 cable. The equipment was purchased on PEH2-6930. Design Change Request 79-446 has been issued to facilitate this change.
M if M I M M TeiitT M M inst &11 F eiha~g M ' d 3
}w e o W.; N W A. The system component eveluation worksheets 4 amasaaaumuwx-e.N w a s.,e I
will be revised to show this change.
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NOV 2 41302 B
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H 02 ANALYZERS 2
Documentation is not available to demonstrate complete acceptability of the H 02 Analysers (2P33-P001A,B). Qualified replacement analyzers were purchased 2
on Purchase Order PEHA-323 and is scheduled for delivery in November, 1982.
The replacement analyzers will be installed during the next Unit 2 refueling nutage scheduled for Spring 1983.
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OY 2 4 1982 9
7 1
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BUCHANAN PHENOLIC TERMINAL BIACKS Information is presently not available to demonstrate complete acceptability of the Buchanan Phenolic Terminal Blocks. ' Additional materials information has been received from the vendor and an evaluation is underway to determine qualification by analysis and comparison with tested terminal blocks.
I 10 2 4 1982
I POWER SUPPLIES The equipment listed was added as a result of the Emergency Operating Procedure (EOP) Review. Information is presently notavailable to demonstrate com-plete qualification.
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- e____:es N 11ag 3,8444 Design Change u ~.--
l Requests (DCR)79-440 and 81-22 were issued t'o facilitate this change. The system component evaluation Sorksheets will be updated to show that the replace-ments power supplies were relocated to a mild environment.
Applicable Equipment l
2T48-E/S K007A,B 2T48-E/S K009A,B 2T48-E/S K019A,B 2T48-E/S K020A,n e
11 NOV 2 4 ggy I
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-r DIFFERENTIAL-PRESSURE SWITCHES
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r of dP switches 2T48-DPS N210& N211. These pressuro(afiite'h6n' are br:ing replacety 4,.
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by qualified Rosemount dP11ransmitters which were ofdered on Purchase Order; 3
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a PEH2-511. Design Change'Reques't (DCR).82-004 has been 'theued-to' facilitate a !
e t '
a this change.
Installation is scheduled for the Unit 2,'ispring,1983 refueling 3
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' $ ),y JiIere.is presently not enough information to demonstrate complete acceptability
.y.
i,
'W (g,., M
.af the temperature elements listed below. These temperature elements are being y
u e
/
ireplaced by Qualified PYC0 RTDs which were ordered on Purchase Order PEH2-6959.
t c, " Design' Change. Request (DCR)82-004 has been issued to facilitate this change.
z d ' Installation is ' scheduled for the Unit 2, Spring,1983 refueling outage.
_A
>w o..
.L.
-/s 7=
Applicable Equipment f ;
e.-
2T48-TE N009A,B,C W.g x...,
/
2T47-TE N007
,w.,
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g 9' i
e NOV 2 4 q 13 w
- - - - -I
- . \\
,4 r
e 6
- EDWIN I. IIATCH NUCLEAR PLANT UNIT 1 D
SECTION 3.3.1.2 JUSTIFICATION FOR CONTINUED OPERATION NUCLEAR STEAM SUPPLY COMPONENTS
-O t
NOV 2 41982
l.,,*l 4
Y EDWIN I. HATCH NUCLEAR PLANT j
-ITEM BY ITDI
.1
' JUSTIFICATION FOR CONTINUED OPERATION NUCLEAR STEAM SUPPLY SYSTEM COMPONENTS 9
- 4. :.;
~
1 4
7
'B'31-N018 A&B -
These instruments provide overpressure ~ protection for the RHR system piping by closing and/or preventing the opening ~of the RHR shutdown: cooling and the reactor head spray valves if the reactor pressure is above a-preset-value.
.The switches could.beisubjected to a harsh environment -due to radiation after-a-LOCA. Documentation to demonstrate complete qualification of-the switches in the radiation environment can not be-located. :A failure of the' switches,could prevent the' operator from bding.able;to,open the, shutdown cooling isolatien valves (2 Ell-F008 and 2 Ell-F009).- If'the valves cannot-be opened, the operator can establish shutdown cooling by use of:the 1 alternate shutdown cooling mode of operation which is described in section 6.2.6 of'the General Electric Line Break Evaluation.
The switches could experience a harsh environment due to temperature and steam in the event of a HELB. The potential failure will not.cause the valves to which they are interlocked to go open; therefore, the RHR system integrity will be maintained. The failure of the switches could prevent the remote manual' opening of the shutdown cooling isolation valves in which case the alternate shutdown cooling made of operation will be utilized.
Based on the above, continued station operation is justified.
4a O 2 4 n 93
A 4 t
6 EDWIN I. HATCH NUCLEAR PLANT UNIT 2 SECTION B.3.1.2 9
JUSTIFICATION FOR CONTINUED OPERATION NUCLEAR STEAM SUPPLY COMPONENTS O
1 I
j e
i r
NOV 2 4 1993
1 o G EDWIN I. HATCH NUCLEAR PLANT ITEM BY ITEM JUSTIFICATION FOR CONTINUED OPERATION NUCLEAR STEAM SUPPLY SYSTDi COMPONENTS l
l l
i
-This piece of equipment has been used during normal operation in plants similar i
to Ratch 2 for the past eleven (11) years. To date, no age related common mode failures have been reoorted. These devices have experienced relatively i
limited service in Hatch 2 as they have been used during normal operation for only three (3) years. With this limited service this equipment is not expected to fail before replacement.
Based on the-above, continued operation is justified'.
'2R21-N042 A6a These instrument provide an ADS permissive signal on low RFV water level which is They will be subjected t'o a harsh environment due to radia-only required post LOCA.
tion but will have served its safety function prior to any significant irradiation.
This piece of equipment has been used during normal operation in plants similar to Hatch 2 for the past eleven (11) years. To date, no age related common mode failures have been reported. These devices have experienced relatively limited service in Hatch 2 as they have been used during normal operation for l
o,nly three(3) years. With this limited service this equipment is not expected I
to fail before replacement.
Based on the above, continued operation is justified.
l i
t NOV 2 4 gggg 6a
r
.s 2B31-N018 A&B These instruments provide overpressure protection for the RHR system piping by closing and/or preventing the opening of the RHR shutdown cooling and the reactor head spray valves if the reactor pressure is above a preset value.
The switches could lbe subjected to a harsh environment due to radiation after a LOCA. Documentation to demonstrate complete qualification of the switches in the radiation environment can not be located. A failure of the switches could prevent the operator from being able to open the shutdown cooling isolation valves (2E11-F008 and 2 Ell-F009).
If the valves cannot be opened, the operator can establish shutdown cooling by use of the alternate shutdown cooling mode of operation which is described in section 6.2.6 of the General Electric Line Break Evaluation.
The switches could experience a harsh environment due to temperature and st am in the event of a HELB. The potential failure will not cause the valves to which they are interlocked to go open; therefore, the RHR system integrity will be maintained.
The failure of the switches could prevent the remote manual opening of the shutdown cooling isolation valves in which case the alternate shutdown cooling made of operation will be utilized.
Based on the above, continued station operation is justified.
U i
l 6b 40y g 4 1932 L
l l
L
i
- r 2B21-N036, 2B21-N037-n ese
- instruments provide a containment spray permissive signal and provide shroud water level indication. H e accident analysis does not take credit for the containment spray function of the RER system, therefore, the containment spray permissive function of the instruments is not required to assure plant safety.
The indication function ~ of the instrument could be affected by the high radiation condition post LCOA. If the indication becomes erratic or ambiguous, the operator will turn on all of the low pressure ECCS systems thus filling the RPV and open one or more SRV's to allow the ECCS flow to spill out the relief valves to the suppression chamber. H is operation assures adequate core cooling.
This piece of equipment has been used during normal operation in plants similar-to Hatch 2 for the past 11 years. To date, no age related common mode failures have been reported. These devices have experienced relatively limited service in Hatch 2 as they have been used during normal operation for only 3 years.
With this limited service, this equipment is not expected to fail before replacement.
Based on the above, continued operation is justified.
2C11-D117, 2C11-D118, 2011-F009 Valves 2C11-D117 and.2C11-D118 are the scram solenoid and valve 2C11-F009 is the scram discharge volume vent and drain pilot solenoid valve. The solenoid for these valves have adequate documentation in all areas except radiation and aging.
The subject valves will not be subjected to a high radiation condition unless there is a LOCA. A IACA signal will cause the valves to be deenergized far before there is high radiation. Ow e the valves have operated there is no need for future operation.
During a HELB event the valves will not be subjected to a harsh environmew due to radiation; therefore, they are assumed to operate as designed.
The ASCO scIam solenoid pilot valve used in qualification testing had according to the test reports, been in use in the tast area for "several years" before the testing was started. The only component in this piece of equipment that is l
susceptible to affects of aging or radiation is the diaphram. It has been reconsnanded to the utilities that all elastomers be replaced after 7 yeaus of service. Kits for renewal of elastomers have been made available to ths utilities for'this purpose.
Based on the above, continue,d operation is justified.
2C71-N002 A-D l
These instruments monitor drywell pressure and provide a scram signal on high l
drywell pressure.
l
' 0 V 2 -; 13e 7
a.
m e-thit i Master List 1\\
Eneet 1 Ef 1 2
~.'
d.
REV 2 (Class IE E10ctrical Equipment Required t's Function Ibder Postulated Accident Conditio SYSTEM: T41C-Reacter Zone Ventilation and Reacter Building Refueling Floor Ventilation System (Isolation Only)
COMPONENTS FIANT DENTIFICATION NUMBER GENERIC NAME 14 CATION INSIDE DRYWELL OUISDE DRYWELL T41-arm 7-F011R Limit Sv./ Pilot Scl.
X OI T41-A0V-F023A.B Limit Sw./ Pilot Sol.
X OI T41-A0V-F031A,B Limit Sw./ Pilot Sol.
X OI T41-A0V-F032A.B Limit Sv./ Pilot Sol.
X OI T41-A0V-F044A.B Limit Sv./ Pilot Sol.
X OI C4-14T,_
Control Cable C7-14T X
C Control cable States Tvoe NT X
C Teminal Block Terminal Tape X
C Insulatine Tane X
C Jacketing Tape Protective Tane T & B 2RB14 X
C Insulated Wire Splice Y
C T & B 2RR14Y Ynentated Ufve Snifce T A R RR1410Y Y
C Tnci,1 a red Tem _ cann.
y C
TAR 14RR10Y Tncul ated Tem Conn.
wr none she< nd Y_,,,,
C ver, A cakt. n1..vo T41-A0V F040A,B
' Limit Sw.
Y C
Isol. Valve x,,,,
01l V0V 2 41982
u u. LInc Nuclear Plant - thtt 1 System W Iveluetten 1Rork S M Z. E M" """
ENVIROMPENT DOCINNIATEDN REF*
Ett N.
OUWE N D W
_ PARAMETER SYSTEN REACTOR VENT ZONE
-.... SPEC.
q
.... tmL.
sFEC,.,,_,,,,qtm..
m IT M OPERATING FLANT ID NO T41-A0V F040A,B See Note TIMg 180 Days NONE 4
See Note 3
IX W OMENT: LIMIT SWITCH t
TEMP.
(260 Max) 1 s e.
i goy)
See HELB NONE See Note 1 NONE NONE See Note Prnfile MNIFACTURERt NAMCO 3
g PRESSimE 16.5 Mex.
NONE See Note 1
i (PSIA)
See Note 1 NONE NONE 3
l PEIDEL Nt9EBERt D2400-XR RETATIVE 100 nunrnm(TJ NONE See Note NONE ij0NE 3
FtBICT1DNt POSITION INDICATION CREMICAL t
None SPRAY NONE E888 See Note NONE NONE 3
s ACCURACT SPECt N/A
)
RADIAT1DN DEMnN N/A 5.1x10 NONE See to 2 NONE NOME (Rede)
SERVICEt N* IbbAE 3
E ACING
- [
1hCAT3DN! Reec. Bldg. E1. 164'-0" 40yeege NONE 3
et 100 F NONE NONE E
F140D 12TET. EuY: See Note 1 SUBletR-(
iN ABOTE FLOOD M VEInt yone pone CENCE See Note 1 None Nome Name i
i
_eDocementetaan References!
l 1.
FSAR Appendix N, Pere. N.5.'1.1 as Table 12 Notest_
2.
HNP-2 Mech. Cale. No 296, Rev. O No HEIA le postulated le this esaperement. The 1.
3.
Spec. 55-6915-2, Pere. 4.1.2 press / temp quoted are the consequences of a brealt
{
in the pipe chase.
No flooding to postulated.,__,
I* Wie to the sus of the 40 year dose med the 18 14C4 dose. S ie value equates to the generet floor ares total 1stegrated does for ENF.2 d ieh te esa=
eervative for ENf-1 due to the sta11erity la design.
l
- 3. There is presently not enough information available to prove complete acceptability of l
this equipment.
i I
- 4. This time is An engineering judgement which bounds the maximum time frame e or which the t
componentisrequiredtoope{ae'. -
l i
sewsn I. Match Noeleer Plant - thiit 1 System Componenk kvelmation Work Sheel:
- Sheet,lk,of 3-REY. 0 8
89 N " C" " "
TM @
QMg h wme - - -
ABRe PARAmTE~~ ' "RSPEC.
QtAL.
srEC._,,,,qtN..
m uos tr e
~"
~'
~
SYSTEMt REACIOR VENT ZONE OPERATINC 180 Days NONE See Note
~~
~~'
See Note FUurr ID NO.T41-A0V F040A,B TIME 4
t COMPOWTI SOLENOID VALVE TEMP.
(260 Max) goy)
See HELB NONE See Note g NONE NONE 3
Prnfile MNWACTWtER: ASCO FRESSIRE 16.5 Max.
NONE See Note 1
,4 (FSIA)
See Note 1 NONE NONE 3
l 3COEL NtBSERt HT 8321A6 REIATIVE 100 MtMIDIIT(T.)
NONE.
.NONE 3
ee ote FtMCT1DN! SYSTEM ISOIATION CREMICAL None SPRAT NONE Mone See Note NONE NONE 3
i ACCURActs SPEC N/A ItADIATEDN DEMDNt N/A 5.1X10 NONE See te 2 OUT TO SBGT SYSTEM (Rede)
SERYTCEt IS01ATION VALVE ACING LOCAT1DNt Rese. Eldg. Et, 164'-0" 40 yeage NONE 3
See Note at 100 F NONE NONE 3
1 FLOOD LEVEL EI2Y: See Note 1 5tmER=
ABOVE FLOOD IZYELt yone None CENCE See Note 1 None Nees 9888
- Documentation Reforences Notest 1.
FSAR Appendix N, Pers. N.5.'t.I & Table 12 1.
2 HNP-2 Mech. Calc. No 296, Rev. O No RELs is postuteted in this cooperament. We Press / tamp quoted are the consequences of a break 3
Spec. 55-6915-2, Pere. 4.1.2 in the pipe chase. No flooding to poeteleted.
2.
nie la the sue of the 40 year dose and the ISO day LOCA dose. Sie value equates to the generet fleer area total 1stegrated dose for ENF-2, which is ese-servative for ENf-1 due to the stallarity la destge.
3.
There is presently not enough information available to prove complete acceptability of this equipment 4.
This time is an engineering judgement which
(
bounds the maximum time frame,for which the component is required to <perate(.
- s. "= 6 g
\\
(514'es. 3E Elcetrieel Eq:ipment Required to Feetion thder Postulated Ac 1 dent Condit l
REY 4 331-Reactor Recirculation System (Isolation di RPT Only)
SYSTEM:
(CE)
'e IDC&TIDN PIANT IDENTIFICATION NUMBER GENERE NAME INSDE DRYWELL OUTSDE DRYWELL B31-MOV F031A.B Valve Motor Ooerator X
Delete Sheet 3 OI Delete Sheet 4 B31-PS N018A,B Pressure Switch OI ' h 4 X
l i
f
?
NOV 2 4 gggg
mene A. esteh Weelear Flaat a thit 1 System Cospoesnt Evatustine Errk Sheet sheet,,2,,of _
REY. 0 ENVIRONENT DOCUMENTATEDN REF*
900..
Offs'ENNDEIG EQtFIPMNT DESCRIFT1DN FARAMETER SPEC.
QlRL.
SPEC.
QUAL.
IETWOD 111MS STS1TMs REACIOR RECIRC. SYSTEM OPERATING SEE NOTE FIANT 2D W. B31-PS N018A,B (GE) ygMg NONE NONE NONE 2
URWOMENT PRESSURE SWITCH TEMP.
(214 Max)
SEE NOTE (Oy)
See RELB NONE I
menn 1.
SENtFACTURERI BARKSDALE FRESSURE SEE NOIE (PSIA) 16.'7 Men.
NONE I
NUNE NONE 2
IWDEL NtBSER: B2T-M12SS REIATIVE SEE NOTE NUMIDIIY(T.] 100 NONE None NONE NONE 2
FINICT1DNt EMERG. CORE COOLING CNEMICAL SEE NOTE
-c S
NORMAL AMB. COND.
SPRAY None NONE None NONE NONE 2
2 ACCtNtACTI SPECt
+
7.
RADIAT1DN 0
SEE NOTE 5.1 x10 NONE See Note 1 NONE NOE 2
c DEPWN! -
(Rads) c'l (See Note 3)
SERTIGtRecire. Suction Pressure ACING 40 years SEE NOTE et 100'r NONE 3
IscATEDN! Reec. Bldg. E1. 130'-0" FLOOD IZTEL EIEV3 y,,,
SUBMER.
ABOVE FLOOD LEVELt CENCE None None 4
Nome Nees Nome h_
- tation_Referencest Notest 1.
FSAR Appendix N. Pers. N.5'.3.1 & Fig. 2 1.
This is the sum of the 40 year does and the 180 day 2.
HNP-2 Mech. Calc. No. 296, Rev. 0 LOCA dose. This value equates to the general 3.
Spec. 55-6915-2. Pers. 4.1.2 floor area total integrated dose for UNP-2,which is
(
4.
FSAR Appendix N. Pers. N.5.6.1 conservative for HNP-1 due to the similarity in design.
2.
There is presently not enough information l
available to prove complete acceptability of~
this equipment.
3.
B31-N018A is located on panel H21-P006 &
B31-N018B is located on panel H21-PO22
-. i,
i SOIENOID VALVES WHICH CONTROL THE OPERATION OF VALVES 2E11-F041A-*D (2E11-7213 Through 2E11-F220) t The valves provide isolation capabilities for instrinnents 2E11-N010A-*D and 2E11-N011A-9. These instrtanents monitor drywell pressure and provide an ADS permissive signal on high drywell pressure.
The valves could be subjected to a harsh environment due to radiation in the event of a LOCA. The switches which the valves service will sense a high drywell pressure and actuate very early in a LOCA event prior to any high radiation being present and will not have to function again.
The safety function of the switches will be satisfied and the potential failure of the isolation valves will have no adverse impact on plant safety.
If one or more of the 2E11-F041A-+D valves are closed for any reason only a failure of the solenoid could cause the isolation valve to open but the chances of the valves being closed concurrent with a LOCA are remote. The instruments in question must be operable or the plant is in a LCO condition.
i These valves could be subjected to a harsh environment due to temperature af ter a HELB but are not required to assure plant safety after that event.
Based on the above, continued operation is justified.
m 22 t
ej e
r i,
)
2P33-F016 and 2P33-F017 These valves provide the capability to select any available sample location for either of the H2-02 analyzers. The normal and accident condition of the valves is de-energized. With no operation of the switching valves each analyzer has the capability to sample the drywell and the torus for H2 and 0. If the switching valve were 2
to inadvertently energize there is a potential that a analyzer could be damaged due to low flow but this is very unlikely since without specific operator action the solencid can not be energized.
All controls and associated cables for the valves are fully qualified.
Continued operation is justified based on the fact that H2 and 02 sampling capabilities exist for the torus and the drywell with the loss of switching capability.
.~
23 NOV 2 41982
Ibest 1 Cf 1 A Edwin 1. Estch Euclear Plant - Whit 1 Ilsster List Rev. 5 (Class IE Electrical Equipment Required to Function thder Postulated Accident Conditions)
SYSTEM:
2 Ell - RESDUAL HEAT REMOVAL (RHR) SYSTEM
-i comms 7:.
IDC&TIDN PIANT DENTIFICATION NUMBER GENERIC EAME INSEE DRYWELL DUISEE DKDIELL 2 Ell-MOV F003kB VA',VE MOTOR OPERATOR X
Q 2E11-MOV F004A,B,C,D -
VALVE MOTOR OPERATOR X
0 2 Ell-MOV F006A,B,C,D' VALVE MOTOR OPERATOR X
0 2 Ell-MOV F007A,B VALVE MOTOR OPERATOR X
9 2 Ell-MOV F008 VALVE MOTOR OPERATOR X
01 2 Ell-MOV F0llA,B VALVE MOTOR OPERATOR I
9 2 Ell-MOV F015A,B VALVE MOTOR OPERATOR X
OT 2 Ell-MOV F016A,B VALVE MOTOR OPERATOR X
00 2 Ell-MOV F017A,B VALVE MOTOR OPERATOR X
Q. -
2cil-MOV F021A,B VALVE MMOR OPERATOR X
Q 2 Ell-MOV F023 VALVE MOTOR OPERATOR X
Q 2 Ell-MOV F024A B VALVE MUTOR OPERATOR X
Q 2 Ell-MOV F026A,B VALVE MOTOR OPERATOR X
Q 9
2 Ell-MOV F027A,B VALVE MOTOR OPERATOR X
2 Ell-MOV F028A,B
_ VALVE MUTOR OPERATOR X
OI 2 Ell-MOV F040 VALVE MUTOR OPERATOR X
Q 2 Ell-MOV F047A,B VALVE MOTOR OPERATOR X
- Q 2 Ell-MOV F048A,B VALVE MOTOR OPERATOR X
Q 2 Ell-MOV F049 VALVE MOTOR OPERATOR Q
2 Ell-A,0,v F065A,B,C,D Lim. Sw./ Sol. Vlv.
.X OI 2 Ell-MO_V _F068A,B VALVE MOTOR OPERATOR X
Q 2 Ell-MOV F073A,B VALVE MUTOR OPERATOR X
Q X
Q 2 Ell-SV F074A,B SOLEN 0E VALVE 2 Ell-MOV F075A,B VALVE MOTOR OPERATOR X
Q 2 Ell-MOV F091A,B VALVE MOTOR OPERATOR X
Q 2 Ell-MOV F140A,B VALVE MUTOR OPERATOR X
Q 2 Ell-PS ' N017A.B.C.D PRESSURE SWITCH X
Q 2El'l-MOY F103A,B' VAVLE MOTOR OP5RATOR X
9
- These components are listed on separate SCEW sheets, and are presently Outstanding Items.
2 4 ggy
=*
Edwin 1. Esteh Cuclear Plant - Enit 1 Master List Ansat L cf
/b\\
~
Rev.6 (Class 1E Ilectrical Equipment Baguired to Function Under Postulated Accident Conditions) *ci SYSTEM:
2E11 - RESIDUAL BEAT REMOVAL (RER) SYSTEM
.~'
, = _.
IDCATIDN
_E FIANT DENTIFICATION WilMBER GENERIC MAME INSDE DRY 1 DELL OITISDE DRY 12 ELL..
2E11-MOV F104A,B VALVE MOTOR OPERATOR X
Q VALVE MMOR OPERATOR X
Q 2E11-MOV F009 2E11-SV F079A.B SOIINOID VALVE X
Q 2 E11-SV F080A,5 S01INOD VALVE X
Q 2 Ell-MOV F010 VALVE MMOR OPERATOR X
Q Delete sh. 39 2E11-A0V F051A,B Pilot Solenoid I
OI wil-AfW FOMA R OI Pilot Solenoid X
' 2R24-S011 A.C. MMOR CDNTROL CIF X
C 1
2R24-S012 A.C. MMOR CONTROL CIE X
C I
2 R24-S018A A.C. MOTOR COhTROL CTE X
C 2R24-S018B A.C. MOTOR CONTROL CIE X
C 2R24-S022 D.C. MOTOR C0hTROL CIP X,
_, j,C 2R27-5096 n,c, yoTog STARTER X
_ Q 2R11-S031 Transformer X
C 2R11-S033 Transformer X
C I
2T52,,,,,,
Elect. Penetration X
X C
~ States _T_ype Nr Terminal Block X
X 1
A05 Power Cable X
C C
B12 Power Cable X
X B13 Power Cable X'
C B09 Power cable X
C Power Emhte X
C B11 lC B06 Power Cable X
C30 Power Cable X
C B17 Power Cable X
C B03 Power Cable X
C NOV L q,,,,j
'.Edwin I. Estch Nuclear Plant - adt i Master List M 1 Cf 1 b I
Rev. 5 (Class IE Electrical Equipment Esquired to Function Onder Postuistcd Ac;ident conditions) 2E11 - Residual Heat Removal (RHR) System SYSTEM:,
(X)MPONENTS s
.~_
' ~ ",
IDCATIDN PIANT DENTIFICATION NUMBER CEh'IRIC MAME INSEE DRYWELL OUIS DE DRYWELL C
C17 Control Cable x
C20 Control Cable x
C C18 Control Cable x
Q C19 Control Cable x
x C
C23 Control Cable x
C C40 Control Cable x
x C
H01 Instrumentation Cable x
C C
K01 Instrumentation Cable x
N07 Instrumentation Cable x
C AMP # P75-1724 Uninsul. Term. Conn.
x C
C AMP # P75-1722 Uninsul. Term. Conn.
x C
AMP # 327283 Uninsul. Tem. Conn.
x C
x AMP # 327284 Uninsul. Term. Conn.
C AMP # 325203 Uninsul. Term. Conn.
x AMP # 321598 Uninsul. Term. Conn.
x C
C AMP # 53943-1
' Insulated Term. Conn.
x x
~
lC AMP # P75-0097 Insulated Term. Conn.
x x
C AMP # 53424-1 Insulated Term. Conn.
x C
AMP # 53425-1 Insulated Term. Conn.
x C
x AMPL,53426-
_ Insulated Term. Conn.
Q AMP # P75,-0_09,4_
Insulated Term. Conn.
x x
Q AMP # P75-0096 Insulated Term. Conn.
x x
~
Q AMP # $3983-1 Insulated Term. Conn.
x x
C AMP # 320559 Insulated Wire Splice x
AMP # 320562 Insulated Wire Splice x
x C
AMP # 320570 Insulated Wire Splice x
C PWB Heat Shrink Wire & Cable Sleeve x
C C
PWC Heat Shrink Wire & Cable Sleeve x
PWD Heat Shrink Wire & Cable Sleeve x
O lC PWH Heat Shrink Wire & Cable Sleeve x
x OY 2 4 193g
co'wa.n 1. Match Nuclear Plant - Ikit 1 Master List E ast i Cf @
,4\\
Rev. 4 (Cissa IE Electrical Equipment Baguired to Feetion Ibder Postulated Accident Conditions)
SYSTEM:
2E11 - Residual Beat Removal (RER) System
..;-i C(MPONENTS
's
1DCATION PIANI DENTIFIC&. ION NUMBER GENERIC M&ME T
INSEE DRYWELL OUISIDE DRYWELL C
PWJ Heat Shrink Wire & Cable Sleeve x
FWK Heat Shrink Wire & Cable Sleeve x
C PVC Heat Shrink Wire & Cable Sleeve x
C PVT Heat Shrink Wire & Cable Sleeve x
x Q
PWI Heat Shrink Wire & Cable Sleeve x
C 2E11-NOV F119A,B Valve Motor Operator x
q Buchanan Phenolic Terminal Block x
x C
2E11-A0V F122A,B Limit Sw./ Sol. Valve x
OI.
2E11-A0V F041A,B Limit Switch x
OI 2E11-SV F213 Solenoid Valve x
01l 2E11-SV F214 Solenoid valve x
01 2E11-SV F215 Solenoid Valve x
OI 2E11-SV F216 Solenoid Valve x
01. ;
2E11-SV F217 Solenoid Valve
- x..
OI 2E11-SV F218 Solenoid Valve x
OI-e 2E11-SV F219 Solenoid valve x
~
vil-SV F220 Solenoid Valve lO1 x
e 40V 2 4 M2
o gen I 3steh Nuclast Flaat = Matt d Sy;tes C#ent Evaluatisa Work Sheet annet 51 ef y Rev. 0 BQUDIENT 'MSCRIFFEM ENVIRDIGEDIT B0CtBEMATM REF*
-1 Rut PARApe 11!t SPEC.
4tmL.
SPEC.
QUAL.
IE M S IIES SYSTEM: RHR OPERATDIO FIAlf! ID W. 2E11-A0V F041A,B,C,D 180 Days NONE See Note NONE NONE See Note TIMg 3
2 m g LIMIT SWITm TEMP.
See HELB Profile NONE NONE NONE See Note
(*F)
(160 Max) 1 2
IIANWACTERER3 MICRO-SWITCH PRESSIEE ONE NONE NONE See Note (PSIA) 14.76 Nax 1
2 amont usesR:
pre 6-2RN gggaygyg See Note e
utsuDITY(1) 100 NONE NONg WNE NONE 2
FlWCEENs POSITION INDICATION CHEMICAI.
See Nota EP34Y NONE NONE NOME NONE NONE 2
IS ACCIBACf3 SPEC N/A R&DIATEM 2
(a DEIGIfg N/A 0
See Note (Rads) 5.1110 Note 1 2
~~
SERVECE: SENSING LINE IS0 g fI AC DIG 40 Yrs.
el IAC&TEDIft See Note Rese. Bldg. E1. 130 0" at 900F NONE 3
FIAOD 12 VEL EI2V 3t393E.
ABOVE FIADD IAVEL:
1 NONE GEBICE NONg Nong NONg NONE HOME NOIIE E_ ;- - = tion Refs _ rest M
1.
FSAR Supplement 15A, Para. 15A.1.1.b &,
1.
This is the sum of the 40 year dose and the 180 Table 7 day LOCA dose.
2.
Mech. Calc. No. 296, Rev. 0 2.
There is presently not enough infermation to prove 3.
FSAR Section 9.4.2.2.1 complete acceptebility of this equipment 3.
This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
l
RC 1. Batak meslaar Plant = Matt d Sy: tem ca r ent Evalustian Work Sheet meet 52 of Rev. 0 g
ENVIRONMDff DOCl3EuffATE00f REF*
- QML, nasamensam men FARAMETER SPEC.
Ql1L.
SPEC.
QML.
BETMS 3333 SYST W:
RHR OPERAT331G Fgaarr 3D m, 2E11-SV F213 ggg 180 Days NONE See Note See Noto NONE NONE 2
IXEStBEEf8 SOIENOID VALVE TEMP.
See HELB See NotO
(*F)
({$ N)
NONE 1
NONE ENE 2
MANWACTMER:
ASCO PRESSIEg See Note NONE NONE NONE (PSIA) 14.76 Max 1
2 MNEL NEBSERS HT8320A185V REIATIVE See Note utsuaIIY(1) 100 NONE NONE NONE NONE 2
FlWCTEW8 CONTAINMENT ISOIATION CHEMICAL f
See Note SPEAY NONE NONE NONE NONE NONE 2
y ACCIEaCts 5FEC:
N/A BADIATEDIl DDEMI N/A I
4 MNE NONE NONE See Note g
(Rede) 5.IX10 Note 1 R
SOL. VALVE FOR SENSING 2
RERVICE: LINE ISOL. VALVE 2E11-FOL' 4W1NG l
40 Yrs.
See Note 1AC&T30Ilt Rese. Bldg. E1. 130M 0" at 90*F 3
FIA0012 VEL EI2V gggggg.
8 NONg GEBICE NONE NOME NONE NONE NOME NONE
- Dsc : tatica Referenceer y,,,,,
1.
FSAR Supplement 15A, Para. 15A.1.1.b 6 1.
This is the sum of the 40 year dose and the 180 Table 7 day LOCA dose.
2.
Mech. Calc. No. 296, Rev. 0 3.
FSAR Section 9.4.2.2.1 2.
There is presently not enough information available to prove complete acceptability of this equipment.
3.
This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
Edi^ I. Esteh Mustaar Flaat = Galt d Syntes Carent Evalusties Work Sheet sheet,,_53._,ef j.
Rev. 0 ENVIR000ENT DOCLBENTAT300f REF*
4 M BE PARADETER SPEC.
QlEL.
SPEC.
QtEL.
BETIElO ITEBE SYSTyM RHR OPERATING yIdart ID N0, 2E11-SV F214 180 Daya NONE See Note See Note NONE NONE TIME 3
2 GREGENf8 SOLENOID VALVE TEMP.
S** N N' M8
(*F)
([ h)
NONE 1
NOE ME 2
IIANINACTEREE ASCO pggg3 g See Note (PSIA) 14.76 Max EE 1
ME NOE 2
M10EI. Blamer: HT8320A185V RE MTIVE See Note MIMIDIIY(1) 100 ME NONE EE EE 2
FIRICEMS CONTAINMENT ISOIATION CHEMICAL See Note g
SPEAY NONE NONE NONE NONE NONE 2
ACCES&Cf3 SPECS N/A BADIATIDIl 2
See Note g
BEMDIls N/A a
4 (Rada) 5.1X10 WE Note 1 NONE NONE 2
'Z$
' SOL. VALVE FOR SENSING A
h4gING 40 Yrs.
N E8 LINE ISOL. VALVE 2 Ell-F(
See Note Reae. B!dg. El. 1300" ae 900F NONE 3
NOM NONE 2
FLOOD 12 VEL EI2V8 StBIER.
M N 1 2 V II.
NONE GEalCE NONE NONE NONE NONE NONE NOME
- Doc m station
References:
Notes:
t 1.
FSAR Supplement 15A, Para. 15A.1.1.b &,
1.
2his is the sum of the 40 year dose and the 180 Table 7 day LOCA dose.
2.
Mech. Calc. No. 296, Rev. 0 3.
FSAR Section 9.4.2.2.1 2
The e is presently not enough information available to prove complete acceptability of this equipment.
3.
This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
Eas^ 1. Estch Nuclear Plant = Wait d SyCtes Cse^ent Evaleastica Work Sheet M % of J Rev. 0
{
BQUDIElff 'MSCRIFTERE ENVIBoleENT DOCl3ENFATEDet REP
- dit&L.
OmW l
PARAIETER SPEC.
QtEL.
SPEC.
QtEL.
IETIIDD INM SYSTEM: RHR OPERATIBIG FIAafE ID MD. 2E11-SV F215 180 Days See Note See Note TIMg NONE 3
IXhMBENts SOIENOID VAINE TEMP.
See HELB 8** " **
Profile NONE NONE NONE (oF)
(160 Max) 1 2
IIANINACTIBER: ASCO Fgg33 M See Note (PSIA) 14.76 Max NONE NONE NONE 1
2 INDEI,3135ER3 HT8320A185V REuTIVg See Note MLMIDIIT(1) 100 NONE NONg NONE NONE 2
h FIRICRIWs CONTAINMENT ISOIATION
- CHEMICAI, See Note o
SPEAY NONE NONE NONE NONE NONE 2
ACCIBaCr3 8PECs N/A BADIATION 2
See Note
,o DEaGN8 N/A 4
e ONE 2
ggggggg, SOL. VALVE FOR SENSING g g,LINE ISOL. VALVE 2E11-FO 41&GDIG 40 Yrs.
See Note Rese. Bldg. El. 130M 0" at 90'F NONE 3
FIA00 LEVEL IIAVs ginggg.
A30 W m IA RI.:
NONg CERICE yoyg yONE NONE NONE NOME IIONE
- Doc s tation Referencest jg,g,,,
1.
FSAR Supplement 15A, Para. 15A.1.1.b &.
1.
This is the sum of the 40 year dose and the 18C 1
Table 7 day IDCA dose.
R S ction
.4 2.
2.
There is presently not enough information available to prove complete acceptability of this equipmere g 3.
This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
B C 1. Estah Musleer Flaat = h it d System Caer^eet Evalustian Work Sheet sheet,55 og _
s
(.
~
Rev. 0 ENVauneerT nocumwrATEDet REF*
(ltEL.
-W FARAETER SPEC.
QlEL.
SPEC.
QUAL.
BETIWS 1235 SYSTEN:
RHR OPERATDIG FIANT 3D We 2E11-SV F216 180 Da7s NONE 3
NONE NONE TDE 2
(XhEWEMISSOLENOID VALVE TEMP.
See HELB See Note
(*F)
(NO
)
1 2
i IIMetEActIREE AS00 pagSSIRE S** Note m
e m
2 (PSIA) 14.76 Max 1
MWEL NtBSERB HT 8320A185V REIATIVg See Note MIMIDIIT(1]
FEICTMs CONTAINMENT ISOIATION CHEMICAL See Note SPRAY NONg NONE NONE NONE NONE 2
ACCESACYs EFEC: N/A RADIATEMI 2
he h M8
^
4 OE NONE NOR 2
(Rada) 5.1X10 Note 1 SOL. VALVE FOR SENSING 8
LINE ISOL. VAINE 2 Ell-Ff 48B ING 40 Yrs.
G I
See Note Rese. Bldg. E1. 130d O" at 90*P NOE 3
FLOOD IAVEL IIAVs SINTER =
ABOVE N IAVEI.:
NONE CENCE yong NONE NONE NONE NOME ISOME
- Documentation Rafes-ces2 Notes:
1.
FSAR Supplement 15A, Para.15A.1.1.b &.
1.
This is the sum of the 40 year dose and the 180 Table 7 day LOCA dose.
2.
Mech. Calc. No. 295, Rev. 0 2.
There is presently not enough information available 3.
FSAR Section 9.4.2.2.1 to prove complete acceptability of this equipment.
3.
This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
l
E C 1. Match h h Flaat = unit d Synten CoCent Evalustian teork Sheet sheet 56 of y:
Rev. 9 ENVIROl0ENT DOCtBENTATIDel REF*
(tutL.
0 - 3 19 EquIRENT SESCRIFTElst PARAMETER SPEC.
QtEL.
SPEC.
~
QlEL.
BIERIOD ITBGB 3D M 2E11-SV F217 PERAT M 180 Days NONE NONE NONE 2
(MadE00EllT3 SOLENDID VALVE TEMP.
See HELB See Note
(*F) hIh1*)
g MNE ENE 2
NONE M ACTIMER: ASCO PRESSIME See Note ENE NONE NONE (PSIA) 14.76 Nex 1
2
=
IEMIEL WEREER: HT 8320A185V REMTIVg See Note MiaGDIIY(1) 100 NONE NONE NONE NONE 2
FlaICIEM: CONTAINMENT ISOIATION CHEMICAL 1
See Note SPEAY NONE NONE NONE NONE NONE 2
C) l c)
ACCIEANs SPEC 8 RADIAT3DIl 2
See Note
.r.
Desifs NONE m
m (Rads) 5.1X10 Note 1 2
cz SOL. VALVE FOR SENSING l Ao SERVICES LINE ISOL. VALVE 2E11-F04%ING 40 Yrs.
See Note CAT M s Rese. Bldg. E1. 1300" at 900F NONE 3
WNE WNE 2
FLOGO u YEL E u V SLEDER.
4 0vE rw00 avai.
NONE CENCE NONE NONE NONE NONE NOIE NONE l
- Documentation Referencest Noteer 1.
FSAR Supplement 15A, Para.15A.1.1.b 6, 1.
This is the sum of the 40 year dose and the 18C Table 7 day LOCA dose.
2.
Mech. Calc. No. 296, Rev. 0 2.
There is presently not enough information available 3.
FSAR Section 9.4.2.2.1 to prove complete acceptability of this equipment.
3.
This tire is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
}
(
4
- __)
BC 1. Esteh Iloclear Plant = Unit d System Cent Evalustian Werk Sheet SheeE 57 of me,. 0 ENVInosesNr nocunENrATIoM REF*
ItutL.
omstamass PARAETER SPEC.
Qu&L.
SPEC.
QUAL.
BETMOD IIBS SYS11Mt RHR
.OPERATBIG FIANE 3D W. 2E11-SV F218 180 Days See Note TIMg IONE 3
NOE NONE 2
IXhetBEur SOI2NOID VALVE TEMP.
S**
NONE NONE NONE See Note rof e
(*F)
(160 Nax) 1 2
IIANWACIMERg ASCO pgggggg See Note (PSIA) 14.76 Max MMIEL MIBGER8 Ifr8320A185V REIATIVg See Note MlatIDIIY(1) 100 NONE NOF.,
FERICrMMI CONTAINMENT ISOLATION CHEMICAI.
See Note SPEAY NONE NONE NONg NONE FONE 2
to ACCIE&Cf3 SPECS N/A 3ADIAT3001 2
See Note 315b01f8 N/A a
4 (Rada) 5.1X10 NONE Note 1 NONE NONE 2
h SERVICgg SgVggFggN}{g-FC 6 40G DIG 40 Yrs.
See Note 8 Reac. Bldg. E1. 130d 0" at 90'F NONE 3
FLo0D 12VIG. ELEV 51553 N IEEI'8 NONE GENCE NOW NONE NONE NONE NOME NONE
- Doccx tation Refer eest y,g,,.
1.
FSAR Supplement 15A, Para. 15A.1.1.b &.
1.
This is the sum of the 40 year dose and the 18C Table 7 day LOCA dose.
2.
Mech. Calc. No. 296, Rev. 0 2.
There is presently not enough information 3.
FSAR Section 9.4.2.2.1 available to prove complete acceptability of this equipment
- 3. This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
E [ I. Match m d==e Fleet = Bait d Syctama cour^ast Evaluaties Work Sheet M 58 ef Rev. 0 ENVIRosses?
DOCIBENTAT300f REF*
QutL.
Nan FARAETER SPEC.
QUAL.
SMC.
QU&I..
ISTHOD IIBS SYSTENE RHR OPERATIBIG See note platrr IB 30. 2E11-SV F219 180 Days See Note TIME NONE 3
GREMENTI SOTENOID VALVE TEMP.
See HELB i
(*F)
(
hx) 3,,
- .,g, I
2 IIANirACTISER8 ASCO PRESSIBLE See Note (PSIA) 14.76 Max ENE 1
.ME WNE 2
M10EL NBSEtt E 832W8W REIAT1vE See Note utMIDIIY(1) 100 ENE NONg ENE WE 2
FWICTIN3 CONTAINMENT ISOIATION CHEMICAI.
l see Note a-SPEAY NONE NONE NCNE NONE NOME 2
e ACCIBAG3 SPECS N/A RADIAT3DIf l 2
,j~See Note DIDelf8 N/A 4
^
(Bade) 5.1X10 NOKE Note 1 NONE WNE 2
C gg=,g,, SOL. VALVE FOR SENSING L' 2
a w
ISOL VAEvE 2E n-F0 0 Aa =
40 Tr..
see m e Rene. Bldg. E1. 1300" at 900F None 3
NOKE.
NONE 2
FLOOD 12 VEL EI2V:
~
SUBER.
k 3
NONE CENCE NONE NOME McWE J
NONE
" NONE, i DONE
- Du.:umentation Referencest 1.
FSAR Supplement 15A, Para.15A.1.1.b &,
1.
This is the'atan of the 40 year dose and the 18C
~
Table 7 de_y LOCA dose. '
2 Mech. Calc. Nc. 296. Rev. 0 c
~
2.
There is presently not enouFh lInfornu:2. ion'eemilabic/ o 3.
FSAR Section 9.4.2.2.1 t
prove complete acceptability of this equipment.
3.
This,tirae is an engineering judgement which bourdd the maximte time frame for which the congonent is required i
to optfrate.
t
EC I. Esteh Neslaar Plant - Bal:: d Sys%s Com^ent, Evslied:tes Warh $hm S' met 53 af e
~
L Rev. 0 ENVIRosesser ime?M MF*
Quth.
0 W EEM S UIS
~
PAlwemr.R SPEC.
QtEL.
SPEC.
QuiL.
IEWS
_ RBIE j
SYSTEN RHR OPERATBIG See Note See Note' FIAart 3D MB. 2E11-SV F220 TDE 180 Days NONE 3
~NONE i'
NOR 2
GREWENTS S01ENOID VALVE TEMP.
See HELB See Note
(*F) h h)
NONE 1
MANWACIMEE8 ASCO PRESSIRE See Note (rsIA) 14.76 Max NOE 1
none NOE 2
kDEEL NESSEE8 Irr 8320A185V REIATIVE See Note NtatIDIIT(1) 100 NOE NONE NOE NONE 2
FBICf3M8 CONTAINMENT ISOLATION CHEMIC&Is See Note SPEAY NONE NONE NONE NONE Nott 2
N8 SPEC N/A RADIAT]DIf 2
to 9E18118 N/A 4
See Note
.c.
(Rads) 5.1X10 NONE Note 1 NONE NONE 2
b
' 39ht,'Y N h F g gjE g g L 4GDIG 40 Yrs.
See Note
- 8 Reac. Bldg. E1. 1300" at 90*F NOE 3
{
FIAOD IRVEL EI2V SURNta=
' "v5 '88 " 3* VEL:
NONE cE=Cs N0m N0n N0u NON:
N0m Non
- Documentation Refer-cest y,g,;
1.
FSAR Supplement 15A, Para. 15A.1.1.b &.
1.
'Ihis is the sum of the 40 year dose and the 18C Table 7 day LOCA doce.
2.
Mech. Calc. No. 296, Rev. 0 3.
FSAR Section 9.4.2.2.1 2
There is presently not enough information available to prove complete acceptability of this equipment.
3.
This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
---6 e
Edwi'a I, EstQ Nuclear Flaat - M it 1 Idaster List meet d Cf M g m.v. 3' l
(Class IE Electrical Equipment Esguired to Faction hder Postulated Accident Conditions) l 3YSTEM:
2P33 - Frimary Containment Atmosehere H and 0; Analvrer System
.y.-
~
M m CATroN
[
FIANT IDENIIFICATION NtlMBER GENERIC NAME 2P33-A0V F002 Lim. Sw./ Sol, Viv.
X OI Lim. Sw./ Sol. Viv.
X OI 2P33-A0V F003 Lim..Sv./_ Sol, Viv.
X OI 2P33-A0V F004 2P33-A0V F005 Lim. Sw./ Sol. Viv.
X OI.
2P33-A0V F006 Lim. Sw./ Sol. Viv.
X OI 2P33-A0V F007 Lim. Sw./ Sol. Viv.
X OI 2P33-A0V F010 Lim. Sw./ Sol, Viv.
X O_I 2P33-A0V F011 Lim. Sw./ Sol, Viv.
X OI 2P33-A0V F012 Lie. Sw./ Sol. Viv.
X OI 2P33-A0V F013 tim. Sw./ Sol, Viv.
X OI 2P33-A0V F014 Lim. Sv./ Sol. Viv.
X OI 2P33-A0V F015 Lin. Sw./ Sol. Viv.
X OI C17 Control Cable X
C C
C40 control cable x..
i States Type bI Terminal Block X
C AMP # P75-0094 l
Insul. Term. Conn.
X, C
AMP # P75-0096 Insul Term. Conn.
X C
AMP # 53983-1 Insul Term. Conn.
X C
AMP # 320562 Insulated Wire Splice X
C PVI Heat Shrink Wire & Cable Sleeve x
C TM1-X 2P33-P001_A_,B (TMI)
H2 & 02 Analyzer
-01 2R24-S011 AC Motor Control Center X
C 2R24-S012 AC Motor Control Center X
lC C18 Control Cable X
C C19 Control Cable X
C X
C C20 Control Cable Control Cable X
C C21 C29 Power Cable X
C C30 Power Cable X
C C32 Power Cable X
C Q
.Edwin I, Batch Nuclear Plant - Ikit 1 Master List Sheet 1 cf d Rev. 3 (Class IE Electrical Equipment Required to Function thder Postulated Accident Conditions)
SYSTEM:
2P33 - Primary Containment Atmosphere H9 and 02 Analyzer System COMPONENTS IOCATION FIANT IDENTIFICATION NUMBER GENERIC NAME INSIDE DRYWELL OUISIDE DRYWELL H01 Instrument cable X
C Buchanan Phenolic Terminal Block X
C AMP # P75-0097 Insul. Term. Conn.
X C
AMP # 321598 Uninsul. Term. Conn.
X C
2P33-A0V F316 Lim. Sw.Isol. Viv.
X
[0 2P33-A0V F107 Lim. Sw. Isol. Viv.
X
[0 l
1
35r^ 1. Emank Busteer Fleet = Matt d System Cent EvalemeSea West meet meet 15 ag
.h me,. 0 ENVIB000E3fr 30CtBWFIATMIII REF#_
g EqWIRENE M PanAMETEa-srEC.
OmL.
sac.
EDIN Immet Irme SYSTD18 PRIM. CONT. H &O 2 2 ANALYZEF gyERATDIG 180 Daya NONE See Note NONE NONE 8**
FIAFE B We 2P33 AOV F016 TDS 3
2
====== tIxIr SWIr a
=Nr.
S;;,"s=
e mNE NO.
NO.
se = =-
(Y)
(210 Mex) 1 2
EEWACEEES MICROSWITCH
' pgESStRE NONE NONE NONE See Note (PSIA) 15.06 Nam 1
2 M El'EE't OPD-AR RE1ATIVE See Note i
HisGDIIT(1) 100 NONE Nom NONE NONE 2
363 POSITION INDICATION OENM*AI.
See Note SPEAY NONE NONE NONE NONE NONE 2
=0 AdMEmad!Tg SPEC 3 N/A BADIATEM 2
See Note Mgggs N/A
%)
1.2 xli)6 NONE
%g NONE NONE 2
I Gs SERTIt33 CHANNEL SELECTION VALVE ACDW 40 Tre See Note O
IOCATMills Rome. 314. E1.158'O
at90h
.NE 3
3 0
FIAOD 12VEI. ELETs gapet.
Amon FI40s IsvuLg NOW cascE NonE NOME NONE Nom Ness 3D15
- Bomumentatism Referenceal g
1.
FSAR supplement 15A, Pars. 154.5.5.1.b 4 1.
nie to the sum of the 40 year dose and the 180 Table 4 day LOCA dose.
2.
Nechanical Cele. 296, Rev. 0 2.
Ihere is presently not enough inforination available 3.
FSAR Section 9.4.2.2.1 to prove complete acceptability of this equipment.
3.
This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
t 35y^ I. Beesh Westeer Flamt = matt J System Cent Evolustion West Sheet Smag 15A gg _ J' mee. o EWIB00eENT Boctnest&TEIN REFe 4M8 '
maus W h4 rammetrum-sesc.
quu srEc.
quar ammes arses SYSTENg PRIM. CONI.
ANAL E 2
OPERAT gg See Note See Note l
pgayr 3 g 2P33-A07 016 180 Days NONE 3
TM 1
N SOLENOID VALVE TEMP.
See HEul See Note
('F) h$
E x) g M
WNE 2
i MEW MEM Ms ASCO PRESSaB NOE NDE 2
See Note (PSIA) 15.06 Max 1
MM HV 200-924-2 gE3ATIvg See Note EE Mt3GD22Y(f.]
100 NOME NONE NONE 2
M8 CHANNEL SEIECTION CNEMICM.
See Note g
staar Nous NONE WONg NONE NONE
.2 i
g mg gyggg N/A BADIATWE 2
See Note 33E15s N/A 1.2 x166 ENE (gege),
Note 1 WE NONE 2
l 10 SERTIts: CHANNEL SELECTION VALVE AC DIS 40 Tre See Nota l
IackTElfs Re:ac.. Bids. E1.158'O' at90*h l
3 NONE NONE 2
(
PLOOD ISVEE. EIRT:
gapet.
j AaWE 75400 IBM.:
NOR CmICE nong Nong NONg Nog pom pong eBoetsentat 5 Referencest IIstee!
i 1.
FSAR Supplement 134, Pars. 15A.5.3.1.b'&
1.
This is the sum of the 40 year dose and the 180 l
Table 4 day LOCA dose.
2 Mechenical Calc. 296. Rev. O 3.
FSAR Section 9.4.2.2.1 2.
There is presently not enough information available to prove complete acceptability of this equipment.
i 3.
This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
_______._._,.__-___._-,_.-_---.;,..,.,_.-_..,.--_--_--____.--...m.._._
____...,,,-m,.__,_,
me,. 0 ENVIBoletst?
DoctSelft1TEGIE REF*
4ML, '
main rammeTEa.
srEc.
quu stsc.
quu soumos mus SYSTEN8 PRIM. CONT. H &O ANALYZM C OPERATDIS 2
PEAVE B We 2P33-A0V F01h 180 Days NONE NONE NONE he Me TDE 3
2 m LIMIT SWIT NES
(*F)
(210 Max)
I 2
33333g33333 MICROSWITCH PRESS M NONE NONE NONE See Note (PSIA) 15.06 Max 1
MM OPD-A R BEIAT11g See Note InsupIIT(1) 100 ENE ENE NONE NOME 2
M 8 POSITION INDICATION CFEMICAL See Note SPEAY WONE IK)NE MONE NONE NONE 2
W8 SPECS N/A RADIATEIII 2
See Note e
3E1EIE8 N/A s
(Rede) 1.2 x160 NONE Note 1 NONE NONE 2
.e.
c; SERVICE: CHANNEL SELECTION VALVE ACDE 40 Tre.
See Note Rl IDCATEDII: Rose. B14. E1.153'0" 3
et 90*F ENE 3
EE WNE 2
FIman tavat, atavs sunntaa Asovs 7 400 EavuLe NOME cumCE NOIE NOME NOME HOME
" DORE WOME i
- Beassmatath BefsEnacoal gegen 1.
FSAR Suppleaset 154, Pere. 154.5.3.1.b'&
1.
This is the sum of the 40 year dose and the 180 Table 4 day LOCA dose.
2.
Nechanical Calc. 296, Rev. 0 2.
There is presently not enough infornation available to 3.
FSAR section 9.4.2.2.1 prove complete acceptability of this equipment.
3.
This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
i
35y ^ E. Esteh Bealeer Flaat = Unit d System C ent Evelemataa Week A met M 'f e J
Rev. O ENVD000eff Doctpert1TENE REF#
4M8.
i, N ame' EqWWIEME h FARMetTER-SPEC.
QtEL.
SPEC.
QWAL.
IMESS IE9S SYSTENsPRIM. CONT. H 602 ANALYZER OPEEATBIG PEA 52 B W o 2P33-A0h F017 180 Days NONE See Note NONE NONE 2
T3pg 3
N SOLENOID VALVE TEMP.
See HELB See Note
(*F) hgf3 ME x) g WE M
2 N
ASCO See Note PRES $tBE ENE (PSIA) 15.06 Max g
EE ME 2
333, m HV 200 -924-2 m Tryg See Note InsuDErY(1) 100 NE NONE ENE NOH 2
M g CHANNEL SELECIION OREME:M.
See Note None SPEAY NONE NONE NONE N0fE 2
s W4 SPECS N/A BADIATEIN 2
See Note 3EnglggN/A (3 4.)
1.2 x160 ME ra Note 1 WNE NOR 2
SEETIII: CHANNEL SELECTION VALVE AGIIW 40 Tre.
See Note j
IAC&TERIls Rose 3143. E1.158'0
et 90 F ENE 3
FIAOD IaVEL IIRTs 333g3 ABOVE FIA00 lavEL:
NOM GENCE NOME N0nt Nous Isole
- 30gs NONE
- Bseismaatatism Refersecean g
1.
FSAR supplement 15A, Fars. 154.5.3.1.b'&
1.
This is the sua of the 40 year dose and the 180 Table 4 day LOCA dose.
2.
Nechanical Cale. 296, Rev. 0 3.
FSAR Sectice 9.4.2.2.1 2.
'Ihere is presently not enought information available to prove complete acceptability of this equipment.
3.
This time is an engineering judgement which bounds the maximum time frame for which the component is required to operate.
" m l'" T ""7
1 Edwta 1. Mateh Nuclear Flaat - Snit 1 Idsster List meet 2 of _
REV O (Class 2 Electrical Equipeast Reguired to Factime Onder Postuisted Accident Conditions)
SYSTEN:
B31--Reactor Recirculation System (C. _E.)
M MPONENTS 1ACATEDN FIMT IDENTIFICATIDN NtBSER GDEAIC MAME BSIDE DKWILL Otfr5IDE DRYMELL B31-PS N018A,B Pressure Switch X
OI i
i I
w t
}
hiu I. Metals Ihsalmar Plant = halt 4 System Car ^ set Essbestian Most Sheet m ost _ ef Rev. 0 ENvInosewhr accesNInimN REr*
- qluth, em PARADE 17.R SPEC.
QtEL.
SPEC.
QEL.
IEEEDS IIBIB SYSTEst REACIOR RECIRC. SYSTEM
'OPERATBIG See Note NONE NONE HWE FIAgry 33 M I.
B31-PS N018A,B TIBE 2
\\
N PRESSURE SWITCH TEMy*
See HELB See Note Profile NONE NONE NONE (N
(160 Max) 1 2
IBMMCIMER8 BARKSDALE PRESSIEg See Note (rcIA) 14.76 Nam NONE 1
NONE NOIE 2
M MBSEE4 B2T-M12SS gggArgyg See Note MtMIDI1T(1) 100 NONE nong NONE Nots 2
FINCrBull EMERG. CORE COOLING CHEMICAL See IEote
,g NORMAL AMB. COND.
SFRAY NONg NONE NONg N0lm NOIE 2
j AE M Gs 5FECs f 17.
3 BADIATElu 2
See IEote 8
4 l
i;;
(Rede) 5.1X10 NONE Note 1 NONE NUlm 2
co EERVICE8 RE ION Aggg 40 Yrs IDCATMil8,PgRC SU
@0" at 9007 NmW 3
NmW NONE b M*
8S eac.
dg.
2 FIAud 12 VEL ELETs stages =
N NONg CEblCE gong gong yIONE IIONE 1101 5 NOIE
- Boeumentatiga Referencess g
1.
FSAR Supplement 15A, Para. 15A.1.1.b ar.
1.
This to the sism of the 40 year does and the 18C Table 7 day LOCA dese.
2.
Mech. Cale. No. 296, Rev. 0 2.
There is presently not enought information available f
3.
YSAR Sectica 9.4.2.2.1 to provide complete acceptability of this equipment.
3.
B31-N018A is located on panel H21-P006 & '531-N0185 j
is located on panel H21-P002 i
Edwin 1, Batab suclear Plant - kit 1 Master List meet Acf l g Rov._3 1.
(Class E Electriaal Eguipesat Esquired to Festian Dnder Postulated Ac.cident Conditions) gT5 TEM:
2B31- - Reactor Ree{rculation System (G.E. )
1
.-i
~.
\\
1
.-n EXMPONDrFS I
1DCATIDE ym! IDENTIFICATIDE 590LE1 NEM ggggt pgyvgu, ours DI D E LL 2B31 - MOV F031 A. B Valve Motor Oeerator x
Delete Sheet 3 01 2B31-PS N018A,B Pressure Switch x
OI O
e t
?
9 e
8 O
e
=
9 e
Nov 2 41992
j Ehin 1. MaEch Nuclear Plant
- Bait d Syntes Caer ^ set Evaluaties Work Sheet sheet 1 of Rev. 0
', L.
ENVIRotemer DOCtHuffATIDH REF*
(llEL.
m an FARAETER SPEC.
QtEL.
SPEC.
QtEL.
BETIIDS IIWW i
SYSTElt: REACIOR RECIRC. SYSTEM OPERATIBIG NONE NONE See Note FEAltg 33 W 2B31-PS N018A,B NONE TIIs 2
(EbSEMB3ffs PRESSURE SWITCH m*
rof e NONE NONE NONE
(*F)
(160 Max)
I IIMRFACTIMERI BARKSDALE pggggg See Note (PSIA) 14.76 Max NONE 1
BEREL MIBEER8 B2T-M12SS REM TIVg See Note NgMIDI2Y(1) 100 NONE pogg NONE NONE 2
g FIBectIM EMERG. CORE COOLING CHEMICAL See Note NORMAL AMB. COND.
3F3AY NONg NONE NONE NONE NONE 2
to ACCIBACf3 SPECS +
7.
RADIATED 18 2
See Note g
DEMDtis 4
ENE Note 1 ENE ENE 2
(Rads) 5.1X10 ru SERVICE: RECIRC, SUCTION ACING 40 Yrs (S{Ng;()0" 10CATIDHg P SS 3
NONE NONE See Note at 900F ENE p
F1000 MVEL ELEV3 staggg.
U"3 NONE CERICE NONE NONE NONE NONE NOME NOME
- Doceentation References Notes.
1.
FSAR Supplement 15A, Para. 15A.1.1.b 6, 1.
This is the sum of the 40 year dose and the 18C Table 7 day LOCA dose.
2.
Mech. Calc. No. 296, Rev. 0 2.
There is presently not enought information available 3.
FSAR Section 9.4.2.2.1 to provide complete acceptability of this equipment.
3.
2B31-N018A is located on panel 2H21-P006 & 2B31-N018B is located on panel 2H21-P002 i
-