ML20054J508
| ML20054J508 | |
| Person / Time | |
|---|---|
| Site: | Farley  |
| Issue date: | 06/23/1982 |
| From: | Clayton F ALABAMA POWER CO. |
| To: | Varga S Office of Nuclear Reactor Regulation |
| References | |
| RTR-NUREG-0588, RTR-NUREG-0737, RTR-NUREG-588, RTR-NUREG-737, TASK-***, TASK-TM IEB-79-01B, IEB-79-1B, NUDOCS 8206290141 | |
| Download: ML20054J508 (61) | |
Text
{{#Wiki_filter:g Malling Address Almema PowIr Comp:ny 600 North 18th str:st
. Post Office Bon 2641 Birmingham, Alabama 35291 Telephone 205 783-6081 F. L. Clayton, Jr.
Semor Vice President Flintridge Building AlabamaPower the southern eletirc system June 23, 1982 Docket No. 50-364 Director, Nuclear Reactor Regulation U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Attention: Mr. S. A. Varga Joseph M. Farley Nuclear Plant - Unit 2 Environmental Quailfication of Safety Related Electrical Equipment Gentlemen: Alabama Power Company provides herewith the additional qualification information for TMI Action Plan equipment in accordance with the commitments of letter dated April 23, 1982. This information completes the response to the NRC letter dated March 26, 1982. This information demonstrates Alabama Power Company's continuing ef forts to assure electrical equipment necessary to j protect the public health and safety is capable of performing its intended function if subject to a harsh environment. If you have any questions, please advise. Yours ver r ly, B206290141 820623 o% a l 'i l DRADDCK05000h N. L. Clayton, J r. Q l FLCJr/ MAL:lsh-D15 l cc: Mr. R. A. Thoma s l Mr. G. F. Trowbridge ! Mr. J. P. O'Reilly Mr. E. A. Reeves i Mr. W. H. Bradford l Office of I&E ! Division of Reactor Operations Inspection Washington, D. C. 20555
i i h 4 1 4 1 l Manual Insertion Instructions E
; Appendix 6 - IEB 79-018 Response For TMI Action Plan Equipment.
l This appendix is intended to be inserted into the Alabama Power Company NUREG-0588 Response. l t r I 3 ; l l l > 1 i i -{ > . t i ) f b f 1 l e. 4
APPENDICES l [
- 1. NUREG-0588 Review Implementation Procedure
- 2. Emergency Operating Procedures Review and Results
- 3. Procedures for Maintaining Equipment Qualification
- 4. Response to NRC Equipment Qualification Safety Evaluation
- 5. Summary of Aging Evaluations
- 6. TMI Action Plan Equipment l
NUREG-0588 Response - Appendix 6 TMI Action Plant Equipment
NUREG-0588 Response - Appendix 6 TM1 Action Plan Equipment a Table of Contents
- 1. Introduction
- 2. Equipment Qualification Status
- 3. Installation Dates, Standard Owners Group Positions and Previously Requested Extensions to Implementation Dates 4 Summary of Outstanding Items O
l
Chapter 1 - Introduction In order to complete the response to NRC letter, dated March 26, 1982, Alabama Power Company committed to provide additional qualification information for TMI Action Plan equipment in letter date April 23, 1982. These commitments are intended to provide the following: 1) Identification of TMI Action Plan equipment requiring envi ronmental qualification.
- 2) System Component Evaluation Work Sheets for equipment identified in Item 1.
- 3) Correlation of equipment items with specific parts of NUREG-0737.
- 4) Installation dates of TMI Action Plan equipment identified in Item 1.
- 5) Identification of qualification documents used as evidence of qualification.
- 6) Standard Owner's Group positions and previously requested extensions to implementation dates regarding NUREG-0737.
To satisfy these commitments, Alabama Power Com9any has performed a review correlating the specific Farley Nuclear Plant areas of a possible harsh environment with the locations of equipment needed to satisfy the requirements of NUREG-0737,
" Clarification of TMI Action Plan Requirements." The results of this review indicate the following parts of NUREG-0737 address equipment requiring environmental qualification:
II.B.1 - Reactor Coolant System Vents II.D.1 - Pressurizer Relief and Safety Valves II.D.3 - Valve Position Indication II.E.1.2 - Auxiliary Feedwater System Indication and Flow c II.E.4.1 - Dedicated Hydrogen Penetrations I II.E.4.2 - Containment Isolation Dependability II.F.1.3 - Containment High-Range Radiation Monitor II.F.1.5 - Containment Water Level II.F.2 - Instrumentation for Detection of Inadequate Core Cooling II.K.3.1 - Automatic PORV Isolation System II.K.3.5 - Automatic Trip of Reactor Coolant Pumps Appendix 6 Chapter 1-1
Only the above parts of NUREG-0737 address equipment req ui ri ng environmental qualification. All other parts of NUREG-0737 address equipment that: (1) is not located in a harsh environment; (2) is not electrical equipment; (3) is not applicable to Farley Nuclear Plant as discussed in Alabama Power Company letter dated January 14, 1981, "NUREG-0737 Response;" or (4) does not require environ-mental qualification in accordance with associated licensing requirements. l t Chapter 2 of this appendix provides the Master Lists and System Component Evaluation Work Sheets (SCEWS) for all TMI Action Plan equipment requiring environmental qualification. Chapter 2 pro-vides the response to commitments 1, 2, 3 and 5 by: A) Identifying the TMI Action Plan equipment requiring environmental qualification by plant ID number, generic name, manufacturer, and model number via the Master Lists, B) Providing SCEWS to demonstrate the status of qualification for equipment identified in Item A, C) Dividing Chapter 2 into sections each of which addresses and correlates by title an individual part of NUREG-0737, D) Identifying in the Document Reference section of each SCEWS the qualification documents cited as evidence of qualifica-tion. Chapter 3 of this appendix provides the installation dates of the TMI Action Plan equipment requiring environmental qualifica-tion, as well as the standard Westinghouse Owners Group positions and previously requested extensions to implementation dates associated with the aforementioned NUREG-0737 parts. In certain cases, references are made to previous Alabama Power Company letters that discuss these matters. Chapter 3 therefore addresses commitments 4 and 6. The environmental qualification of TMI equipment does not necessarily imply that such equipment is safety related nor that such equipment is essential to achieve a safe shutdown condition. The environmental qualif,1 cation of all equipment that is located in a possible harsh environment and essential to achieve a safe shutdown condition is verified in previous responses to NUREG-0588. Appendix 6, Chapter 1-2
Chapter 2 Equipment Qualification Status Table of Contents I. Discussion II. Master Lists III. System Component Evaluation Work Sheets Section Plant System ID NUREG-0737, Part Section 1. Bil Inadequate Core Cooling, II.F.2 Section 2. B13 Reactor Coolant System (Head Vent), II.B.1 Section 3 B31 Pressurizer Relief and Safety Valves, II.D.1 Section 4. B13/B31 Pressurizer Safety Valve Position Indication, II.D.3 Section 5. D21 High Range Containment Radiation, II.F.1.3 Section 6. E17 Hydrogen Recombiner System, II.E.4.1 Section 7. G21 Containment Water Level, II.F.1.5 Section 8. N23 Auxiliary Feedwater System, II.E.1.2 Section 9. Various Containment Isolation Dependability, II.E.4.2 Section 10. Various PORV Isolation System, II.K.3.1 Section 11. Various Automatic Trip of RCP's, II.K.3.5 Appendix 6, Chapter 2
I. Discussion Alabama Power Company has performed a review of the location of all TMI Action plan equipment and has identified the equipment requiring environmental qualification. The accompanying Master Lists and System Component Evaluation Work Sheets to this chapter identify this equipment and verify its qualified status. Below is a discussion of each of the sections provided in this chapter. Inadequate Core Cooling; NUREG-0727, II.F.2 Instrumentation and equipment associated with inade-quate core cooling is addressed by R.G.1.97. In accordance with letter dated November 16, 1981, Alabama Power Company committed to respond to the Regulatory Guide upon the promulation of the associated draft licensing documents that would affect the design (e.g., NUREG-0801,-0799,-0814,-0835). Following the preparation and implementation of a design for an integrated system to satisfy the various licensing requirements in this regard, Master Lists and SCEWS will be preparad. Reactor Coolant System (Head Vent); NUREG-0737, II.B.1 Four (4) solenoid valves, Target Rock model 79AB001, are undergoing qualification testing and, upon comple-tion of the test and subsequent evaluation, the associ-ated SCEWS will be updated. All other equipment located in a possible harsh environment have adequate documentation to demonstrate their capability to func-tion in the most limiting post-accident environment postulated for Farley Nuclear Plant - Unit 2. Pressurizer Safety and Relief Valve; NUREG-0737, II.D.1 Master lists and SCEWS are provided, herein, to verify the status of qualification of all equipment located in a possible harsh environment. Four (4) solenoid valves, ASCO model HTX8302A22V, lack adequate qualification documentation. The solenoids are scheduled to be t replaced at the ne3t outage of sufficient duration to l complete the planned modification. All other equipment located in a possible harsh environment have adequate documentation to demonstrate their capability to function in the most limiting post-accident environment postulated for Farley Nuclear Plant - Unit 2. I l Appendix 6, Chapter 2, 1-1
Pressurizer Safety Valve Position Indication; NUREG-0737, II.D.3 Master lists and SCEWS are provided, herein, to verify the full qualification of all equipment located in a possible harsh environment. High Range Containment Radiation; NUREG-0737, II.F.1.3 A test report regarding the Victoreen Radiation Detectors was recently completed and evaluated by Alabama Power Company subsequent to their installa-tion. The review of the test report indicates the installation of a water-tight fitting is necessary to protect the cable connection and to establish simi-larity with the test specimen. The design of the water-tight fitting has been initiated and will be implemented at the next outage of sufficient duration to complete the modifications. All other equipment located in a possible harsh environment have adequate documentation to demonstrate their capability to function in the most limiting post-accident environment postulated for Farley Nuclear Plant - Unit 2. Hydrogen Recombiner System: NUREG-0737, II.E.4.1 As stated in Alabama Power Company letter dated January 14, 1981, Farley Nuclear Plant does not utilize external hydrogen recombiners. Dedicated hydrogen penetrations are therefore not applicable to Farley Nuclear Plant. The qualified status of equipment associated with the hydrogen recombiner system located in the containment or Farley Nuclear Plant is verified in a previous NUREG-0588 response, Section C.2.7, dated July 1, 1981. Containment Water Level; NUREG-0737, II.F.1.5 Master Lists and SCEWS are provided, herein, to verify the status of qualification of all equipment located in a possible harsh environment. Two (2) level transmit-ters, GEMS-Delaval model XM54854-323, are undergoing qualification testing and, upon completion of the test and subsequent evaluation, the associated SCEWS will be revised. All other equipment located in a possible harsh environment have documentation to demonstrate their capability to function in the most limiting post-accident environment postulated for Farley Nuclear Plant - Unit 2. Auxiliary Feedwater System; NUREG-0737, II.E.1.2 The status of qualification for equipment associated with the auxiliary feedwater system is verified in a previous NUREG-0588 response, Section C.2.16, dated July 1, 1981. Appendix 6, Chapter 2, I-2
I Containment Isolation Dependability; NUREG-0737, II.E.4.2 The qualified status of equipment associated with containment isolation is verified in previous NUREG-0588 responses, dated July 1 and December 28, 1981, Sections C.2.3, C.2.4, C.2.6, C.2.9, and C.2.11 through C.2.20. Chapter 3 of the December 28, 1981 response identified two (2) solenoids located in the containment that lack adquate qualification documents and are scheduled for replacement during the first refuel!ng outage. The solenoids are utilized to provide isolation of a cooling duct that is wholly enclosed within the containment and does not penetrate the containment boundary. The solenoids are not necessary to provide containment isolation or to satisfy the requirements of NUREG-0737, and are not considered an outstanding item in this regard. Automatic PORV Isolation System; NUREG-0737, II.K.3.1 As stated in Alabama Power Company letter dated May 26, 1981, Alabama Power Company has reviewed the Westinghouse Owners Group report regarding this issue and has determined that an automatic PORV isolation system would not appreciably enhance protection against a PORV LOCA and no modifications are necessary. Consequently, no e,nvironmental qualification documentation is necessary. Automatic Trip of RCP's; NUREG-0737, II.K.3.5 As stated in letter dated January 14, 1981, it is the opinion of Alabama Power Company that resolution of this issue will be achieved without any design modifications. The Westinghouse Owners Group has provided the NRC Staff the results of model analyses regarding this issue. In the event that an automatic system to trip the reactor coolant pumps is required after the NRC determination of model acceptability, environmental quali-fication of associated electrical equipment will be prepared upon system installation, as necessary. The SCEWS provided'for TMI Action Plan equipment reflect the most recent peak containment temperature and pressure postualted to result for a LOCA or HELB. The analyses of the pressure / tempera-ture response were performed in association with Technical Specification 3.6.2.3, Containment Cooling System. The Safety Evaluation Report in Alabama Power Company's letter dated August 17, 1982 provides the basis that environmental qualification of Unit 2 containment equipment is not invalidated as a result of this analysis, and this matter is not an unreviewed safety question. The most recent containment temperature and pressure responses are attached as Figures 1 and 2. SCEWS of containment equipment addressed in previous NUREG-0588 submittals will not be revised. Appendix 6, Chapter 2, 1-3
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Master Lists for TMI Action Plan Equipment Requiring Environmental Qualification l l l
MASTER UST g,,gion 1 Sheet 1_ hoh M. Fartry Nuclear P! ant Unit _2 - KLASS 6E ELECTRICAL EQULPMENT REQUIRED TO FUNCT@N UNDER POSTUL Bil - Inadequate Core Cooling; NUREC-0737. II.F.2
$YSTEM: _
As discussed in Chapter 2 to this appendix, Master Lists and SCEWS will be prepared following the preparation and implementation of a
- design for an integrated system to satisfy the various licensina requirements..
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MASTER LIST 2 Section 2
. Joseph M. Farley Nuclear Plant Unit Sheet _1 of 5 (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)
SYSTEM: Reactor Coolant System (Head Vent) NUREG-0737, II.B.1 COMPON ENTS Pt: ANT ID NUMBER GENERIC NAME MANUFACTURER MODEL BLOG. ELEv. Q2B13SV2213A Solenoid Valve Target 79AB001 CTMT 2115'-0" Q2B13SV2213B Solenoid Valve Target 79AB001 CTMT 7 115'-0" Q2B13SV2214A Solenoid Valve Target 79AB001 CTMT > 115'-0" Q2B13SV2214B Solenoid Valve Target 79AB001 CTMT 7 115'-0" General _q2T52 B014-A __ Control Pene trat f or Electric 100 Series CTMT 7 115'-0" 2VALS145B Control Cable Okonite None CJdT 7 115'-0" 2 VAL 5145C Control Cable Okonite Norte CTMr 7- 115 ' -.0" A21B9Q7 Terminal Block S t_at e s Tvoe ZWM CTMT__J 115'-0" 02A1_3Sv2213A-A])B Terminal Block Sta t e_5 Tvot_gWM CTMT > 115'-0". 2 VAL 5146B Control cable Okonite None CTMT 7 115'-0" 2 VAL 5146C Control Cable Okonite None C_T_MT 7 115'-0"_ __Q2 B13SV2214A /J B _ Terminal Block States Type ZWM CTMT 7 115'-0" General 02TS2B01.6-B Control PenetratJon Electrie 100 Str_ies CTMT 7 115'-0"
.. 2VBL5145B Control Cable Okonite Nome CTMT 2 115'-0"_
_ 2VBL5145C Contral_C_able okonite None CTMr > 113 ' _Q" Zd25 Teminal Block Kraten TypeJW cTwT > 115 ' - 0" __Q2B13SY2213B-B/JB _Tes tna1 Bioek , Keaeea Tvne_ZWM cTMr > 115 ' - O'_' 2VBL5146B Control Cable Okonite None CTMT y 115'-0"
,2VBL5146C Cont.rol Cable Okonite None CTMI >115'-0" Q2513Sv2214B-B/JB Terminal Block States Type ZWM CTMT 7 115'-0" i
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MASTER t.lST hph M. Farfey Nucle:r Plant Unit 2 sa tion 3 sheet _ 3 _of g_ ICLAss IE ELECTRICAL EQUIPMENT REOutRED TO FUNCTION UNDER POSTULATED ACCloENT system B31- Pressurizer Relief and Safety Valves NUP.EG-0737, II.D.1 COMPONENTS PLANT ID NUMBER CENERIC NAPE MANUFACTURER MODEL
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stoc Etre _ N2831SV0444BA Solenoid Valve ASCO _ HTX8320A22V CTMI >115'-0" N2831SV0444BB Solenoid Valve ASCO HTX8320A22V CTMT >115'-0"
,N_2,83,l_SV04445AA _ Solenoid _ Valve _ ASCO '
HTX8320A22V _CTMT >115' " f(1B31Syf445AB- _ Solenoid Valve ASCO HTX8320A22V CTMT _> _115 ' -0 "
?VAtR0200 .Cah19 Oknnita Nnna CTMT >115'-0" 2 vat 50350 m ie Okonite None CTMT >115'-0" N2B31SV0444BA-B/JD Junction Box States Tvoe ZWM CTMT s115'-0" '
N2831SV0445AA-A/_JB Junction Box italei' Company Type ZWM CTMT >115'-0" Q2T528038-B General CTMT. Penetrn. 100 sprins i gig g,4e cTMT >115'-0" i n9T;9pn1 %a CTMT. Penetrn. 100 Series CTMT >115'-0" [ _9-J02 Field routed _ Cable Okonite _None- CTMT >115'-0"
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.] MASTER LIST Section 4 a Joseph M. Farley Nuclear Plant Unit 2 Sheet 1 of 6 (CLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)
SYSTEM: B13/B31 Pressurizer Safety Valve Positipn Indication NUREG-0737. II.D.3
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COMPON E N TS PLAPR ID NUMBER GENERIC N AME MANUFACTURER MODEL BLD . E LEV-2VYKH174A ' Cable Okonite Hone ImT___iltS!-0" Q2B13G001-B Terminal Box States Compa_ny_ App _ZMi Cmr >_115'-0" N8L5099G Cable Ok oni_t e None CNT '7.115 ' -0" 2VBL5099H Cable Okonite Hone CHIT 7115h0"__ 2VBL5099J Cable Dkonite None cmr 7 11s'-0" _ General cmr 7 , Q21528025-B Ctmt. Penet. Electric 100_ Series 115hD" General 7 _Q2T52B02hB C tmt @J1, Electric 100_ Series cmr 115'-0" gsC13:52034 Position switch NAMCO EA-180 CTMT 7 115'-0" Q2B13ZS2035 ILosition swilgh NAMCO EA-180 cmT 7 115'-0" Q2B13ZS2036 Position switch NAMCO EA-180 CMT 7115'-0" i N2B31ZSO444B Limit switch NAliC0 EA-180 cmT 7115'-0" _ e l , IL2B112SO445A Limit switth NAMCO EA-180 cmT >115'-0" States l E2131SV0444BA-B/JB Junction Box Company Type ZWM CMT > 115 '-0" States
'P' ?' "*l044 5AA-A /JB Junction Box Company _
Type ZWM CMT '?115'-0"
'. General
.Q2T528019-A Control Pentrn. Electric 100 Series CMT '? l15 '-0"
' General 92Ti2B038-B Control Pentrn. Electric 100 Series' CMT '7115'-0" H'* T Sfn SD Control Cable Okonite Rone CmT 7115'-0" 2VBL5020D Control Cable Okonite Rone CmT h 15'-0" 0AT352B007A Control Penetra. $"N"ric
, inn o riae rTFT 311R'_na IVXKH174A Cable Okonite None CTMT >115'-0" GPO 1374 Row S,s1
- MASTER LIST Section 5 l 2 Sheet 1_nf _3 __ '
Joseph M. Farley Nuclear Plant Unit (CLASS IE ELECTRICAL EOUl? MENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS D21 - High Range Containment Radiation ; NUREG-0737, II.F.1.3 SYSTEM: COMPON ENTS GENERIC N AME MANUFACTURER MODEL- BLDG. E EV. PLANT 10 NUMBER 2VkIS011E Cable Victoreen Note 1 CMT ~)115'-0" 2VAIS011G Cable Victoreen Note 1 CMT >115'-0" Radiation Detector Victoreen 877-1 Cmr > 115 ' -0" Q2D21RE0027A-A 2VBIS009E Cable Victoreen Note 1 CMT 7115'-0" 2VBIS009G Cable Victoreen Note 1 Cmr 7115'-0" Q2D21RE0027B-B Radiation Detector Victoreen 877-1 CmT 7115'-0" C MT Penet. 100 Series CTMT ,7115'-0" Q2T52B009-A Eh , General 7115'-O C MT Penet. Electric 100 Series Cmr Q2T52B011-B Note 1 - Cables have been qualifi ed along with de tector. I o
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MASTER LIST scetion 6 Jowph M. Farley Nucle r Plant Unit 2 Sheet 1 cf MLAss IE ELECTRICAL EQUIPMENT AEOUIRED TO FUNCTION UNDf,R PO$TUL.ATED ACCIO(NT CONDITICNsl i sysTEu: E17 - %drogen Recombiner System _NURE_G-R73Z,II.E.4.1 __ As discussed in Chapter 2 to this appendix, dedicated hydrogen penetrations are not applicable to Farley Nuclear Plant. The qualified status of electrical equipment aswciated with the hydrogen recombiner system has been verified in a previous 70 REG-0588 response,.Section C.2.7, dated July 1, 1981. , e e e e e O I
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. MASTER LIST Secti::n 7 Joseph M. Farley Nuclear Plant Unit 2 Sheet I ~
(CLAOSIE Et.ECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONSI SYSTEM: G-21 Liquid Waste Disposal (Narrow Range Containment Sump Level); NUREG-0737
, II.t.1.b COMPON ENTS PLAblT ID NUMBER GENERIC MAM E MANUFACTURER MODEL BL DG. ELEV.
Q2C21LT3282A-A - Level Sensor Cems-Delaval XM54854 cmT 80'-0" , l , Q2C21LT3282B-B Level Sensor Cems-Delaval XM54854 CTnr 80'-0" , I' 2VAI5023A Control Cable Okonite None CTMT Various 2VBIS023A C'ontrol Cable Okonite None CTMT Various General Q2T52B007-A Control Penetration Electric 100 Series _CTHr > 11f 0" Ceneral _Q2T52B022-B Control Panetration Electric 100 Series __lDiI_ . 2 113'-0" 9
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l l .' MM GPD 1374 Rev. S/31
MASTER LIST Jowph M. Fwley Nuclear Plant Uent ? Sseun 8 Sheet _1_ cf 4 CLASS IE ELECTRICAL EQUtPMENT AEOutRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDIT
, ,3 7,,. N23 - Auxiliary Feedwater System NUREG-0737. II.E.1.2 As discussed in Chapter 2 to this appendix, the qualified status of electrical equipme associated with the auxiliary feedwater system has been verified in a previous NUUG-0588 response dated July 1, 1981.
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MA$f ER UST Soction 9 Jowph M. Farfey Nucte:r Pfant Unit 2 Sheet 1 ef ICLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUP*CTION UNDER POSTULATED ACCloENT CONDITioNsl system: Various - Containment Isolation Degendabl]ity_ NUREG-0737. JI.E.4.2 l As discussed in Chapter 2 to this appendix, the qualified status of this equipment ise ddressed by a previous NUREG-0588 response dated August 25 and December 28, 1981,
.Sictions C.2.3, C.2.4, C.2.6, C.2,9 and C.2,11 through C.2.20.
P e O O S T i 9 r ,
MASTER List saceton 10 ' l Juoh M. Farley Nuclear Plantunit 2 Sheet,1 sf ) Et. Ass IE ELECTRICAL EQUtPMENT REQUIRED TO FUNCTICN UNDER POSTULATFD ACCloCNT CONDITICNSI Various - Automatic PORY Isolation System; NUREG-0737, II.K.3.1
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As discussed in Chapter 2 to this appendix, Alabama Power Company has determined that
... automatic PORV isolation system could not appreciably enhance protection acainst a P6RV LOCA and no modifications are necessary. -
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, Jowph M. Farley Nuclear Plant Unit 2 Soed en 11 Sheet _ 2 gf
# CLASS 8E ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULAT
;y3;gu. Various - Automatic Trip of RCP's; NUREG-0737. II.K.3.5 As discussed in Chapter 2 to this appendix, it is the opinion of Alabama Power Compan) that the resolution of this issue will be achieved without design modifications.
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I System Component Evaluation Work Sheets For TMI Action Plan l Equipment Requiring Environmental Qualifiction i 0 l l e
- MASTER LIST g3,gg,, 1 Joseph M. Farley Nuefw Plant Unit 2
' Sheet t l
ICLAS$ IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED A Bil - Inadequate Core Cooling: NUREC-0737. II.F.2
$YSTEM.
As discussed in Chapter 2 to this appendix, Master Lists and SCEWS will be prepared following the preparation and implementation of a
- ^ design for an integrated system to satisfy the various licensina requirements.
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l MASTER LIST 2 Section 2
. Joseph M. Farley Nuclear Plant Unit Sheet 1 of 5 (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)
SYSTEM: Reactor Coolant System (Head Vent) NUREG-0737 II.B.1 COMPON EN TS PLANT ID NUMBER GENERIC NAME M ANUFACTUR ER MODEL BLOG. ELEV. Q2 B13SV2213A Solenoid Valve Target 79AB001 CTMT .2115'-0" Q2B13SV2213B Solenoid Valve Target 79AB001 CTMT 7 115'-0" Q2B13SV2214A Solenoid Valve Target 79AB001 CTMT ? 115'-0" Q2B13SV2214B Solenoid Valve Target 79AB001 CTMT 7 115'-0" General Q2T52B014-A Control Penetratior Electric 100 Series CTMT 7 115'-0" 2 VAL 5145B Control Cable Okonite None CTMT 7 115'-0" 2VALS145C Control Cable Okonite None CTMT 7 115'-0" A2T11007 Teminal Block States Tvoe ZWM CTMT > 115'-0" _.02B13SV2213A-A/JB Teminal Block States Tvoe ZWM CTMr > 115'-0" 2 VAL 5146B Control Cable Okonite None CTMT 7 115'-0" 2 VAL 5146C Control Cable Okonite None CTMT 7 115'-0" _ _Q2_B_13SV2214A /J B Teminal Block States Type ZWM CTMT 7 115'-0" General 02T52B016-B Control Penetration Electric 100 Series CTMT 7115'-0" 2VBL5145B Control Cable Okonite None CTMT 7 115'-0" 2 VEL 5145C Control Cable. Okonite None CTMT > 115 ' -O" B2TE025 Terafnal Block Rtaten Type _7W CTvT > 115 ' - O" 02 B11RV2211R-B LT E Ter-inal 41ock staten Tvp, 7W cTMr > 115 '-O" 2VBL5146B Control Cable Okonite None CTMT y 115'-0" 8 2VBL5146C Control Cable Okonite None CTMT >115'-0" i Q2B13SV2214B-B/JB Teminal Block States Type ZWM CTMT 7 115'-0" GPD 1374 Rev. 6/81
SYSTEM COMPONENT EVALUATION WOF:K SHEET - Section 2 2 , Sheet 2 of 5 Joseph M. Farley Nuciear Plant, Unit i ENVIRONMENT DOCUMENTATION REF.* A L, OUTSTANDING SPEC. QUAL SPEC. OUAL MET M ITE M PARAMETER l l SYSTEM: Reactor Coolant System OPE R ATING PLANT 10 NO. TIME 4 COMPONENT: Solenoid Valve TEMP. 316 ( F1 Note 1
- Note 4 1 Note 4 Note 4 MANUFACTURER
- Target Rock PRESSURE 63.1 (PSIA) Note 2 Note 4 2 Note 4 Note 4 MODEL NUMBER: 79AB-001 RELATIVE HUMIDITY (%) 100 Note 4 3 Note 4 Note 4 FUNCTION: Reactor Vessel Head CHEMICAL H3 BO3+
Vent SPRAY NaOH Note 4 3 Note 4 Note 4 ACCURACY: SPEC: N/A 5 x 10 7 DEMON: RADIATION Rads. Note 4 3 Note 4 Note 4 SERVICE: Reactor Vessel Head Vent LOCATION: Containment AGING Note 3 Note 4 Note 3 Note 4 Note 4 _! FLOOD LEVEL ELEV: 115'-0" SUBME R-ABOVE FLOOD LEVEL: yes GENCE None N/A N/A N/A N/A 6 8
' DOCUMENTATION
REFERENCES:
NOTES:
- 1. J. M. Farley,FSAR Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end .of th'Is chapter.
- 2. J. M. Farley FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be. updated in the July 22 1982 FSAR revision.
- 3. J. M. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Figure 1 attached at the end of this chapter.
FSAR Figure 6.2-39 will be updated in the July 22, 1982 FSAR revision.
- 3. Enclosure 4 to IE Bulletin 79-01B.
4 Qualification testing is scheduled to be completed by the fourth quarter of 1982
- 5. This equipment is not essential to achieve a safe shutdown condition for any licensed DBE. and, therefore, no operating time is specified.
SYSTEM COMPO 4ENT EVAltl A TION WOR < SHEET
! Sectio, 2 *
.losoph M. Farfe y Nucle v Plant Unit 2
_ Sheet _ 3 of, 5 ENVil ONMENT DOCUMENTATION I- EF. OUTS"ANDING' OdAL. EQUIPI AENT DE SCRIPTION METHOD 81 EMS ARAMETER :IPEC. QUAL. SPE C. QUAL. SYSTEM: Reactor Coolant System OPERATING Note 4 Note 4 T E Simultaneous None PLANT ID NO. 30 Days 4 Test COMPONENT: Electrical Fenetration TEMP. 316
- Simultaneous None (Low Voltage) I FI Note 1 340 1 4 Test MANUFACTURER: General Electric PRESSURE 63.1 Simultaneous- None INAI Note 2 118 2 4 Test MODEL NUMBER: 100 Series '
RELATIVE Simultaneous None HUMIDITY (%I 100 100 3 4 Tese FUNCTION: Containment Isolation CHEMICAL H3 803+ H3 503+ Simultaneous None SPRAY NaOH NaOH 3 4 Test ACCURACY: SPEC: I 8 N/A RADIATION 5 x 10 1 x 10 DEMON: Rads. None Rads. 3 4 Sequential SERVICE: Electrical Fenetration LOCATION: Containment AGING Note 3 40 yrs. None 4 Sequential None ! ( FLOOD LEVEL ELEV: 115'-0" SUBMER. ABOVE FLOOD LEVEL: yes GENCE None N/A N/A N/A N/A None d l 8
'OOCUMENTATION
REFERENCES:
NOTES:
- 1. J. N. Farley FSAR Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end of this chapter.
l 2. J. N. Farley.FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be updated in the July 22,'1982 FSAR revision.
- 3. J. N. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Figure 1 attached at the end of this chapter.
- 4. Ceneral Electric Co. Report Low FSAR Figure 6.2-39 will be updated in the July 22. 1962 FSAR revision.
Voltage Electrical Containment 3. Enclosure 4 to IE Bulletin 79-01B. Penetration Qualification Test This equipment is not essential to achieve a safe shutdown condition for any Report (Bechtel File E22-98) 4-licensed DBE and, therefore, no operating time is specified. l
SYSTEM COMPONENT EVALUATION WORK SHCET Section 2 . 2 Sheet 4 of, 5 Joseph M. Farley Nuclear Plant Unit _
-~
ENVlHONMENT DGOUMENTATION ItEF. 3)AL. OUTS TANDNOG METHOD ITEMS EmMMMRMM - PARAMETER SPEC. QUAL. SPEC. QUAL. OPERATING Note 4 Note 4 Simultaneous None SYSTEM: Reactor Coolant System TWE 4 Test PLANT ID NO. 30 Days TEMP. Simultaneous None COMPONENT: Cable Power and Controh 316 ( F) Note 1 346 1 4 Test MATNJFACTURER:he Okonite Company Simultaneous None PRESSURE 63.1 (PSIA) Note 2 113 2 4 Test l Sissultaneous None MODELNUMOER: None
' RELATIVE HUMIDITY (%) 100 100 3 4 Test H380 3+ Simultaneous None FUNCTION: Electrical Power and CHEMICAL H3 B03+
Control SPRAY NaOH NaOH 3 4 Teat ACCURACY:
- SPEC: N/A RADIATION 5 x 10 7 2 x 10 8 DEMON: Rada. Rads. 3 4 Sequential None SERVICE: Electrical Safety Systems LOCATION: Containment AGING Note 3 40 yrs. Note 3 4 Sequential None !
n 115'-0" SU8MER- = FLOOO LEVEL ELEV: N/A N/A None a A80VE FLOOO LEVEL: yes GENCE None N/A N/A - 8 NOTES:
' DOCUMENTATION
REFERENCES:
- 1. J. N. Farley FSAR Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end of this chapter.
- 2. J. N. Farley.FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be updated in the July 22. 1982 FSAR revision.
- 3. J. N. Farley FSAR Table 3.11-1 2. LOCA pressure profile f rom Figure 1 attached at the end of this chapter.
FSAR Figure 6.2-39 will be updated in the July 22, 1982 FSAR revision.
- 4. De Okonite Company Engineering Reports.No. 141 dated 2-29-72 & 3. Enclosure 4 to IE Bulletin 79-018.
Okonite Report No. N-1 dated 4. This equipment is not essential to achieve a safe shutdown condition for any July 3, 1978. licensed DBE and, therefore, no operating time is specified. ~ n , . , ,
SYSTEM COMPO MENT EVALUATION WOR K SHEET Section 2 l Sheet 5 of 5 l Joseph M. Farley Nuclea nt Unit 2 ENVIRONMENT DOCUMENTATION HEF.* NAL, OUTSTANDING METHOO ITEMS PARAMETER SPEC. QUAL. SPEC. QUAL. SYSTEM: Reactor Coolant System OPERATING Note 5 Note 5 Simultaneous None TIME 4 PLANT ID NO. COMPONENT: Terminal Block with TEMP
- 316 307 Simultaneous None NEMA 4 Enclosure ( FI Note 1 4 Test Note 4 1 MANUFACTURER: States Company PR ESSUR'E 63.1 Simultaneous None (PSIA) Note 2 80 2 4 Test RELATIVE
~
Simultaneous None MODEL NUMBER: Type ZWM HUMIDITY (%) 100 100 3 4 Test Catalog M-25012 FUNCTION: Coeductor Tet7aination CHEMICAL H3B0 3+ H3 B03+ Simultaneous None ' SPRAY NaOH NaOH 3 4 Test 7 8 RA C: RADIATION 5 x 10 1 x 10 None D MON,N/A Rada. Rads. 3 4 Sequential SERVICE: Electrical Safety Systems LOCATION: Containment AGING Note 3 40 yrs. Note 3 4 Sequential None ! b, FLOOO LEVEL ELEV: 115'-O" SUBMER-GENCE None N/A N/A N/A N/A None 6 A80VE FLOOD LEVEL: yes h l
' DOCUMENTATION
REFERENCES:
NOTES:
- 1. J. M. Farley FSAR Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end of this chapter.
- 2. J. M. Farley FSAR 71gure 6.2-4 FSAR Figure 6.2-40 will be updated in the July 22. 1982 FSAR revision.
- 3. J. M. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Figure 1 attached at the end of this chapter. i
- 4. Wyle Laboratories NEQ Test Report FSAR Figure 6.2-39 will be updated in the July 22 1982 FSAR revision. I 44354-1 dated 3-8-79 3. Enclosure 4 to IE Bulletin 79-018.
- 4. Equipment surface temperature during IDCA does not exceed qualification temperature.
- 5. This equipment is not essential to achieve a safe shutdown condition for any licensed DBE and, therefore, no operating time is specified. 1
MASTER List Joseph M. Farley Nucle r Plant Unit 2 section 3 Sheet _i of 5 fCLASS IE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CO sv$rEn B31- Pressurizer Relief and Safety Valves flVREG-0737, II.D.1 COr@0NENTS PLANT ID NUMBER GENERIC NAME MANUFACn!RER HDDEL
'- LOCATION stoc ELn-N2B31SV0444BA Solenoid Valve .ASCO HTX8320A22V CTMI >115'-0" ti2831SV0444BB Solenoid Valve ASCO HTX8320A22V CTMT >115'-0" N7831SV04445AA Solenoid Valve ASCO HTX8320A22V CTMT >115' "
N1831SV0445AB Solenoid Valve ASCO HTX8320A22V CTMT >115'-0" PVAl60700 Cable nknnito Nnno CTMT >115'-0" 2 val 5035D rahle Okonite None CTMT >115'-0" N2831SV0444BA-B/JO Junction Box {ates Tvoe ZWM CTMT s115'-0" 5t. ales' '- N2B31SV0445AA-A/JB Junction Box Company Type ZWM CTMT >115'-0" General Q2T52B038-B CTMT. Penetrn. Eiget ic 100 spripe CTMT >115'-0" n? TORN 10.A CTMT. Penetrn.
~
ne(a 100 Series CTMT >115'-0" ( 9-J02 Field routed Cable Okonite None - CTMT >115'-0" J 2
?
oro san sinc
SYSTEM COMPONENT EVALUATION WORK SHEET Joseph M. Farley Nuclear Plant Unit 2 Appendix 5 Section 1 Section 3 _ Sheet 2 of 5 l ENVIRONMENT DOCUMENTATION REF. EQUIPMENT DESCRIPTION QUAL. OUTSTANDING PARAMETER SPEC. QUAL. SPEC. QUAL METHOD ITEMS SYSTEM: PZR Relief and System OPERATING ' Valves- TIME Note 5 Note 4 Note 5 Note 4 Note 4 PLANT ID NO. COMPONENT: TEMP' 316 Solenoid Valve (oF) Note 4 Note 4 Note 1 Note'4 2 MANUFACTURER: Automatic Switch PRESSURE 63.1 Note 4 Note 4 Company (PSIA) Note 2 Note 4 1 MODEL NUMBER: H1X8320A22V - RELATIVE ' HUMIDITY (%) 100 Note 4 3 Note 4 Note 4 FUNCTION: Pilot for Air Operated CHEMICAL 11 3 B03+ Valve SPRAY 3 Notr' 4 Note 4 Na0li Note 4 ACCURACY: SPEC:
!^ ^ '^ '
5 x 10 7 ' DEMON: Rads 3 Note 4 Note 4 Note 4 SERVICE: PORV AGING Note 3 Note 3 LOCATION: Containment Note 4 Note 4 Note 4 ! FLOOD LEVEL ELEV: 115' 2 SUDMER. 2 ABOVE FLOOD LEVEL: yes GENCE N/A N/A Note 4 N/A N/A g 1 o
'DOCUMEN TATION REF EHENCES: _ NOTEsi,
- 1. J. M. Far*cy FSAR FIC urc 6.2-6
- 2. J. M. Farley FSAR Figure 6.2-4
- 1. LOCA temperature profile from Figure 2 attached at the end of. this Appendix.
- 3. J. M. Farley FSAR Table 3.11-1 FSAR Figure 6.2-6 will be updated in the July 22, 1982 FSAR revision.
- 2. LOCA pressure profile from Figure 1 attached at the end of this Appendix.
FSAR Figure-6.2-4 will be updated in the July 22, 1982 FSAR revision.
- 3. Aging requirements in accordance with NUREG-0588, Section 4, Category II.
- 4. Qualification for this instrument has not been documented. It will be replaced during the next refueling outaae.
- 5. This equipment is not essential to achieve a safe shutdown condition under any -
licensed DBE and, therefore, no operating tine is specified.
SYSTEM COMPONENT EVALUATION YlORK SHEET Section 3 Joseph M. Farley Nucleer Plant Unit 2 _ Sheet 37f 5 _
....,.6., ,
Ef4VIRONMENT j DOCUMENTATION REF.* 'r OUTSTANDING OUAL METHOD ITEMS EQUIPMENT DESCRIPTION SPEC OUAL SPE C. OUAL PARAMETER l , l CPERATING iote 5 Note 5 None SYSTEM: Pressurizer Relief and
- Safety Valves TIME S h itaneous j PLANT ID NO.
COMPONENT: Terminal Block with T MP. NEMA 4 Enclosure Note 1 Note 4 1 4 Test MANUFACTURER: States Company PRESSURE simultaneous None (PSIA) 63.1 2 4 'u l MODEL NUMBER: Type ZWM RELATIVE Simultaneou s' None Catalog M-25012 HUMIDITY (%) 4 H3B03 + 11 B0 + Simultaneous None FUNCTION: Conductor Termination CHEMICAL 3 3 SPRAY NaCll NaOH 3 4 Test N/A RADIATION Rads Rads - None DE 3 4 9eauential-SE RVICE: Electrical Safety Systems AGING !
~
LOCATION: Containment Note 3 40 yrs. Note 3 4 semiential None 4 FLOOD LEVEL ELEV: 115' SullME R- T ADOVE FLOOD LEVEL: yes GENCE None None None None None None ;
' DOCUMENTATION
REFERENCES:
_ NOTES:_
- 1. J. M. Farley FSAR. Figure 6.2-6 ,
- 2. J. M. Farley FSAR Figure 6.2 ,4 LOCA temperature profile from Figure 2 attached at the e'nd of this chapter.
- 3. J. M. Farley FSAR Tabic 3.11-1 1.
4l Wyle Laboratories NF.Q Test Report FSAR Figure 6.2-40 will be updated in the Julv 22. 1987 FRAR revisfon. 44354-1 dated 3-8-79 LOCA pressure profile from Figure 1 attached at the end of this chapter. 2. FSAR Figure 6.2-39 will be updated in the July 22, 1982 FSAR revision.
- 3. Aging requirements in accordance with NUREG-0588, Section 4. Category II.
4 Equipment surface temperature during LOCA does not exceed qualification tempera-ture. .
- 5. This eouioment is not essential to achieve a safe shutdown condition for any
S / STEM COMPON INT EVALUt TION WORK SHEET , Section 3 Joseph M. Farley Nuc;eal- 8 lantJlnit 2 !;heet !. of 5 r D3CUMENTATION REF. ENVin0 WMENT QUAL OUTSTA NDING l EQUIPMENT DESCRIPTIOld METHOD ITEMS SPEC OUAL SPEC. l OUAL RAMETER l SYsTE M: Pressurizer Safety and l OPERATING Note 4 flote 4 , ilimultaneous None Relief Valves TIME PLANT ID NO. - 30 Days 4 ,re i st COMPONENT: Electrical Penetratfor T MP. ;imultaneous None 316 (Low Voltage) Note 1 340 ' 1 4 're s t . MANUFACTURER: General Electric PR ESSURE 63.1 simultaneous None
'^I 4
, Note 2 118 2 rest MODEL NUMBER: 100 Series RELATIVE t;imultaneous None HUMIDITM 100 4 100 3 rest CHEMICAL 1 None FUNCTION: Containment Isolation II3B03+ 11 3 B O3+ limultaneous SPRAY NeOll Naoll 3 4 re n t '
5 x 107 1 x los , ACCURACY: SPEC: RADIATION Rede Rads DEMON: N/A None l 3 4 ';equential SERVICE: Electrical Penetration AGING ! LOCATION: Containment 4 lequential None - Note 3 40 yrs. None E FLOOD LEVEL ELEV: 115' SUBMER- 7 ABOVE FLOOD LEVEL: yes GENCE NM NM WA None g.
' DOCUMENTATION
REFERENCES:
NOTES: J. M. Farley FSAR Figure 6.2-6
!. J. M. Farley FSAR Figure 6.2-4 1 J. M. Farley FSAR Table 3.11-1 1. LOCA temperature profile from Figure 2 attached at the end of this chapter.
- s. G:ntral Electric Co. Report Low FSAR Figure 6.2-40 will be updated in the July 22, 1982 FSAR revision.
Voltage Electrical Containment Penetration Qualification Test 2. LOCA pressure, profile from Figure 1 attached at the end of this chapter. Report (Bechtel File E22-98) FSAR Figure 6.2-39 will be updated in the July 22, 1982 FSAR revision.
- 3. Aging requirements in accordance with NUREG-0588, Section 4, Category II.
- 4. This equipment is not essential to achieve a safe shutdown ennditinn for anu licencoa nnr ana +horornro nn onnratinn t irno ic cnocified.
SYSTEM COMPONENT EVALUATION WORK SHEET Section 3 . Joseph M. Farley Nuclear Plant Unit 2 Sheet 5 cf, 5 ENVIHONMENT DOCUMENTATION REF.* OtlAL. OUTSTAND 400G ll ITEMS EMMMEMN - PARAMETER SPEC. QUAL. SPEC. l OUAL METHOD
'r- ~ Note 4 Note 4 None SYSTEM: Pressurizer Safety and OPERATING Simultaneous TIME 4 Test PLANT ID NO. Relief.. Val.ves 30 Days TEMP. 316 Simultaneous None COMPONENT: Cable Power and Controh I II Note 1 346 1 4 Test l
MANUFACTURER:W e Okonite Company PRESSURE 63.1 Simultaneous None (PSIA) Note 2 113 2 4 Test Simultaneous None MODEL NUMBER: None RELATIVE HUMIDITY (in 100 100 3 4 Teat CHEMICAL H350 3+ H3 B03+ Simultaneous None FUNCTION: Electrical Power and Control SPRAY NaOH NaOH 3 4 Test - ACCURACY: ' SPEC: N/A RADIATION 5 x 10 7 2 x 10 8 DEMON: Rads. Rads. 3 4 Sequential None SERVICE: Electrical Safety Systems LOCATION: Containment AGING Note 3 40 yrs. Note 3 4 Sequential None ! n 2 FLOOD LEVEL ELEV: 115'-0" SUBMER- None d A80VE FLOOD LEVEL: yes GENCE None N/A N/A N/A N/A .g NOTES:
' DOCUMENTATION
REFERENCES:
- 1. J. N. Farley FSAR Figure 6.2-6 1. IDCA temperature profile from Figure 2 attached at the end of thae chapter.
- 2. J. N. Farley FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be updated in the July 22, 1982 FSAR revision.
- 3. J. N. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Figure 1 attached at the end of this chapter.
4 Se Okonite Company Engineering FSAR Figure 6.2-39 will be updated in the July 22, 1982 FSAR revision. Reports.No. 141 dated 2-29-72 & 3. Enclosure 4 to IE Bulletin 79-01B. Okonite Report No. N-1 dated 4. This equipment is not essential to achieve a safe shutdown condition for any July 3, 1978. . ;; , ; : licensed DBE and, therefore, no orerating ime is speci(.ted.,,. l
1 i MASTER LIST 4 l Section 4 t Joseph M. Farley Nuclear Plant Unit 2 Sheet 1 of 5 (CLASSIE ELECTRICAL EQUIPMENT REOUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS) SYSTEM: B13/B31 Pressurizer Safety Valve Position Indication NUREG-0737. II.D.3 COMPON EN TS PLANY ID NUMBER GENERIC NAME MANUFACTURER MODEL BLDG ELEV. 2VYKH174A ' Cable Okonite None CmT [> 115 ' -0" Q2B13G001-B Terminal Box States Company Type ZWM cmT >115'-0" 2VBL5099G Cable Okonite None Cm? '7_115 ' -0" 2VBL5099H Cable Okonite Hone cmT 711s'-0" 2VBL5099J Cable Okonite None cmT 7 1158-0" General Q2T52B025-B Ctmt. Penet. Elettric 100 Series cmT 115'-0" General 7 115'-0" Q2TS2B022-B C tm_t . Penet. Electric 100 serien cmT 92_B13ZS2034 Position switch NMiCO EA-180 cmT 7 11s '-0" Q2B13ZS2035 Position switch NAMCO EA-180 cmT 7115'-0" Q2B13ZS2036 Position switch NAMCO EA-180 CMT 7115'-0" i N2B31ZSO444B Limit switch NAMCO EA-180 cmT 7115'-0" _
~
. l l R23)JZSO445A Limit switch NMCO EA-180 cmT >115'-0" l States N2B31SV0444BA-B/JB Junction Box Company Type ZWM CIMT > 115 '-0" States N2b31sV0445AA-A/JB Junction Box Company Type ZWM CmT >115'-0" General Q2_T52)019-A Control Pentrn. Electric 100 Series CmT 7115'-0" 4 General Q2T52B038-B Control Pentrn. Electric 100 Series CmT >115'-0" 2 VAL 5035D Control cable Okonite None CmT 7115'-0" l 2VBL5020D Control Cable Okonite None Cmr M 15'-0" General QAT3528007A Control Penetra, ripetric inn drine ETMT s114'-0" IVXKH174A Cable Okonite None CTMT >115'-0" GPO 1374 Rev. 6/81
SYSTEM COMPC NENT EVAltlATION WOftK SHEET Section 4 Joseph M. Farley Nucim r Plan' Unit 2 , Sheet 2 of 5 L I ENVIRONMENT DOCUMENTATION REF. OUTSTANDONG QUAL PARAMETER SPEC. QUAL. SPEC. QUAL. MET M ITEMS SYSTEM: System-Pressurizer Safety OPERATING Note 4 Note 4 valve Position TIME Simultaneous None PLANT ID NO. -30 Days 4
. Indication Test i COMPONENT: Cable Power and Contro5 TEMP. 316 Simultaneous None
( F) Note 1 4 346 1 Test MANUFACTURER:%e Okonite Company PRESSURE 63.1 Simultaneous None IPSIAI Note 2 113 2 4 Test MODELNUM8ER: None RELATIVE Simultaneous None HUMIDITY t%) 100 100 3 4 Test FUNCTION: Electrical Power and CHEMICAL H3 B03+ H3 B03+ Simultaneous None Control SPRAY 4 NaOH NaOH 3 Test 8 NA *
, N/A RADIATION 5 x 10 I 2 x 10 Rada. Rads. 3 4 Sequential None SERVICE: Electrical Safety Systems LOCATION: Containment AGING Note 3 40 yrs. Note 3 4 Sequential None l E!
FLOOD LEVEL ELEV: 115'-O" SUBMER. O ABOVE FLOOD LEVEL: yes GENCE None N/A N/A N/A N/A None 6 8
' DOCUMENTATION
REFERENCES:
NOTES:
- 1. J. M. Farley,FSAR Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end of.th'ia chapter.
- 2. J. M. Farley FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be updated in the July 22, 19t$2 FSAR revision.
- 3. J. M. Farley FSAR Table 3.11-1 2. IIKA pressure profile from Figure 1 attached at the end of this chapter.
- 4. We Okonite Company Engineering FSAR Figure 6.2-39 will be updated in the July 22, 1962 FSAR revision.
Reports.No. 141 dated 2-29-72 & 3. Enclosure 4 to IE Bulletin 79-01B. Okonite Report No. N-1 dated . July 3, 1978.
- 4. This equipment is not essential to achieve a safe shutdown condition for anv licensed DBE and, therefore, no operating time is specified.
$ fSTEM COMPONENT EVALUATION WORK SHEET Section 4 2 , ,, Sheet 3 of 5 Joseph M. Ferley Nuclear I'lant . Unit ,
ENVIRONMENT DOCUMENTATION REF. QUAL. OUTSTANDING
- METHOD ITEMS PARAMETER SPEC. OUAL SPEC. QUAL SYSTEM:h$YYoSNni[dakNn OPERATING Note 5 Note 5 Simultaneous None .
TIME - 4 Test PLANT ID NO. 7 Daya . Simultaneous None I COMPONENT: Terminal Block with TEMP. 316 307 I NEMA 4 Enclosure ( F) Note I Note 4 1 4 Test. I MANUFACTURER: States Company PRESSURE 63.1 Simultaneous None l (PSIA) Note 2 80 2 4 Test
.l Simultaneous None l MODEL NUMOER: Type ZWM RELATIVE .
HUMIDITY (%) 100 100 3 4 Test ! Catalog M-25012 I Simultaneous None l FUNCTION: Conductor Termination CHEMICAL H3 503+ H3 B03+ SPRAY NaOH 3 4 Test i NaOH I 7 8 , ACCURACY. SPEC: N/A 5 x 10 1 x 10 None l RADIATION Rads. 3 4 Sequential DEMON: Rads. SERVICE: Electrical Safety Systems LOCATION: Containment AGING Note 3 40 yrs. Note 3 4 Sequential None ! n-FLOOD LEVEL ELEV: 115'-0" SUBMER-None o GENCE None N/A N/A N/A N/A ABOVE FLOOD LEVEL: yes 8 NOTES:
' DOCUMENTATION
REFERENCES:
- 1. J. M. Farley FSAR Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end of.th1Js chapter.
- 2. J. M. Farley FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be updated in the July 22, 1982 FSAR revision.
- 3. J. M. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Fiaure 1 attached at the end of this chapter. i FSAR Figure 6.239 will be updated in the July 22, 1982 FSAR revision. l
- 4. Wyle Laboratories NEQ Test Report ,
l 44354-1 dated 3-8-79 3. Enclosure 4 to IE Bulletin 79-01B.
- 4. Equipment surface temperature during IACA does not exceed qualification temperature.
- 5. This equipment is not essential to achieve a safe shutdnwn enndition for any licensed DBE and, therefore; no operating time is specified. /.
SYSTEM COMPONENT EVALU ATION WOF.K SHEET Section 4 2 Sheet 4 of 5 Joseph M. Farley Nuclear Plant Unit _ ENVIRONMENT DOCUMENTATION REF.' ObAL. OUTSTANDING METHOO UN EQUIPMENT DESCRIPTION SPEC. QUAL. SPEC. OUAL PARAMETER l "i 8 OPE ATING Ncce 4 Note 4 g g,,g g,,,,,,i None SYSTEM:h@fo#'[t'1on s fnd1ca 1Yn 4 Teat PLANT ID NO. 30 Daya ( TEMP. Simultaneous None
- COMPONENT
- Electrical Fenetration 316 (Low Voltage) ( F) Note 1 1 4 Test l 340 Simultaneous None MANUFACTURER: General Electric PRESSURE 63.1 (PSIA) Note 2 2 4 Test 118
' Simultaneous None MODEL MUMBER: 100 Series RELATIVE -
HUMIDITY (%) 100 100 3 4 Test CHEMICAL H3 503+ Simultaneou. None FUNCTION: Containment Isolation A H3 B03+ NaOH NaOH 3 4 Test ACCURACY: SPEC: N/A RADIATION 5 x 10 7 i x 10 8 4 Sequential None DEMON: Rade. Rads. 3 g SERVICE: Electrical Penetration AGING yog,3 None 4 Sequential None : LOCATION: Containment 40 yrs. R 2 FLOOD LEVEL ELEV: 115'-O" SUBMER- None o GENCE None N/A N/A N/A N/A ABOVE FLOOD LEVEL: yes 8 NOTES:
' DOCUMENTATION
REFERENCES:
- 1. J. N. Farley FSAR Figure 6.2-6 1. LOCA temperature profile frem Figure 2 attached at the end of th'io chapter.
- 2. J. N. Farley'FSAR Figure 6.2-4 FSAR Figure 6.2-40 will ec updated in the July 22, 1982 FSARstevision.
- 3. J. N. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Figure 1 attached at the end of this chapter.
- 4. Ceneral Electric Co. Report Low FSAR Figure 6.2-39 will be updated in the July 22, 1982 FSAR revision.
Voltage Electrical Containment 3. Enclosure 4 to IE Bulletin 79-018. Penetration Qualification Test 4. This equipment is not essential to achieve a safe shutdown condition for Report (Bechtel File E22-98) any licensed DBE and, therefore, no operating time is specified.
~
SYSTEM COMPONENT EVALUATION WORK SHEET Section 4 - Joseph M. Farley Nuclear Plant Unit 2 ___ Sheet 5 of 5 ENVIRONMENT DOCUMENTATION REF. OUTSTANDHOG
' QUAL.
METHOO ITEMS PARAMETER l SPEC. QUAL. SPEC. l OUAL SYSTEM:h{ e"Yos'1[IE [Ed1[afft[n OPE R ATING Note 5 Note 5 Simultaneous None PLANT 10 NO. TIME COMPONENT: Limit Switch TEMP. 3[6 . Simultaneous None , (OF) Note I 340 1 4 Test MANUFACTURER: Namco Controls PRESSURE 63.1 Simultaneous None (PSIA) Note 2 84.7 2 4 Test < MODEL NUMBER: EA-180 - RELATIVE Simultaneous None HUMIDITY l%) 100 100 3 4 Test FUNCTION: Valve Position CHEMICAL H350 3+ SPRAY H3 B03+ .:imultaneous None Indication NaOH NaOH 3 4 Test
" N/A RADIATION 5 x 10 I 2 x 10 8 D -
Rads. 4 None Rads. 3 Sequential l SERVICE: l LOCATION: Containment AGING Note 3 Mote 4 Note 3 4 Sequential None ! n FLOOD LEVEL ELEV: 115'-0" SUBMER. 2 ABOVE FLOOD LEVEL: yes GENCE None N/A N/A N/A N/A None 6 8
'OOCUMENTATION
REFERENCES:
NOTES:
- 1. J. M. Farley FSAR Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end of this chapter.
- 2. J. N. Farley.FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be, updated in the July 22. 1982 FS,AR revision.
- 3. J. N. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Figure 1 attached at the end of this chapter.
4 Acme-Cleveland Development Co FSAR Figure 6.2-39 will be updated in the July 22, 1982 FSAR revision. Qualification Report for NAMCO 3. Enclosure 4 to IE Bulletin 79-015. Controls Limit Switch Model 4. Ihe Qualified life is being determined and will be reflected in surveillance & EA-180 dated 11-21-77 t QTR105 maintenance procedure. dated 8-28-80. 5. This equipment is not essential ta achiava a cara cho+dnwa cnaditinn far anv licensed DRF and, thorpfnre, nn cperating time is specified.
MASTER 1.lST Srction 5 Joseph M. Farley Nuclear Plant Unit 2 Sheet 1 of 3
- C;.;,00:E ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS)
D21 - High Range Containment Radiation ; NUREG-0737, II.F.1.3 3,,,g,p
$ COMPONENTS PLAhlT ID NUMBER GEN E RIC NAME MANUFACTURER MODEL BLDG. ELEV.
IVA]5011E , Cable Victoreen Note 1 CMT )115'-0" 2VAIS011G Cable Victoreen Note 1 CMT >115'-0" 02D21RE0027A-A Radiation Detector Victoreen 877-1 CET > 115 ' -0" 2VBIS009E Cable Victoreen Note 1 CMT 7115'-0" 2VBIS009G Cable Victoreen Note 1 CmT 7115'-0" Q2D21RE0027B-B Radiation Detector Victoreen 877-1 CmT 7 115'-0"
'" ,7115'-0"
^ " ?!009-A CMT Penet. 100 Series CmT 7
General Q2TS2B011-B C MT Penet. Electric 100 Series CMT 7115'-0" Note 1 - Cab:,es have been qualifi ed along with de tector. I 2 4 9.
._j GPO 1374 Rev. 6/81 ,
SYSTEM COMPO JENT EVALUATION WOR ( SHEET Sectios 5 2 Sheet 2 of 3 Joseph M. Farley Nucler Plant Unit _ ENVIPONMENT DOCUMENTATION REF. OlfAL. OUTSTANDING MET M IN EQUIPMENT DESCRIPTION OUAL SPEC. OUAL.
--PARAMETER l SPEC. l l
" " Note 4 SYSTEM: a OPERATING Note 4 Simultaneous' None PLANT IU NU. . 30 Days 4 Test COMPONENT: Radiation Detectors TEMP. 316 Simultaneous None
. ( F) Note 1 360 1 4 Test MANUFACTURER: Victoreen PRESSURE 63.1 Simultaneous None (PSIA) Note 2 133 2 4 Test Simultaneous None MODEL NUM8ER: 877 1 RELATIVE HUMIDITY (%) 100 100 3 4 Test H380 3+ Simultaneous None FUNCTION: Radiation Monitor CHEMICAL H3 B03+
SPRAY NaOH NaOH 3 4 Teat 8
^ N/A RADIATION 5 x 10 7 2.2 x 10
- Rads. Rads. 3 4 Sequential None SERVICE: Post Accident Monitor ,
LOCATION: Containment E1.155 AGING Note 3 40 yrs. Note 3 4 Sequential None ! R FLOOD LEVEL ELEV: 115'-0" SU3MER- o GENCE None N/A N/A N/A N/A None ABOVE FLOOD LEVEL: yes D NOTES:
' DOCUMENTATION
REFERENCES:
- 1. J. M. Farley FSAR Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end of tifia chapter.
- 2. J. M. Farley FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be updated in the July 22, 1982 FSAR revision.
- 3. J. M. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Figure 1 attached at the end of this chapter.
4 Victoreen Test Report 950.301 FSAR Figure 6.2-39 will be updated in the July 22, 1982 FSAR revision.
- 3. Enclosure 4 to IE Bulletin 79-01B.
l' dated 6-19-81
- 4. This equipment is not essential to achieve a safe shutdown condition for any licensed 00E and, therefore, :10 operatino time is specified.
SYSTEM COMFONENT EVALUATION WORK SHEET Section 5 Sheet 3 ef 3 hh M. Farley Nuciw Plait Unit . , . . 2 j ENVIRONMENT DOCUMENTATION REF.* AL, OUTSTANDNeG METHOO UN PARAMETER SPEC. OUAL SPEC. QUAL High Range Containment OP ATING None SYSTEM: Radiation Note 4 Note 4 Simultaneous NT 1D w. . 30 Days 4 Test COMPONENT: Electrical Penetration TEMP, 316 Simultaneous None (Low Voltage) ( F) Note 1 4 Test 340 1 MANUFACTURER: General Electric PRECE 4E 63.1 Simultaneous None
; (PSIA) Note 2 4 Test 118 2 Simultaneous None MODEL NUMBER: 100 Series RELATIVE HUMIDITY (%) 100 100 3 4 Test CHEMICAL H 350 3+ None FUNCTION: Containment Isolation H3 B03+ Simultaneous SPRAY NaOH 4 Test NaOH 3 l
ACCURACY: SPEC: N/A RADIATION 5 x 10 7 1 x 10 8 DEMON: Rads. Rads. 3 4 Sequential None SERVICE: Electrical Penetration l AGING Note 3 4 Sequential LOCATION: Containment 40 yrs. None None - FLOOD LEVEL ELEv: 115'-O" SUBMER. None N/A N/A N/A ABOVE FLOOD LEVEL: yes GENCE N/A None f
' DOCUMENTATION
REFERENCES:
NOTES:
- 1. J. M. Farley FSAll Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end of this chapter.
- 2. J. N. Farley FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be updated in the July 22, 1982 FSAR' revision.
- 3. J. N. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Figure 1 attached at the end of this chapter.
- 4. General Electric Co. Report Low FSAR Figure 6.2-39 will be updated in the July 22, 1982 FSAR revision.
Voltage Electrical Containment 3. Enclosure 4 to IE Bulletin 79-018. Fenetration Qualification Test 4. This equipment is not essential to achieve a safe shutdown condition for any l Report (Bechtel File E22-98) licensed DBE and, therefore, no operating tine is specified.
MASTER LIST saetion 6 Joseph M. Farrey Nucle:r Plant Unit 2 Sheet 1 ef MLAss it ELECTRICAL EQUIPMENT REOutRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS) sysTam: E17 - %droaen Recombiner System _NUREG-0737. II.E.4.1 As discussed in Chapter 2 to this appendix, dedicated hydrogen penetrations are not applicable to Farley Nuclear Plant. The qualified status of electrical equipment auociated with the hydrogen recombiner system has been verified.in a previous NUREG-0588 response,.Section C.2.7, dated July 1, 1981'. . i S 4 e
MASTER LIST Sectinn 7 Joseph M. Farley Nuclear Plant Unit 2 Sheet 1 (CLASS lE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCIDENT CONDITIONS) SYSTEM: G-21 Liquid Waste Disposal (Narrow Range Containment Sump Level); PUREG-0737,II.F.] COMPON E NTS PLANT ID NUMBER GENERIC NAME MANUFACTURER MODEL - B L DG. ELEV. Q2G21LT3282A-A - Level Sensor Gems-Delaval XM54854 CTMT 80'-0" , I Q2G21LT3282B-B Level Sensor Gems-Delaval XM54854 CTKr 80'-0" , 1 2VA15023A Control Cable Okonite None CTKr Various 2VBIS023A C'ontrol Cable Okonite None C' INT Various General Q2T52B007-A Control Penetration Electric 100 Series CTMr '> 115 '-U " General Q2T52B022-B Control Penetration Electric 100 Series CIMT > 115'-0" 1 - 2 l GPD 1374 Rev. 6/81 - l
SYSTEM COMPONENT EVALUATION WORK SHEET Section 7 Joseph M. Farley Nuclear Plant Unit 2 Sheet 2 of 4
.t... . . , .-
ENVIRDNMENT DOCUMENTATION REF. QUAL. OUTSTANDING QUAL. METHOD ITEMS PARAMETER SPEC. SPEC. l OUAL SYSTEM: Liquid Waste Disposal OPERATING PLANT ID NO. TIME Note'5 Note 5 yate 4 got,4 yet,4 COMPONENT: Level Sensor TEMP, 316 OII Note i Note 4 1 Note 4 Note 4 MANUFACTURER: TransAmerica Delava:1 PRESSURE 63.1 Gems Sensor Div. IPSIA) Note 2 Note 4 2 Note 4 Note 4 . MODEL NUMBER: XM54854-323 RELATIVE HUMIDITY (%) 100 Note 4 3 Note 4 Note 4 FUNCTION: Level Indication CHEMICAL H3 BO3+ SPRAY NaOH Note 4 3 Note 4 Note 4 ACCURACY: SPEC: 7 N/A RADIATION 5 x 10 DEMON: Rads. Note 4 3 Note 4 Note 4 SERVICE: Containment Sump g LOCATION: Containment AGING Note 3 Note 4 Note 3 Note 4 Note 4 ;:: n FLOOD LEVEL ELEV: 115'-0" SUBMER. b i ABOVE FLOOD LEVEL: No GENCE Note 4 N/A N/A N/A N/A 6 (DOCUMENTATION
REFERENCES:
NOTES: ( 1. J. M. Farley FSAR Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end of this chapter. l
- 2. J. M. Farley'FSAR Figure 6.2-4 FSAR figure 6.2-40 will be updated in the July 22, 1982 FSAR" revision.
l 3. J. N. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Figure 1 attached at the end of this chapter. l FSAR Figure 6.2-39 will be updated in the July 22, 1982 FSAR revision.
- 3. Enclosure 4 to IE Bulletin 79-018.
- 4. Qualification testing is scheduled to be completed 3rd quarter 1982 by Wyle Labs for Gems.
- 5. This equipment is not essential to achieve a safe shutdown condition for any licensed DBE and, therefore, no operating time is specified.
. i
l iYSTEM COMPorIENT EVAlb&lON WOR SHEET . Section 7 Joseph M. Farfei Nucles Plant Unit 2 __ Sheet _ s 3 of_ 4 ENVIR JNMENT ')OCUMENTATlON REF. QUAL OUTSTANDlNG EWIN M E Rim M MET M UN "hARAMETE R $PEC. QUAL. SPEC. l OUAL SYSTEM: Liquid Waste Disposal OPERATING Note 4 Note 4 simultaneous None PLANT ID NO. ME 4 30 Daye Teat COMPONENT: Cable Power and Controh TEMP. 316 - Simultaneous None , (8F) Note 1 4 Test 346 1 MANUFACTURER: De Okonite Company PRESSURE 63.1 Simultaneous None (PSIA) Note 2 2 4 Test 113 RELATIVE
. Simultaneous N0ne MODELNUM8ER: None 4 HUMIDITY (%) 100 100 3 Teat l l
l FUNCTION: Electrical Fower and CHEMICAL H3 803+ H3 503+ Simultaneous hone Control SPRAY NaOH NaOH 3 4 Test 7 8 N/A RADIATION 5 x 10 2 x 10 D - 3 4 Sequential None Rads. Rads. SERVICE: Electrical Safety Systems AGING Note 3 40 yrs. Note 3 4 Sequential None @ LOCATION: Containment FLOOD LEVEL ELEV: 115'-0" SUBMER. N0ne GENCE None N/A N/A N/A N/A d ABOVE FLOOD LEVEL: yes %
' DOCUMENTATION
REFERENCES:
NOTES:
- 1. J. M. Farley FSAR Figure 6.2-6 1. IDCA temperature profile from Figure 2 attached at the end of th'is chapter.
- 2. J. M. Farley'FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be updated in the July 22. 1982 F5AR r'evision.
- 3. J. M. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Flaure 1 attached at the end of this chapter.
FSAR Figure 6.2-19 will he. undated in the July 22. 1982 FSAR revision.
- 4. %e Okonite Company Engineering Reports.No. 141 dated 2-29-72 & 3. Enclosure 4 to IE Bulletin 79-015.
Okonite Report No. N-1 dated 4. This equipment is not essential to achieve a rafe shutdown condition for any July 3, 1978. licensed DBE and, therefore, no operating time is specified.
SYSTEM COMPONENT EVALL'ATION WOF K SHEET Sectica 7 - 2 Sh*'t 4 of 4 Joseph M. Farley Nuclear Plant Unit _ ENVillONMENT DOCUMENTATION ItEF. OdAL. OUTSTANDNIG EMMEMEMEM METHOO ITEMS PARAMETER SPEC. QUAL SPE C. QUAL. SYSTEM: Liquid Waste Disposal OPERATING Note 4 Note 4 Simultaneous None TIME PLANT ID NO. 30 Days 4 Test COMPONENT: Electrical Fenetration TEMP. 316 . Simultaneous None , (Iow Voltage) ( F) Note 1 1 4 Test 340 MANUFACTURER: General Electric PRESSURE 63.1 Simultaneous None (PSIA) Note 2 4 Test 118 2 RELATIVE Simultaneous None RIODEL MUMBER: 100 Series 100 HUMIDITY (%) 100 3 4 Teae CHEMICAL H350 3+ None FUNCTION:Conttainment Isolation H3 B03+ Simultaneous A NaOH 4 Test NaOH 3 ACCURACY: SPEC: N/A RADIATION 5 x 10 7 1 x 10 8 DEMON: Rads. 4 Sequential None Rads. 3 SERVICE: Electrical Fenetration LOCATION: Containment AGING Note 3 40 yrs. None 4 Sequential None ! 115'-0" SU8MER. 2 FLOOD LEVEL ELEV: 5 A80VE FLOOD LEVEL: yes GENCE None N/A N/A N/A N/A None 6
'OOCUMENTATION
REFERENCES:
NOTES:
- 1. J. N. Farley FSAR Figure 6.2-6 1. LOCA temperature profile from Figure 2 attached at the end of this chapter.
- 2. J. M. Farley FSAR Figure 6.2-4 FSAR Figure 6.2-40 will be updated in the July 22, 1982 FSAR. revision.
- 3. J. M. Farley FSAR Table 3.11-1 2. LOCA pressure profile from Figure 1 attached at the end of this chapter.
- 4. General Electric Co. Report Low FSAR Figure 6.2-39 will be updated in the July 22. 1982 FSAR revision.
Voltage Electrical Containment 3. Enclosure 4 to IE Bulletin 79-018. Penetration Qualification Test 4- This equipment is not essential to achieve a safe shutdown condition for any Report (Bechtel File E22-98) licensed DRF and, therefore, no operating time is specified.
MASTER List g, egg,, 8 l Joseph M. Fwfey Nuefw Plant Unit ? Sheet 1_ cf I ICLASS BE ELECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCloENT N23 - Auxiliary Feedwater System NUREG-0737, II.E.1.2 _ _ p ,7,, As discussed in Chapter 2 to this appendix, the qualified status of electrical equiptr ,
~
i associated with the auxiliary feedwater system has been verified.in a previous
)
Nt! PEG-0588 response dated July 1,1981. e 6 M
l MASTER UST 9 !
,' g3, g g.,
Joseph M. Farley Nuclear Plant M 2 Shest_1 cf __ ICLAss it ILECTRICAL EQUIPMENT REQUIRED TO FUNCTION UNDER POSTULATED ACCloENT CONDITaoNS) sysitM: _V arious - Containment Isolation Dependab.1111y NUREG-0737. II.E.4.2 As discussed in Chapter 2 to this appendix, the qualified status of this equipment leaddressed by a previous NUREG-0588 response dated August 25 and December 28, 1981, Sections C.2.3, C.2.4 C.2.6, C.2,9 and C.2,11 through C.2.20. ,- , 1
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MASTER UST sce tten 10 Juon M. Fwley Nuclear N ntunit 2 - Sh*- I- C' gtAgg ( ELECTRICAL EQUIPMENT REOulmEO 70 FUNCTION UNDER POSTULATED ACCIDENT coNoiTe0NSI Various - Automatic PORV Isolation System; NUREG-0737. II.K.3.1 g,,,, As discussed in Chapter 2 to this appendix, Alabams Power Company has determined that an automatic PORV isolation system could not appreciably enhance ' protection against alP6RV LOCA and no modifications are necessary. . e t i e G 4 6 1 4 t l l __3.., -. _ , , , _ . - - .-- - -
; MASTER LtST g:;,ggen 11 Jowph M. Farrey Ectw Plant Unit 2 $heet _ 2_ cf ICLAss et ELECTRtCAL EOutPMENT REQUIRED TO FUNCTION TENDER PosTut.ATED AcciotNT CONDITION $1 sysitw: Various - Automatic Trip of RCP's; NUREG-0737. II.K.3.5 As discussed in Chapter 2 to this appendix, it is the opinion of. Alabama Power Company that the resolution of this issue will be achieved without desigri modifications.
O a 1 f I } s
'~.
I \ t 5 l t I
Chapter 3 Table of Contents Section 1. Discussion Table 1. Installation Dates, Previously Required Extension to Implementation Dates, and Westinghouse Owners Group Position
- l i
l i , ,1
I. Discussion In letter dated April 23, 1982, Alabama Power Company committed to provide installation dates of TMI Action Plan equipment requiring environmental qualification as well as standard Westinghouse Owner's Group positions and previously requested extensions to implementation dates. This information is provided in the accompanying Table 1 with appropriate references to previous Alabama Power Company letters. l l Appendix 6, Chapter 3, 1-1 l
TABLE 1 Pag 21 of 4 . Westinghouse Owners Group NUREG-0737, Part # Installation Extension to Implementation Dates Positions II.B.1 The reactor coolant vents were No extensions were requested to N/A installed prior to exceeding 5% satisfy NUREG-0737. power in May 1981. Alabama Power Company has notified the NRC of the completion of the installation in I letter dated December 22, 1981. II.D.1 As discussed in Chapter 2, No extensions were requested to N/A installatibn of the fully qualified ' satisfy NUREG-0737. Upgrading the electrical equipment will be qualification of this equipment is l completed at the next refueling addressed by the requirements or outage. NUREG-0588. II.D.3 Modifications to provide positive No extensions were requested to N/A indication of pressurizer relief satisfy NUREG-0737. and safety valve position were installed prior to fuel load in March 1981 as discussed in Alabama Power Company letter dated January 14, 1981. II.E.1.2 In letter dated June 4, 1982, No extensions were requested to N/A Alabama Power Company stated that satisfy NUREG-0737. all modifications to satisfy this part of NUREG-0737 were implemented. The installation of these modifiations were completed prior to exceeding 5% power in May 1981.
TABLE 1 Paga 2 of 4 ., Westinghouse Owners Group i NUREG-0737, Part # Installation Extension to Implementation Dates Positions l II.E.4.1 No modifications were made to N/A N/A satisfy this part of NUREG-0737. Alabma Power Company has stated that this modification is not applicable to Farley Nuclear Plant in letter dated January 14, 1981. II.E.4.2 The identity of the equipment and No extensions were required to N/A its qualified status associated satisfy NUREG-0737. The schedule with this NUREG-0737 part is to upgrade the qualification of described in Chapter 2 to this this equipment is addressed by I appendix. The last modifications Alabama Power Company in letter to upgrade the qualification of dated December 26, 1981, to l l this equipment were completed prior satisfy the requirements of to exceeding 5% power in May 1981 NUREG-0588. and is discussed in Alabama Power Company letter dated December 28, 1981. II.F.1.3 As discussed in Alabama Power No extensions were required to N/A Company letter dated January 14, satisfy NUREG-0737. The schedule 1981, the modifications to satisfy to install the water tight this NUREG-0737 part were completed fitting, as a result of recent prior to exceeding 5% power in May test completion as discussed in 1981. Chapter 2, is scheduled for the next refueling outasi to satisfy NUREG-0588. l
TABLE 1 Pag 2 3 of 4' , Westinghouse Owners Group NUREG-0737, Part # Installation Extensions to Implementation Dates Positions II.F.1.5 As discussed in Alabama Power No extensions were required to N/A company letter dated January 14, satisfy NUREG-0737. 1981, the modifications to satisfy this NUREG-0737 part were completed prior to exceeding 5% power in May 1981. II.F.2 As discussed in Chapter 2 to this ' As stated in letter dated November N/A appendix,the response to address 16, 1981, Alabama Power Company this part of NUREG-0737 is deferred will provide a schedule to until the promulgation of the implement an integrated system to I associated draft licensing satisfy this part of NUREG-0737 documents. following the promulgation of the associatied draft licensing document. II.K.3.1 As discussed in Chapter 2 to this N/A WCAP-9804 was appendix, Alabama Power Company transmitted to does not propose any modifications the NRC Staff to resolve this issue. by owners group letter 0G-52, dated March 13, 1981.
TABLE 1 Paga 4 of 4 '- Westinghouse Owners Group NUREG-0737, Part # Installation Extensions to Implementation Dates Positions II.K.3.5 As discussed in Chapter 2 to this N/A Model analyses Appendix, Alabama Power Company were submitted does not propose any modificaions to the MRC to resolve this issue. Staff in owners group letter 0G-45, dated December 3, 1980, and owners group
~
- letter OG-50, dated March 23, 1981.
.E Chapter 4 - Summary of Outstanding Items As discussed in Chapter 2, the following three types of equipment were installed without complete qualification documentation. No of Chapter 2 Manufacturer Generic Name Model Items Reference Target Rock Solenoid valve 79AB001 4 Section 2 ASCO Solenoid valve HTX8320A22V 4 Section 3 Victoreen Radiation detector 877-1 2 Section 4 GEMS-Delaval Level sensor XM-54854 2 Section 7 The Target Rock solenoid valves and GEMS-Delaval level trans-mitters are presently undergoing qualification testing, which is expected to be completed during the fourth and third quarter of 1982, respectively. The test report for the Victoreen radiation detectors was recently evaluated. As discussed in Chapter 2, the evaluation of the test report indicates a water-tight fitting is necessary to protect the cable connection and to establish simi-larity with the test specimen. This modification will be completed during the next refueling outage. The ASCO solenoid valves lack adequate qualification documentation and are scheduled to be replaced at the next refueling outage. Other than the ASCO solenoid valves, all of the above equipment were installed prior to the completion of the qualification test program and the evaluation of the associated test reports. Alabama Power Company installed this equipment in order to provide the state-of-the-art coincident with the implementation dates required by NUREG-0737. Alabama Power Company will continue to monitor the progress of these ongoing qualification test programs. The ASCO scienoid valves will be installed to satisfy NUREG-0588. Appendix 6, Chapter 4}}