ML20153D667
| ML20153D667 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 08/31/1988 |
| From: | PORTLAND GENERAL ELECTRIC CO. |
| To: | |
| References | |
| PGE-1025-A-05, PGE-1025-A-5, NUDOCS 8809060003 | |
| Download: ML20153D667 (172) | |
Text
{{#Wiki_filter:ENVIRONMENTAL QUALIFICATION PROGRAM MANUAL s, ,) FOR THE TROJAN NUCLEAR PLANT PGE-1025 i The following information and checklist are furnished as a guide for , the insertion of new sheets for Amendment 5 into the Environmental ; Qualification Program Manual for the Trojan Nuclear Plant. This material is denoted by use of the amendment number and date in the I lower outside corner of the page. New sheets should be insert.ed as listed below. O Discard Old Sheet Insert New Sheet ' r (Front /Back) (Front /Back) 1/11 1/11 thru thru vii/ blank xi/ blank 2-1/2-2 2-1/2-2 thru thru 2-7/ blank 2-7/ blank 3-7/3-8 3-7/3-8 j Tab 3-2 (Sh 1)/ Tab 3-2 (Sh 2) Tab 3-2 (Sh 1)/ Tab 3-2 (Sh 2) thru thru 4-11/4-12 4-11/4-12 , D l 4-19/4-20 N D 4-19/4-20 lSA*A8883 8!88ljp 7;"d;;"!,l,3 l
Discard Old Sheet Insert New Sheet (Front /Back) (Front /Back) Tab 4-1 (Sh 1)/ Tab 4-1 (Sh 2) Tab 4-1 (Sh 1)/ Tab 4-1 (Sh 2) thru thru Tab 4-1 (Sh 13)/ Tab 4-1 (Sh 14) Tab 4-1 (Sh 13)/ Tab 4-1 (Sh 14) 5-7/5-8 5-7/5-8 Appendix 8A Appendix 8_A 8A-9/ blank 8A-9/ blank Tab 8A-1/ blank Tab 8A-1/ blank Tab 8A-2 (Sh 1)/ Tab 8A-2 (Sh 2) Tab 8A-2 (Sh 3)/ Tab 8A-2 (Sh 4) Figure 8A-1/ blank Figure 8A-1/ blank (nru thru Figure 8A-5/ blank Figure 8A-5/ blank Figure 8A-7/ blank Figure 8A-7/ blank thru thru Figure 8A-10/ blank Figure 8A-10/ blank Appendix 8C Appendix 8C Appendix 8C Title Fage/ blank Appendix 8C Title Fage/ blank 80-1/8C-2 8C-1/8C-2 thru thru 8C-16/ blank 8C-19/ blank Tab 8C-3/ Tab 8C-4 Tab 8C-3/ Tab 8C-4 thru thru l l Tab 8C-7/ blank Tab 8C-11/ blank l l Tab 8C-8 (Sh 1)/ Tab 8C-8 (Sh 2) Tab 8C-12 (Sh 1)/ Tab 8C-12 (Sh 2) I thru thru
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Tab 8C-8 (Sh 7)/ blank Tab 8C-12 (Sh 7)/ blank Amendment 5 (August 1988) l
i, ENVIRONMENTAL QUALIFICATION PROGRAM MANUAL' () FOR THE TROJAN NUCLEAR PLANT CONTENTS Section Title Page LIST OF EFFECTIVE PAGES. . . . . . . . . . . ... . x l{h i 3
1.0 INTRODUCTION
. . . . ............... 1-1 2.0 REGULATORY CRITERIA FOR ENVIRONMENTAL QUALIFICATION. . . . ............... 2-1 ;
2.1 RIGULATORY CRITERIA DEVELOPMENT. . . . . . . . . . 2-1 $ l 2.2 REGULATORY BASIS FOR ENVIRONMENTAL QUALIFICATION REVIEW . . . . . . . . . . . . . . . 2-4 3.0 EQUIPMENT REVIEWED FOR ENVIRONMENTAL 9 QUALIFICATION. . . . ............... 3-1 i ' 3-1 3.1 Sco?E OF EQUIPMENT . ............... i i 3.2 PROCEDURE FOR IDENTIFYING EQUIPMENT IMPORTANT TO SAFETY IN HARSH ENVIRONMENTS. . . . . . . . . . 3-2 , 3.2.1 IE Bulletin 79-01B Master List Development . . . 3-3 3.2.2 10 CFR 50.49 Master List Development . . . . . . 3-5 3.3 PROCEDURE FOR IDENTIFYING EQUIPMENT IMPORTANT , TO SAFETY IN HILD ENVIRONMENTS . . . . . . . . . . 3-7 3.4 PROCEDURE FOR IDENTIFYING OTHER EQUIPMENT SUBJECT TO ENVIRONMENTAL QUALIFICATION REVIEW. . . 3-8 3.5 POST-ACCIDENT SYSTEM OPERATING TIMES . . . . . . . 3-9 i
- 4.0 SPECIFIED ENVIRONMENTAL CONDITIONS AND f j EVALUATION CRITERIA. ............... 4-1 l i
4.1 TEMPERATURE AND PRESSURE . . . . . . . . . . . . . 4-1 4.1.1 Pipe Breaks Inside Containment . . . . . . . . . 4-2 i 4.1.1.1 Loss-of-Coolant Accident . . . . . . . . . . . . 4-2 1 4.1.1.2 Main Steam Line Break. . . . . . . . . . . . . . 4-2 4.1.2 Pipe Breaks outside Containment. . . . . . . . . 4-4 4.1.3 Normai Environment Temperatures. . . . . . . . . 4-5 ' 4.1.4 Evaluation Criteria. . . . . . . . . . . . . . . 4-5 1 4.1.4.1 Temperature. . . . ............... 4-5
; 4.1.4.2 Pressure . . . . . ............... 4-6 1
O i V i j Amendment 5 4 (August 1988) 4 4
l ENVIRONMENTAL QUALIFICATION PROGRAM MANUAL FOR THE TROJAN NUCLEAR PLAN'" CONTENTS Section , Title Pago 4.2 HUMIDITY . . . . . . . . . ... .... .... . 4-6 4.2.1 Pipo Breaks Insido and Outsido Containment . . . 4-6 4.2.2 Normal Environment Humidities. .... . .. . . 4-7 4.2.3 Evaluation Critoria. . . . . . ..... .... 4-7 4.3 CHEMICAL EFFECTS . . . . . . . . ......... 4-8 4.3.1 Pipe Breaks Inside Containment . ... .... . 4-8 4.3.2 Pipe Breaks Outside Containment. ... .... . 4-9 4.3.3 Evaluation Critoria. . . ... ........ . 4-10 4.4 RADIATION. . . . . . . . .. . ... ...... . 4-10 4.4.1 Radiation Dosos. . . . . . . ..... .. .. . 4-10 4.4.1.1 Accident and Normal Radiation Doso Estimatos . . 4-10 4.4.1.2 Radiation Damage Threshold Levels. ..... .. 4-11 4.4.1.3 Radiation Doso Rato Effects. ..... ... . . 4-13 4.4.1.4 Beta Doso Effects. . . . . . ..... . .. . . 4-13 4.4.2 Evaluation Critoria. . . . .. ..... .... 4-13 4.5 AGING. . . . . . . . . . . .. ....... .. 4-15 4.5.1 Basis and yproach . . . .. . .... . .. . . 4-15 4.5.2 Application of Arrhenius Methodology . . ... . 4-17 4.5.2.1 Selection of Activation F.norgy for Use in Arrhonius Methodology . . . . . ... . .. .. 4-20 4.5.3 Maintenanco and Surveillanco Program Considorations. . . . . . . ..... . .. .. 4-21 4.5.4 Evaluation Critoria. . . . .. . ... .... . 4-21 4.6 SUBHERGENCE. . . . . . . . . ... ... ... . . 4-22 4.6.1 Pipe Breaks Inside Containment . ... . .. . . 4-22 4.6.2 Pipe Breaks outside Containment. ... . .. . 4-23 4.6.3 Evaluation Celtoria. . . . . . . . .. ... . . 4-23 4.7 NORMAL ENVIRONMENT ELECTRICAL VARIATIONS . ... . 4-24 4.7.1 Evaluation Criteria. . . . . .. ... . . .. . 4-24 4.8 SYNERGISTIC EFFECTS. . . . . . . . ... .... . 4-25 4.9 MARGINS. . . . . . . . . . . .. .... . ... . 4-25 4.10 T*AT SEQUENCE. . . . . . . ... .... . ... . 4-27 4.10.1 Equipment Qualified to DOR Guidelines. . ... . 4-27 4.10.2 Equipment Qualified to NUREG-0588 Roquirements . 4-28 5.0 ENV1HONMENTAL QUALIFICATION REVIEW . .. . .... 5-1 Amendment 5 - 11 - ) (August 1988) l 1 i
l t ENVIRONMENTAL QUALIFICATION PROGRAM MANUAL FOR THE TROJAN NUCLEAR PLANT CONTENTS Section Title Pago 5.1 REVIEW OF ELECTRICAL EQUIPMENT IN HARSH' ENVIRONMENTS . . . ................ 5-1 ! 5.1.1 Review Process . ................ 5-1 L 5.1.1.1 Documents Used in the Review Process . . . . . . 5-2 5.1.1.1.1 Component Summary Sheet. . . . . . . . . . . . . 5-3 5.1.1.1.2 Equipment Qualification Summary Sheet. . . . . . 5- 4 l l 5.1.2 Review Procedure . ............... 5-5 5.1.2.1 Installed Equipment. . . . . . . . . . . . . . . 5-5 ( 5.1.2.2 New and Replacement Equipment. . . . . . . . . . 5-6 ' 5.1.2.3 Nonconforming Equipment. . . . . . . . . . . . . 5-7 l 5.2 REVIEW OF ELECTRICAL EQUIPMENT IN MILD ( ENV1HONMENTS . . . ................ 5-7 5.3 REVIEW OF OTHER EQUIPMNNT SUBJECT TO ENVIRONMENTAL QUALIFICATION. . . . . . . . . . . . 5-8 ; 5.4 MAINTENANCE AND SURVEILLANCE PROGRAM . . . . . . . 5-9 > t 6.0 ENVIRONMENTAL QUALIFICATION DOCUMENTATION. . . . . 6-1 6.1 CENTRAL FILE . . . .... . . . . . . . . . . . . 6-1 > I 6.2 EQUIPMENT QUALIFICATION
SUMMARY
FORMS. . . . . . . 6-1 I i 6.3 COHPONENT
SUMMARY
SHEETS . . . . . . . . . . . . . 6-2
7.0 REFERENCES
. . . . ................ 7-1 8.0 APPENDICES . . . . ................ 8-1 8.A Radiation Dose Assessment. . . . . . . . . . . . . 8A-1 !
8.B Thermal and Hydraulic Analysis of High-Energy ; Line Breaks in the Main Stcam Support Structuro . 8B-1 [ 8.C Thermal-Hydraulle Analysis of 2 High-Energy Lino r Break in the Turbine Building . . . . . . . . . . 8C-1 l 8.D Deleted. . . . . . . ............... SD-1 ; 8.E Deleted. . . . . . ................ 8E-1 l l l l i 6154k j 1
- 111 - Amendment 5 (August 1988)
ENVIRONMENTAL QUALIFICATION PROGRAM MANUAL FOR THE TROJAN NUCLEAR PLANT TABLES Number Tit,lo 3-1 Safety-Rolated Functions / Systems Needed to Mitigato a LOCA or HELB Accident 3-2 10 CFR 50.49 Master List 3-3 Deleted 3-4 Summary of NRC Environmental Qualification Requirements for NUREC-0737 Items II.B.3. II.F.1.1, and II.F.1.2 3-5 Functional Basis For Post-Acciduc.t System Operating Times 3-6 Post- Accident Swstem Operating Times 4-1 Trojan Nuclear Plant 2nvironmental Conditions Appendix 8A 8A-1 Calculated Trojan Total Integrated Dosos 8 A- 2 Review of Total Integrated Doso Calculations Appendix 8B 8B- 1 Major Milestones in the Evaluation of Main Steam Support Structuro Environmental Conditions Resulting from High-Energy Line Breaks 8B-2 RELAP4/ MOD 5 Main Steam Support Structure Model ParamcLers for a Main Feedwster Line Break and Original Main Steam Line Break Analysis BB-3 Pressuro Responso of the Main Steam Support Structuro Break Compartment (Volume 3) to a Main Feedwater Lino Break 88-4 Temperaturo Rosponse of the Main Steam Support Structure Non-Break Compartracnts to a Main Feodwater Line Break 8B-5 RELAP4/ MOD 6 Main Steam Support Sttmeture Model Parameters for a Main Steam Line Break i
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Amendment 5 O\
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4 , ENVIRONMENTAL QUALIFICATION PROGRAM MANUAL' i FOR THE TROJAN NUCLEAR PLANT 4 TABLES l i i P Number Title 88-6 Main Steam Line Blowdown Resulting in Worst-Case Temperature , Profile for the MSSS (RELAP4/ MOD 6 Analysis) , i < 8B-7 Pressure Response of the Main Steam Support Structure Break ( ,f Compartment (Volume 3) to a Main Steam Line Break (RELAP4/ i j MOD 5 Analysis) 8B-8 Temperature Response of the Main Steam Support Structure Non-Break Compartments to a Main Steam Line Break (RELAP4/M006 Analysis) ( t 85-9 Characterization of MSSS Compartments i i 8B-10 EQ Components in Main Steam Support Structure f , t Appendix 8C i 8C-1 Mass and Energy Release for a Main Feedwater Line Break , i in the Turbine Building i 8C-2 Mass and Energy Release for a Main Steam Line Break in the ' u !
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Turbine Building I i j 8C-3 Mass and Energy Release for a Main Steam Lino Break in the l Turbine Building l i 8C-4 Mass and Energy Release for a 0.8-Foot 2 Main Steam Line ' l Break in the Turbine Building ( l 8C-5 Mass and Energy Release for a 1.0-Foot 2 Main Steam Line i Break in the Turbine Building j 8C-6 Mass and Energy Release for a 1.2-Foot 2 Main Steam Line : Break in thJ Turbine Building ( } 8C-7 Pressure Response of Turbine Building Compartments for a Main Feedwater Line Break at 100-Percent Power j 8C-8 Temperature Response of Turbine Building Compartments to a ] Main Feedwater Line Break at 100-Percent Power ) - i j 8C-9 Pressure Response of Turbine Building Compartments for a !
- Main Steam Line Break at 100-Percent Power
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4 Amendment 5 l (August 1988) '
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ENVIRONMENTAL QUALIFICATION PROCRAM MANUAL FOR THE TROJAN NUCLEAR PLANT TABLES Number Title 2 8C-10 Temperature Responso of Turbino Building Compartments to a Main Steam Line Break at 100-Porcent Power 8C-11 Worst-Case Temperaturo Rosponso of Turbino Building Compart-ments to Partial Arca Main Steam Lino Break at 100-Porcent Power 8C-12 EQ Components in Turbino Building 9 6154k
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ENV1HONMENTAL QUALIFICATION PROGRAM MANUAL f 's FOR THE TROJAN NUCLEAR PLANT ( l FIGURES Number Title 4-1 Containment Pressuro vs. Time for the Design Basis Accident 4-2 Containment Temperature RosPonso for the Design Basis Accident 4-3 Qualification Requirement Profilo for Containment Pressurc 4-4 Qualification Requirement Profile for Containment Temperaturo 4-5 Qualification Requirement Profile for MSSS Pressure 4-6 Qualification Requirement Profile for MSSS Temperature 4-7 Qualification Requirement Profile for Turbino Building Pressure 4-8 Qualification Requirement Profile for Turbine Building Temperature 5-1 Environmental Qualification Review Proccas O)
\s- 5-2 Environmental Qualification Review Procedure for New and Replacement Equipment Appendix 8A 8A-1 Post- Accident Radiation Zones, Post-LOCA Mode, Elevations 5 Feet and 25 Feet 8A-2 Post-Accident Radiation Zones, Post-LOCA Mode, Elevation 45 Feet 8A-3 Post-Accident Radiation Zones, Post-LOCA Mode. Elevation 0; 61 Feet o 8A-4 Post- Accident Radiation Zones, Post-LOCA Modo, Elevation 17 Feet 8A-5 Post- Accident Radiation Zones, Post-LOCA Mode, Elevation 93 Feet 8A-6 Post-Accident Radiation Zones, Intact RCS Mode, Elevations l 5 Feet and 25 Feet l
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- vii - Ameadnent 5 (August 1988) l i
u ENVIRONMENTAL QUALIFICATION PR00 RAM MANUAL FOR "JHE TROJ AN NUCLEAR PLANT FIGURES Number Title 8A-7 Post-Accident Radiation Zones, Intact RCS Mode, Elevation 45 Fcot 8A-8 Post-Accident Radistion Zones, Intact RCS Mode. Elevation 61 Feet 8A-9 Post-Accident Radiation Zones Intact RCS Modo Elevation 77 Feet CA-10 Post- Accident Rad.8 ation Zones, Intact RCS Modo. Elevation 93 Feet 8 A..' 1 Volume Correction Factor (Full-Range) 8A-1. Volume Correction Factor (Small Volumes) 8A-13 Outside containment Doso Assessment Flowchart 8A-14 Inside Containment Dose Assessment Flowchart Appendix 8B 7 w 8B-1 Isometric View of the Main Steam Piping in the Main Steam Support Structure and Turbine Building 8B-2 Isometric View of the Feedwater Piping in the Main Steam Support Structure and Turbine Building 8B-3A Schematic of RELAP4/M005 Model BB-3B Schematic of RELAP4/ MOD 6 Mod.il 8B-4 Model of the MSSS. Elevation 45 Feet 0 Inches 8B-5 Nodalization of the MSSS. Elevation 54 Feet 6 Jnches 8B-6 Nodalization of the MSSS. Elevation 69 Feet 0 Inckes 8B-7 Nodalization of the MSSS, Elevation 100 Feet 6 Inches 8B-8 Long-Term MFLB Blowdown Curve 8B-9 Long-Term MSLB Blowdown Curve for 0-Percent of Rated Power l , 1 Amendment 5 - vili - O (August 19S8) i
ENV1HONMENTAL QUALIFICATION PROCHAM MANUAL FOR THE TROJAh NUCLEAR PLANT ( .
\, - FIGURES Number Title 8B-10A Break Volumo Responsc to MFLM h 8B-10B Short-Term Pressuro Responso of Break Volumo to MFLB 8B-11 h. ~'onso of Non-Break MSSS Compartments to MFLB 8B-12A Break Volume Responso to MSLB for 0-Percent of Rated Power 88-12B Short-Term Pressure Response of Break Volume to MSLB for 0-Percent of Rated Power 4
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- iX - Amendment 5 l (August 1988)
LIST OF EFFECTIVE PAGES PC E- 1025 Environmental Qualification Program Manual for the Trojan Nuclear Plant AMENDHENT 5 Amendment Amendment Page No. No. Date Title Pags Original July 1982 i thru vii 4 Aug. 1987 1-1 1 March 1984 2-1 5 Aug. 1988 2-2 4 Aug. 1987 e 2-3 and 2-4 5 Aug. 1988 2-5 and 2-6 4 Aug. 1987 2-7 5 Aug. 1988 3-1 2 June 1985 3-2 thru 3-4 1 March 1984 3-5 and 3-6 4 Aug. 1987 -- 3-7 5 Aug. 1988 0 3-8 2 June 1985 3-9 4 Aug. 1987 Table 3-1, Sheets 1 thru 3 4 Aug. 1987 .m i Table 3-2, Sheets 1 thru 65 5 Aug. 1988 Table 3-3 2 June 1985 Table 3-4 4 Aug. 1987 Table 3-5 1 March 1984 Table 3-6 4 Aug. 19P1 4-1 thru 4-11 4 Aug. 1987 -- 4-12 5 Aug. 1988 0 4-13 thru 4-18 4 Aug. 1987 4-19 5 Aug. 1988 4-20 thru 4-29 4 Aug. 1987 Tabic 4-1, Sheets 1 thru 14 5 Aug. 1988 Figures 4.-1 thru 4-4 1 March 1984 Figure 4-5 2 June 1985 Figures 4-6 thru 4-8 4 Aug. 1987 5-1 and 5-2 3 Dec. 1985 5-3 and 5-4 2 June 1985 5-5 and 5-6 4 Aug. 1987 g 5-7 5 Aug. 1988 5-8 thru 5-10 4 Aug. 1987 Figure 5-1 2 June 1985 Figure 5-2 4 Aug. 1987 6-1 thru 6-3 2 June 1985 7-1 and 1-2 4 Aug. 1987 8-1 Original July 1982 O Amendment 5 -x l August 1988)
i a LIST OF EFFECTIVE PAGES PGE-1025 ; Environmental Qualificat. ion Program Manual i for the Trojan Nuclear Plant ; a i j AMENDMENT 5
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)i ! Amendment Amendment ! i Page No. No. Data f Appendix 8A 8A-1 thru 8A-6 1 March 1984 8A-7 thru 8A-8 ,, Aug. 1987 - 8A-9 5 Aug. 1988 [ i Table 8A-1 5 Aug. 1988 , 4 Table PA-2 5 Aug. 1988 3 , 1 Figure 8A-1 5 Aug. 1988 Figure 8A-2 thru 8A-4 5 Aug. 1938 i Aug. 1988 Figure 8A-5 5 , Figure 8A-6 4 Aug. 1981 i Figure 8A-7 thtm 8A-10 5 Aug. 1988 G i Figure 8A-11 thru 8A-13 1 March 1984 j Figure 8A-14 Original July 1982 j Appendix 88 1 l l 88-1 thru 8B-25 4 Aug. 1981
; Tables 88-1 thru 8B-10 4 Aug. 1987 l i )igures 88-1 thtm 8B-12b 4 Aug. 1987 Appendix 8C 8C-1 thtv 8C-19 5 Aug. 1988 -
Tables 8C-1 thtm 8C-3 Table 8C-4 thtm 8C-12 4 5 Aug. 1987 Aug. 1988 0! Figures 8C-1 thtm BC-5 4 { ] Aug. 19b; ; I b j Appendix 8D j 8D-1 2 June 1985 l 1 ! j Appendix BE l i j j' 8E-1 2 June 1985 I i I 6154k j i j - Xi - Amendment 5 { j (August 1988) I 4 l l f
1 I [ 2.0 REGULATORY CRITERIA FOR ENVIRONMENT.;L QUALIFICATION t This Chapter summarizes the regulatory criteria, guidelines and ' standards used in the environmental qualification review of electric equipment important to safety in the Trojan Nuclear Plant. , i 4 i 1 2.1 REGULATORY CRITERIA DgVELOPMENT ! l l The Nuclear Regulatory Commission (NRC) has established crittria for l I environmental qualification of safety-related electrical equipment in : nuclear power plants. General Design Criterion 4 of Appendix A to ! 10 CFR 50 establishes the general requirement for environmental quell-J j fication of safety-related equipment. It states in part that "struc-tures, systems, and components important to safety shall be designed to l
- accommodate the effects of and to be compatible with the environmental ;
I conditions associated with normal operation, maintenance, testing, and
- postulated accidents, including loss-of-coolant accidents". The Trojan f j Nuclear Plant was originally designed to meet General Design Criterion 4; ,j i however, the NRC later developed specific guidelines and requirements 8 j to implement this general requirement for operating reactors.
- i 3 i Institute of Electrical and Electronic Engineers (IEEE) 323-1974, "IEEE Standards for Qualifying Class 1E Equipment for Nuclear Power Generating l
) Stations", is the current industry standard for environmental qualif t-l 1 cation of safety-related electrical equipment. This standard was first 4 ! issued as a trial-use standard, IEEE 323-1971. After substantial revi-sien, the current version was issued in 1974. Both versions of this j j ) standard set forth generic requirements for equipment qualification, i but the 1974 standard includes specific requirements for aging, marstes, and maintaining documentation records that were not included I in the 1971 trial-use standard. The 1974 standard was endorsed by the NRC in Regulatory Culde 1.89. "Environmental Qualification of Certain j Electric Equipment Important to Safety for Nuclear Power Plants", for newer plants, ie, existing construction permit appilcants. However, no ) Regulatory Guide was ever issued adopting the 1971 IEEE 323 standard. lO i j l 3 2-1 Amendment 5 j (August 1988)
Design of the Trojan Nuclear Plant was initiated well beforo the issuance of IEEE 323-1971. Nevertholoss, PGE mado a commitment to the Westinghouso qualification prugram, which used IEEE 323-1971 as a design standard for many important Nuclear Steam Supply System compo-nonts, especially those inside the Containment Building whero the most sovere post-accident environmental conditions woro postulated. Applicable provisions of IEEE 323-1971 woro also factored into the design of balance-of-Plant equipment outside Containment where appro-priato. In 1978, the NRC iscued IE Circular 18-08 requesting licenscos to examine installed safety-related electrical equipment and ensure appropriate documentation of its qualification to function under accident conditions. The following year, IE Bulletin 19-01 was issued requiring licensecs to provide written evidenne of electri-cal equipment qualification. Although these documa c. requested qualificatien reviews and information, neither provided specific guidelines for conducting detailed qualification reviews. Subsequently, in late 1979 the NRC staff developed definitivo critoria for reviewing the environmental qualification of safety-related elec-trical equipment. The Division of Operating Reactors 'Ouidelines for Evaluating Environmental Quall scation of Class IE Electrical Equipment in Operating Reactors" (DOR Cuidelines) were developed specifically for operating reactors- In addition, for reactors under licensing review, the NRC issued NUREG-0588, "Interim Staff Position on Environmental Qualification of Safety-Related Electrical Equipment". The intent of the DOR Culdelinos is not to provide guidelines for implementing either version of IEEE 323 for operating reactors. T1.s intent as rather to provide a basis for judgments required to con-firm that operating reactors are in compliance with General Design , i Criterion 4. The intent of SUREC-0588 is to implement IEEE 323 for plants under licensing revivw. It provides a number of NRC staff positions on selected areas of the qualification larue. These positions are dividoJ into two categories: l l I Amendment 4 I (August 1987) 2-2 l I
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- (1) Category I positions apply to equipment qualifled in accordance with IEEE 323-1974.
(2) Category II positions apply to equitment qualifled in accordance with IEEE 323-1971. f After the NRC staff completed their inillal review of licensecs' responses to IE Bulletin 79-01, IE Bulletin 79-01B was issued in l January 1980 requiring additional qus11fication information in a ' specified format for electrical equipment evaluated against the DOR l Culdelines. NUREG-0588 was also referenced as a source of supple. mental infornation to be used with the DOR Culdelines, j I On May 23, 1980 the NRC Commissionera issued a Memorandum and Order I (CLI-80-21). In this order, the Commission endorsed the NRC staff's f use of the DOR Cuidelines to review operating plants and NUREG-0588 3 to review plants under licensing review as well as those pieces of { i equipment in cperating plants which do not meet the DOR Guidelines, j The Commission directed the staff to complete its review of environ-mental qualification, including publication of Safety Evaluation Reports (SER), by February 1,1981, and ordered that all safety- [ related elect:ical equipment in all operating plants be qualified [ to the DOR Culdelines or NUREG-0588 by no later than June 30, 1982, f j 2 j In order to implement the provisions of the Commission's Memorandum l J and Order, the NRC issued 'two separate Orders to licensees. An Order l 1 I 4 in August 1980, subsequently as. ended in September, required submittal j e t' a complete response to It Bulletin 19-018 by November 1, 1980. ) An Order in October 1980 amended the operating license of Trojan and j ) other operating plants to require: (a) qualifical;1on of all safety-j related equipment by June 30, 1982 in accordance with the DOR Cuide- .) lines or NUREG-0588, and (b) establishment of a central documentation j file for environmental qualification by November 1,1980. These l f requirements are documented in Trojan Technical Specification 6.13, l
"Environmental Qualification,*, C ;
3 i ! i 2-3 Amendment 5 l' ! (August 1988) i
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i 1 i l On June 25, 1982 the Commission promulgated an interim rulo as i 10 CFR 50.49, "Environmental Qualification of Electrical Equipment Important to Safety for Nuclear Power Plants". This rule suspended the June 30, 1982 deadline for completion of environmental qualification of safety-related electrical equipment pending publication of a final rule on qualification of such equipment. On January 21, 1983 the Commission promulgated a final rule on environmental qualification of electric equipment important to safety. This rule superseded the June 25, 1982 interim rule and was intended to codify the methods and criteria that meet NRC requirements in the area of environmental qualification. hi In June 1984, the NRC issued Revision 1 to Regulatory Guide 1.89. Revision 1 to Regulatory Guide 1.89 describes a method acceptable to the 1?C staff for complying with 10 CFR 50.49. The Regulatory Guide generally endorses IEEE 323-1974, subject to certain clarifications and conditiora. 2.2 REGULATORY BASIS FOR ENVIRONMENTAL QUAT,IFICATION RCVIEW The review described in this report was originally conducted in accor-dance with the DOR Culdelines. NUREC 0588 was used as suppicmental guidance. This approach was consistent with the Commission's Memorandum and Order (CLI-80-21) as implemented by Trojan Technical Specification 6.13. This report has since been amended to address the requirements of 10 CFR 50.49, the guidelines of Regulatory Guide - 1.89 (Revision 1), and Generic Letter 88-07, "Modified Enforcement Policy Relating to 10 CFR 50.49 Environraental Qualification of Electrical Equipment Important to Safety for Nuclear Powoc Plants". The DOR Cuidelines, NUREC 0588, 10 CFR 50.49, and Regulatory Guide 1.89 (Revision 1) have been implemented in accordance with the following: Amendment 5 2-4 (August 1988)
(1) Equipment ordered prior to February 22, 1983 (the offectivo date of 10 CFR 50.49) is qualified in V accordance with the DOR Guidelines or NUREG- 0588 (Category I). (2) Equipment ordered af ter February 22, 1983, but before m June 1, 1984 (the effective issue dato of Revision 1 to U Regulatory Guido 1.89), is qualified in accordance with NUREG-0583 (Category I), unless the provisions of Item 4 below are applicable. Qualification in accordance with NUREG 0588 (Category I) is construed to be equivalent to meeting the provisions of 10 CFn 50.49, i (3) Equipment ordered after Juno 1, 3984 will be qualified ] in accordance with 10 CFR 50.49, unless the provisions , of Item 4 below are applicable. The provisions of Revision 1 to Regulatory Guido 1.89 will be complied with in the qualification review of this equipment, 3 except as noted in this topical report. (4) Replacement equipment ordered af ter February 22, 1983 must be qualified in accordance with the provisions of Items 2 and 3 above, unless there are sound reasons to
- the contrary. The following are considered to be sound reasons for the use of replacement equipment previously qualified in accordance with the DOR Guidelines or -
N NUREG-0588 in lieu of upgrading: (a) The item of equipment to be replaced is a component of equipment that is routinely replaced as part of normal equipment maintenance, es, gaskets 0-rings, and coilst i these may be replaced with identical componeni.e. (b) The item to be replaced is a component that is part of an item of equipment qualified as an assembly; these (9 G may be replaced with identical components. 2-5 Amend =ent 5 (August 1988)
(c) Replacement equipment qualified in accordance with the provisions of 10 CFR 50.49 does not exist. (d) Replacement equipment qualified in accordance witn the provisions of 10 CFR 50.49 is not availabic to meet installation and operation schedules. However, in such case, the replacement equipment may be used only until upgraded equipment can be obtained and an outage of sufficient duration is availabic for ecplacement. (e) Replacement equipment qualified in accordance with 10 CFR 50.49 would require significant plant modifications to accommodate its use. (f) The use of replacement equipment qualified in accordance with 10 CFR 50.49 has a significant _ probability of creating human factor problems that U would negatively affect plant safety and performance, for example:
- 1) Knowledge, skills, and ability of existing plant staf f would require significant upgrading to operate or maintain the specific replacement equipment;
- 2) The use of the replacement equipment would create a one-of-a-kind application; or
- 3) Maintenance, surveillance, or calibration activities would be unnecessarily complex.
For replacement equipment qualified in accordance with Paragraphs (c) through (f) of this item, a nonconformance report shall be processed as described in Section 5.1.2.3. AmendLent 5 2-6 (August 1988)
. .-_ =---- - -. =. .. . . . . _
i i l 4 The provisions of Generic Letter 88-07 are also followed in the environmental qualification program. If a potential deficiency is g identified in the environmental qualification of a component, Generic < Letter 88-07 provides the following guidelines on appropriate actions to be taken: i (1) A prompt determination of operability shall be made for the 4 affected equipment. t t (2) Imediate steps shall be taken to establish a plan, with a ; l reasonable schedule, to correct th'e deficiency. t i (3) A justification for continued operation (JCO) shall be 1 written and kept on flie. This justification does not { require NRC review and approval. I ! A finding of operability ray be made using analysis and partial , I test data to provide reasonable assurance that the equipment will , perform its intended safety function, or that failure of the 3 t equipment will not result in significant degradation of any j i safety function or provide misleading information to the operator. { i I 4 If operability cannot be demonstrated, and the equipment is covered by [ plant Technical Specifications, the appropriate action statements will f f be followed. If the aquipment is not covered by the Technical Speci- l I fications, the reactor can continue to operate if the safety function I l can be accomplished by other designated equipment that is qualified, { or limited administrative controls can be used to ensure the safety l
) l 1
function is performed. l t If a deficiency in the environmental quali.! cation of equipment is l discovered, reportability under 10 CFR 50.72, 10 CFR 50.73, 10 CFR 21 Technical Specifleations, or any other pertinent requirement must be determined. This is especially true if the equipment *.s determined to be inoperable. l O ! 2-7 Amendment 5 (August 1988) l l
. ~ . - . _ . - ~ _ . _ = _ - - - _ . _ . _ _ - - . - . - . . . .
i i ! program to the extent described in Topical Report PGE-1043 '. Ih i IG i i O The approach used to review the environmental qualification of equip--
- l ment important to safety in harsh environments is described in Sec- ,
tion 5.1. [ , i I ; l 3.3 PROCEDURE FOR IlWMTIFYING EQUIPMENT
- TMPORTANT TO SAFETY IN MILD ENVIRONMENTS j 1 I Environmental. qualification of electric equipment important to safety f j located in a mild environment is not included within the scope of 10 CFR 50.49. According to 10 CFR 50.49, a mild environment is an i environment that would at no time be signifleantly more severe than the [
environment that would occur during normal plant cperation, including ' j anticipated operational occurrences. The criteria used to distinguish f i mild from harsh environment areas is delineated in Chapter 4. l The identification of equipment important to safety in slid environ-
~
- ments was conducted in conjunction with the identification of equipment in harsh environments. This process is described in the preceding j section. The CSS docu.ments all equipment important to safety in mild l d i environments by component identification number Plant location, func- j tional and environmental requirements, and equipment data.
j I t The approach used to review the environmental qualification of j j equipment important to safety in mild environments is described in ; i i Section 5.2. { l j $ I l j s I } 3-7 Amendment 5 (August 1988) i
,-- -._ __.._ -. _ - . _ _ - - _ _ . ____.._-.___..___m -
_ _~. . ,_ _ -
3.4 PROCEDURE FOR IDENTIFYING OTHER EQUIPMENT SUBJECT TO ENVIRONMRNTAI, QUALIFICATION REVIEW Regulatory Guide 1.97 specifies that Category 3 instrumentation "should O be of high-quality commercial grade and should be selected to withstand the specified service environment". Generally, the specified service environment is the normal environment; however, for several Category 3 post-accident instruments at Trojan, it is appropriate to specify the service environment as the post-accident environment. It was also considered appropriate to recategorize several post-accident instruments from Category 2 to Category 3 on the basis of previous requirements specified by NUREG-0737. The instrumentation in question concerns the post-accident sampling system (NUREG-0737. Item II.B.3), the noble gas affluent monitors (II.F.1.1), and the iodine and particulate sampling capability (II.F.1.2). NUREG-0737 specifies environmental qualification require-ments for the noble gas offluent monitors. This requirement appears in Table II.F.1-1 and states that "the instruments shall provide suf fi-ciently accurate responses to perform the intended function in the environment to which they will be exposed during accidents". NUREG- 0 73 7 does not specify any environmental qualification requirements for the post-accident sampling system or Lodine / particulate sampling capability. Subsequent to YUREG-0737, 10 CFR 50.49 was promulgated and requires environmental qualification of "certain post-accident monitoring equip-ment" specified as Category 1 and 2 in Regulatory Guide 1.97. The noble gas effluent monitors are listed in Regulatory Guide 1.97 as Cate-gory 2. The post-accident sampling system and iodine / particulate sampl-ing capability are listed in Regulatory Guide 1.97 as Category 3. The various environmental qualification requirements for the aforemen-tiened equipment are sutmarized in Table 3-4. With respect to the noble gas effluent monitors, PGE has adopted the position that Regulatory O Amendment 2 3-8 (June 1985)
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- BLDG./RM/ELV OERVICE HLRSER CTS 045 TERMINAL SOARD BUCHANAN NQB104 M 447 104 SIM LIFE D ISL SYP VLV CV2280 17.4.2 CT3 047 TERMINAL BOARD SUCHANAN 9538104 M 449 104 STM LIFE S ISL SYP VLV CVZ278 17.4.2 CT3 075 TERMINAL aOARD SUCHAfe4AN NQB112 E 358 % ACCLRt SAMPLE ISOL VLY.CV5652 17.4.2 CT3 076 TERMINAL 90ARD BUCHAfe4AN HQB112 E 358 54 RCS HOT LEG 21P I*,OL VLV.CV5655 17.4.2 CTS 077 TEletINAL 80 ARC SUCMAfetAN 98J8112 E 358 54 PZR LIQ SPCE 31P ISOL VLV.CV565 17.4.2 CT3 0 78 YERMINAL BOARD BUCHA794AN NQB110 E 158 % PZR VAP SPACE ISOL VLV.CV5659 17.4.2 CTS 079 TERMINAL 90ARD BUCMAD94AN HQB112 E 358 54 RCDT Q1P TO AUTO GAS ANAL.CY566 17.4.2 CT3 104 TERMINAL 80ARD GE NO NAMEPLATE C 77 105 IIS S CONT FOR PfVC 1428 MILO CTS 110 TERPflNAL BOARD SUCHANAN C 45 77 QRM TO C20 MILD CTS 203 OPLICE POINT RAYCHEM HCOF-N C ISOA 60 TE421A-HOT LEC RCS 9.4.2 CT3 204 OPLICE POINT RAYCHEM MCOF-N C 1804 62 TE4218-COLD LEG RCS 9.4.2 CTS 205 LPLICE POINT RAYCH[M HCSF-N C IBSA 62 TE4204-MOT LEC RCS 9.4.2 CTB 206 SPLICE POINT RAYCHEM HCSF-N C 180A 62 TE4208-COLD LEC RCS 9.4.2 CT3 207 SPLICE POINT RAYCH[M MCST-N C ISOA 62 TE413A-HOT LEG RCS 9.4.2 CTS 208 OPLICE POINT RAYCHEM MCSF-N C 180A 62 TE425A-MOT LEG RCS 9.4.2 CTS 209 OPLICE POINT RAYCHEM MCOF-N C IBOF 45 TE4338-COLD LEG RCS 9.4.2 CIS 210 SPLICE POINT RAYCHEM MCSF-N C 180A 60 TE4438-COLD LEC RCS 9.4.2 CTB 218 OPLICE POINT RAYCMEM HCSF-N C 0808 84 TE415A-HOT LEG RCS 9.4.2 CTB 219 LPLICE POINT RAYCHEM MCSF-N C 0B08 77 TE421A SCS HOT LEG 9.4.2 e BUILDING CODES A= AUXILIARY CaCONTAlfGENT E= ELECTRICAL FsFUEL M4tAIN STEAM PrPIPE TsTUpBItE CWtERIC COMPONENTS UMD SUILDING PE9ETRATION SUILDING SUPPORT PL*ETRATION SUILDING IN MAft( LOCATIONS STRUCTURE Sh C ed 93 :3 C CL f4 f1
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u v V I C7/26/83 $HEET 9 OF 65 l TABLE 3-2 l ELECTRICAL EQUIPMENT EPUIROP9 ENTAL QUALIFICATION 10 CFR 50.49 MASTER LIST l l LOCATION EQG i PLANT ID 8 COP 90pKNT MApeXACTURER MODEL
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l C % C5 CONTROL PANEL C 55 91 PRCS IND & CONT PROT "J T III MILD j C % C5 CONTROL PML C 53 95 PRCS IPe & CONT GRP III MILD 1 l C % C6 CONTROL PAsEL C 51 95 PRCS Ipe & CONT RACK MILD C % DI CONTROL PAsEL C 53 91 PRCS IEC PROT SET IV RACK 14 MILD C 56 D2 CONTROL PAREL C 55 93 PRCS IND S CONT PROT "JT 4 MILD C 54 05 CONTROL PANEL C 53 95 PRCS ISC PROT "A T III RACK 16 MILD C 56 D4 CONTROL PAPEL C 53 91 PRCS Isc CONT CRP IV RACK 28 MILD C % 05 CtMTROL PANEL C 53 91 PRCS Ipe & CONT GRP IV P'ILD C h D6 CONTROL PANEL C 53 95 PRCS ISC CRP IV VCT LYL IND MILD C M A CONTROL PAtEL C 55 95 PROT STS TEST CA8 MILD C 40 S CONTROL PAPEL C 55 95 PROT SYS TEST CAB MILD C 42 CONTROL PMEL C 53 95 "AI:;MIC PRC MILD C 44 8 CONTROL PANEL C 53 93 ALM SAFECUARDS CAB MILD C 45 A CONTROL PANEL C 51 91 ALM SATECUARDS MILD C 44 A CtMTROL PANEL C% 91 $$PS A IP@UT RACK MILD C 44 S CONTROL PANE L C% 93 SSPS A IPFUT RACK HILO C 46 C CONTROL PAMEL C% 91 +4.PS A IPFUT RACK MILD C 46 9 CONTROL PAK L C% 93 "J.PS A INPUT RACK MILO C 4F A CONTROL PANEL C M 95 SSPS S IPPUT RACK MILD 1 l l
- BUILDING CODE : A*AUXILIANT C=CONTAIseENT E=EtfCTRICAL FerUEL n= MAIN STE AM P= PIPE YsTURBIE G=CEpKRIC COMPONENTS USED i
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' RVICE EQS BAASER C 47 8 CadTROL PMKL C% 93 $$PS S TIFJT RACK MILD C 47 C CONTROL PAPEL C% 95 5".?S S It#5UT RACK MILD C 4F D COPHROL PAPEL C% 93 SOPS S ItsWT SACK HILD C 48 A CONTROL PAtKL C 54 95 $$PS TRAIN A LOGIC MILD C 48 8 COtHROL PAsEL C% 93 OOPS TRAIN 8 LOGIC MILD C 49 A CONTROL PAtKL C 53 93 SOPS #1ILD C 49 8 CONTROL PAtKL C 53 93 SOPS MILD C 60 A CONTROL PMKL C 53 93 RYLIS MILD C 60 $ CORROL PAtKL C 53 *3 RYLIS MILD C % A CONTROL PAPEL C 53 95 ISLN I/O TO TSC CPU MILD C M S CONTROL PAtKL C 53 93 ISLN I/O TO TOC CPU MILD C 101 CONTROL PAtKL T 85 45 00L CEN 81 EXCITER MILD C 102 CONTROL PAPEL T $6 45 DSL GEN 8 2 EXCITER MILD C 121 COPHROL PAfEL C 38 65 REAC TRIP "jct.tte BRKR MILD C 122 CONTROL PAtKL C 38 65 REAC TRIP $NGR. SACK-UP BRKR MILD C 160 A CO** TROL PA>KL T C160 45 Af N Cart & Aux "JfTore Ptt
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$S n a ELECTRICAL EQUIPMENT EtNIROtt1 ENTAL QUALIFICATIOra
- s g" 10 CFR 50.49 ftASTER LIST cn sm O PLANT ID 8 LOCATION EQS COff0fENT mat 3JFACTURER NODEL *BLOG./RM/ELY SERVICE NUMBER
-CTS 204 SPLICE POINT RAYCHEM HCSF-N C IBSA 60 TE43IB COLD tEG 9.4.2 CTS 205 SPLICE POINT RAYCHEM HCSF-M C IBSA 60 TE430A HOT LEG 9.4.2 CTS 206 SPLICE POINT RAYCHEM HCSF-N C IBSA 60 TE4300 CCLD LCG 9.4.2 CTB 210 SPLICE POINT RAYCHEM HC!i-N C 0B08 60 LT 461 PT 457 9.4.2 CTB 228 SPLICE POINT RAYCH99 HCSF-N C OBSi 50 PT964 9.4.12 CT3 401 TERftINAL BOARD N/A A 137 5 FT971A A S EXEMPT CV 3004 Al NOTOR OPERATED VALVE LIMITORQUE SMS-000 M 438 59 STM GEN E201A FROH TD AFH PHP 64.4.2 CV 3004 A2 NOTOR OPERATID VALVE LIMITORQUE stb-000 M 438 59 STM CEN 2201A FROM DD AFH PMP 64.4.2 CV L004 B1 ti1 TOR OPERATED VALVE LIMITORQUE SMB-000 N 441 59 STM GEN E2018 7 ROM TD AFM PHP " 4.2 CV 3004 B2 HOTOR OPERATED VALVE LIMITORQUE St1B-000 M 441 59 STM GEN E2018 FROM DD AFH PHP 64.4.2 CV 3004 C1 MOTOR OPERATED YALYZ LIMITJRQUE Ste-000 M 440 59 STM GEN E201C FROM TD AFH PMP 64.4.2 CV 3004 C2 NOTOR OPERATED VALVE LIMITORQUE SMB-000 M 440 59 STM GEN E201C FRON 00 AFH Pt1P 64.4.2 CV 3004 D1 t10TOtt OPERATED VALVE LIMITORQUE Ste-000 M 439 59 STM GEM E201D FROM TD AFH Pt1P 64.4.2 CV 3004 02 NOTOR OPERATED VALVE LIMITORQUE StO-000 M 439 59 STM GEN E2010 FROM 00 AFH PHP 64.4.2 CZ 06 PEFETRATION AMPitENOL 50003326-07 C 0808 54 CHAN C ItGTRM 8.4.2 CZ 07 PEPETRATION AMPHENOL 50003326-08 C OBSB 54 CHAN C ItGTRM 8.4.2/3.4.2 0 9 DISTRIBUTION PAPEL C 38 61 125 V EMER LIGHTItG HILD 0 10 DISTRIBUTION BUS EDC) GENERAL ELECTRIC C 38 65 125V DC CONT CTR BUS MILD D 10 X 125 VDC PArEL C 38 65 DC PNL FOR DIO FOR B2KR MILD o BUILDItG CODE: A= AUXILIARY C=CONTAltafMT E= ELECTRICAL F =FtK L H: MAIN STEAM P= PIPE T=TWtBIPE G=rEFERIC COMPOtENTS USED BUILDIfG PEFETRATION BUILDIfG SUPPORT PEtETRATIG4 BUILDItG IN F1ANY LOCATIOtG STRUCIURE m
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C7/26/88 SHEET 17 0F 65 TA8LE 3-2 ELECTRICAL EQUIPtENT Ef;/IR0peENTAL QUALIFICATION 10 CFR 50.49 ftASTER LIST LOCATION EOS - PLANT IS S CENetNENT MafGJFACTURER MODEL *SLDC./IIM/E LY SEttVICE #dmSER 9 105 ass DC Af9ETER C 38 61 STRY el CUR LOAS MILD D 11 125 VOC BATTERY C & 8 SATTERIES C 39 65 SUS DIO, D30 STRY MILD 8 12 125 VOC SATTERY C & D SATTERIES C 40 65 9US D20, D40 STRY MILD 0 20 sISTRIeUTION BUS IBC) GE9ERAL ELECTRIC C 38 65 125V CONT CTR SUS MILD D 29 X 125 VOC ftNEL C 38 65 PC HL FOR DIO FDR BAKR MILD 0 2eSees DC AfGETER C 38 61 STRY SZ CUR LOAD MILD D 21 SATTERY CNARGER Post CONVERSION PROD. C 38 65 125V STRY CMGst MILD D 22 SATTERy r-R Pee CindVERSION PROD. C 38 65 125V STRY CMGR MILD D 23 SATTElty rmR pee CONVERSION PROD. C 38 65 125V STRY CHGR HILD 0 24 SATTERy r m a Post CONVERSION PROD. C 38 65 125V STRY CMGR MILD D 30 SISTRISUTION SUS (DCl GENERAL ELECTRIC C 38 65 125V LONT CTR SUS MILD D 30 X 125 VOC PA0EL C 38 65 DC Pla. FOR D30 FOR S E R MILD 0 4e sISTRIaUTION SUS ISC) GENERAL ELECTRIC C 38 65 125V CONT CTR SUS MILD D MB X 125 VOC PAsEL C 38. 65 DC PteL FOR D 40 Fest BAKR MILD 0 62 LIGI8 TING PAIEL C 38 61 CONTROL SLDC MILD D 63 LIGetTING PatCL F 281 43 FUEL SLDG SEE E DM lotsarat SafrER MOTOR C 53 93 OUTSIDE AIR OpWR ,CS-2 MILD SPE 10250C33 BAfrER MOTolt C 53 93 Ft2E 88000 E)st FAN CONT CS-3 MILD Brg 19254C96 SafrER MOTOR C 53 93 TOILET Del FAN CONT CS-4 MILD
- SUILSIse3 CODE A=AUKILIARY C=CaedTAlseEsfT E= ELECTRICAL F= FUEL M: MAIN STEAft P= PIPE . T=TURSIIE C=GEDERIC CtWr0 DENTS USED BUILDING PEBETRATION SUILDING SUPPORT PE9ETRATItzt suIeJING IN MANY LOCATIONS STRUCTURE
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- BLDG./RM/ELY SERVICE BAR1BER DM 10251 A DAPPER P10 TOR C 53 95 OUTSIDE AIR DNPR. CB-1 MILD DM 10251 8 DAMPER tt0 TOR C 53 93 OUTSIDE AIR DNPR, CS-1 MILD DM 10501 DAMPER MOTOR C 53 93 RECIRC AIR DNPR CS-2 ftILD DM 10502 DAMPER MOTOR C 53 95 RECIRC AIR DNPR CB-2 MILD DH 30501 DAffER POTOR C 53 93 D01 AIR DNPR C8-12 MILO Ot 10504 DArfER tt0' w C 53 93 SPLY AIR OtPR CB-2 ftILD CT3 203 SPLICE POIN. RAYCHEtt HCSF-N C IBSA 60 TE441A HOT LEG 9.4.2 CT3 204 SPLICE POINT RAYCHEM HCSF-N C IBSA 60 TE4418 COLD LEG 9.4.2 CTS 205 SPLICE PO NT RAYCHEM HCSF-H C IBSA 60 TE440A HOT LEG 9.4.2 CT3 206 SPLICE POINT RAYCHEM HCSF-H C IBSA 60 TE4408 COLD LEG 9.4.2 CTS 210 SPLICE POINT RAYCHEM HCSF-6 C 0008 72 PT 458 9.4.2 CT3 228 SPLICE POINT RAYCHEM HCSF-N C OBSF 50 PT967 9.4.12 CTS 401 TERttINAL BOARD N/A A 137 5 FT970 A A 8 EXEMPT DZ 06 PEPETRATIG4 AMPHENOL 50003326-07 C 0B08 54 CHAN O IfGTRM 8.4.2 DZ 07 PEtETRATION AMPHENOL 50003326-09 C 0B08 54 CHAN D ItGTkd 8.4.2/3.4.2 FIS 610 FLOH IPOICATION SMITCH BARTON 288A A 137 5 P202A EXEt9T FIS 611 FLOH IrmICATIG4 SMITCH CART 0t4 288A A 237 5 P2028 EXEMPT FIS 3004 Al FLOM INDICATION SMITCH 8ARTG4 580A-0 ft 438 59 AFM TO STM CEN A FROM P102A 60.4.2 FIS 3004 A2 FLOH INDICATIG4 $ HITCH BARTON 580A-0 ft 438 59 AFH TO STM CEN A FR0tt P1028 60.4.2 o BUILDING CODE A=ALIKILIARY CzCORAltt1ENT E* ELECTRICAL Fs FL:EL H=ttAIN STEAtt P PIPE T=TUR8ItE C=CEFERIC COttP0 TENTS LEED BUILDItG PERETRATION BUILDIPC SUPPORT PEtETRATION BUILDItG IN mat # LOCATI0tG STRUCTURE o
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l i V C7/26/88 SHEET 19 0F 65 TA8LE 3-2 ELECTRICAL EQUIPMENT ENVIR00eENTAL QUALIFICATION 10 CFR 50.49 MASTER LIST LOCATION EQS PLANT 10 8 Cof90E NT MMAJFACTURER MODEL e8LDC./RM/ELY SERVICE NLABER
- FIS 3004 81 FLOM IDSICATION SMITCH BARTON 580A-0 M 441 59 AFM TO STM GEN 8 FROM P102A 60.4.2 FIS 3004 82 FLOM INDICATION SMITCH BARTON 5804-0 M 441 59 AFM TO STM GEN 8 FROM P1028 60.4.2 FIS 3004 C1 FLOM IpeICATION SMITCM SARTON 580A4 M 440 59 AFM TO STM CEN C FROM P102A 60.4.2 FIS 3004 C2 FLOM INDICATION SMITCH SARTON 580A-0 M 440 59 AFM TO STM GEN C FROM P1028 60.4.2 FIS 3004 01 FLOM INDICATION SMITCH BARTON 580A-0 M 439 59 AFN TO STM GEN D FROM P102A 60.4.2 FIS 3004 02 FLOM INDICATION SNITCH BARTON 580A-0 M 439 59 AFM TO STM GEN D FROM P1028 60.4.2 FIT 917 FLOM IISICATING TRAN2 TITTER SARTON 384 A 158 25 CCM PPP DISCH EXEMPT FT 414 FLOM TRAN2 TITTER FOMBORO E13DH C OBSF 45 RCS L1 COLD LEG EXEt1PT FT 415 FLOM TRAN2 TITTER FOMBORO E13DH C OSSF 45 RCS L1 COLD LEG EXEttPT FT 416 FLOM TRAN2 TITTER FOXBORO E130H C OBSF 45 RCS L1 COLD LEG EXEt1PT FT 424 FLOM TRAN2 TITTER FoxBORO E13DH C OBSF 45 RCS L2 COLD LEC EXEMPT FT 425 FLOM TRAN2 TITTER FOMBORO E130H C OBSF 45 RCS L2 COLD LEG EXEMPT FT 426 FLOM TRAM 2 TITTER FOXBORO E13DH C OBSF 45 RCS L2 COLD LEG EXEMPT FT 4% FLOM TRAN2 TITTER FoxBORO E13DN C OBSF 45 RCS L3 COLD LEG EXEMPT FT 415 FLOM TRAM 2 TITTER F00SORO E13DH C OBSF 45 RCS L3 COLD LEG EXEteT FT 436 FLOM TRAN2 TITTER FOXBORO E13DH C OBSF 45 RCS L3 COLD LEG EXEteT FT 444 FLOM TRAN2 TITTER FOMBORO E13DH C OBSF 45 RCS L4 COLD LEC EX*T T FT 445 FLOM TRAfCtITTER FoxBORO 2130H C OBSF 45 RCS L4 COLD LEG EXEMPT FT 446 FLOM TRAN9 TITTER FOMBORO E13DH C OBSF 45 RCS L4 COLD LEG EXEMPT
# SUILDING CODES A=AUKILIARY C=CONTAIIeENT E= ELECTRICAL F= FUEL MzMAIN STEAh P= PIPE T=TURBIPE G:CEPERIC COPPONENTS USED BUILDING PENETRATION BUILDING SUPPORT PE9ETRATION BUILDING IN MANY LOCATIONS STRUCTURE E
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- PLM4T ID 8 COMPGENT HAPAJFACTURER HDDEL *BLDA./RH/ELV SERVICE tAJt1BER FT 510 FLG4 TRANSMITTER BARTG4 384 T 103 63 STM GEN LP 1 FDM/FS MISMATCH NILD FT 511 FLCH TRAPCHITTER BARTON 384 T 103 63 STM GEN LP 1 FoH/FS MISMATCH MILD I FT 512 FLON TRAtCMITTER BARTON 7M C OBSF 45 STM GEN LP 1 38.4.2 f FT 513 FLON TRArcitITTER BARTON 7M C OBSF 45 STM CEN LP 1 38.4.2 l FT 520 FLON TRAlcitITTER BARTON M4 T 103 68 STM GEN :* 2 FDH/FS ttISttATCH HILD FT 521 FLOH TRAFEMITTER SARTON 384 T 103 68 Sm CEN Le 2 FDH/FS HISitATCH PtILD FT 522 FLON TRAPCMITTER SARTON 7M C OB"F 45 STM CEN LP 2 38.4.2 l FT 523 FLCH TRAPCMITTER BARTON 7M C OBSF % STM GEN LP 2 38.4.2 FT 530 FLOM TRAPCMITTER BARTON 384 T 103 63 STM GEN LP 3 FDH/FS HISMATCH MILD FT 531 FLOH TRAftetITTER BARTON 384 T 103 63 STM GEN LP 3 FDH/PS HISMATCH NILD FT 532 FLON TRAPCitITTER BARTON 7M C OBSF 45 STM GEN LP 3 38.4.2 FT 513 FLOM TRAPCMITTER BARTON 7M C OBSF 45 STM GEN LP 3 38.4.2 FT 540 FLOH TRAtCHITTER BARTON 384 T 103 63 STM CEN LP 4 FDH/FS MISitATCH NILD FT 541 FLON TRArcitITTER BART0t4 384 T 103 63 STM CEN LP 4 FDH/TS MISitATCH HILD FT 542 FLCH TRAPCitITTER BARTON 7M C OBSF 45 STM CEN LP 4 38.4.2 FT 543 FLOH TRAtCMITTER SARTON 7M C OBSF 45 STM GEN LP 4 38.4.2 FT 600 F10H TRAtCMITTER BARTON 384 F 234 45 RHR HOT LEG Itt24 EXEMPT FT 918 FLG4 TRAlcitITTER BARTON 384 A 137 5 SI PHP A DISCH EXEMPT FT 922 FLOH TRArcitITTER BARTON 384 A 137 5 SI PHP S DISCH EXEttPT O SUILDItG CODE: A*ALMILIARY C=CG4 TAIT #1NT ErELECTRICAL F= FUEL HzHAIN STEAft P= PIPE T=TURBItE CzGEtERIC COMPONENTS USED BUILDING PEtETRATION BUILDING SUPPORT PEtETRATIG4 BUILDIfC IN MANY LOCATI0tG STRUCTURE o
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- BLDG./RM/ELY SERVICE NUteER i
FT 970 A FLOM TRANSMITFER SARTON 384 A 137 5 RHR TRAIN 8 CUT EXEMPT FT 970 8 FLOM TRANSMITTER BARTON 384 A 137 5 RHR TRAIN 8 OUT EXEMPT FT 9 71 A FLOM TRAfrAITTER BARTON 384 A 158 5 RHR TRAIN A OUT EXEW T FT 971 S FLOM TPANSMITTER SARTON 384 A 158 5 RHR TRAIN A OUT EXEMPT FT 2079 A FLOM
- IRAN 2 TITTER ROSEM0m T 1153HA6 A 141 30 SPRAY ADDITIVE PLM A DISCHARGE 39.4.2 FT 2079 8 FLIF TRANSMITTER ROSEMotMT 1153HA6 A 143 30 SPRAY ADDITIVE Ptw B DISCHARGE 39.4.2 FT 3043 A FL' A TRANSMITTER FOXBORO N-E13DM M 442 70 AFM FL TO STM GEN E201A 14.4.2 FT 1943 a ft0M TRANSMITTER FG>3ORO N-E130M M 445 70 AFM FL TO STM GEN E2018 14.4.2 1
FT 3043 C FLOM TRANSMITTER FOXBORO N-E13DM M 444 70 AFM FL TO STM GEN E201C 14.4.2 FT 3043 9 FLOM TRAfCHITTER FOXBORO N-E13Det M 443 70 AG4 FL TO STM GEN E2010 14.4.2 a l FT 3043 E FLOM TRAN2 TITTER ROSEMOUNT 1153HA6 M 4M 59 AFM FL TO STM GEN E201A 39.4.2 t
. FT 3043 F FLON TRANSMITTER ROSEMOLNT 1153HA= M 441 59 AFM FL TO STM GEN E2015 39.4.2 FT 3043 G FLOM TRANSMITTER ROSEMOLMT 1153HA6 M 440 59 ATM FL TO STM GEN E201C 39.4.2 FT 54M3 N FLOM TRANSMITTER ROSEMANT 1153HA6 M 439 59 AFM FL TO STM GEN E2010 39.4.2 FY M36 I/P CONVERTER FISHER TYPE 146 A 137 5 RHR HT EXCHR A OUT EXEtPT-
! FY 607 I/P CONVERTER FISIP7 TYPE 546 A 137 5 RHR HT EXCHR S OUT EXEMPT ) G 101 DIESEL GEMRATOR St NO NAM PLATE T 85 45 EMER Pest TO SUS Al MILD G 102 EXCITER T 85 45 DSL GEN 8 1 MILD 6 103 GROUpeING RESISTOR GE 275X630C177 Y 85 45 DSL GEN 8 1 NEUTRAL HILD a SUILDING CODE A=AUKILIARY C=CONTAIEENT E= ELECTRICAL F. FUEL MzMAIN STEAL. P= PIPE TaTURSINE G= GENERIC COFPONENTS USED
^1 SUILDING PENETRATION BUILDING SUPPORT PEE TRATION BUILDING IN MANY LOCATIONS STRUCTURE
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# D ELECTRICAL EQUIPMENT EtNIROtt1 ENTAL QUALIFICATIOtt y $ 10 CFR 50.49 MASTER LIST
'e on u OD LOCATIOtt EQS PLAT 4T 10 8 CG1PONENT MAPAAFACTURER MODEL *BLDC./ Ret /E LV SERVICE PAA1BER G 201 DIESEL GENERATOR 82 NO NAr*EPLATE 7 86 45 EMER POHER TO BUS A2 MILD G 202 EXCITER T 86 45 DSL CEN 8 2 MILD 0 203 CROtrCIPC RESISTOR GE 275X630C377 T 86 45 DSL GEta 82 NEUTRAL Mith LIS 896 LEVEL IPOICATING $ HITCH BARTON 581-4 E 358 56 RVLIS HYD ISLN OVERTRAVEL 57.4.2 LIS 897 LEVEL INDICATIPC SHITCH BARTON 581-4 E 358 56 RVILS HYO ISLN OVERTRAVEL 57.4.2 LIS 898 LEVEL INDICATING SHITCH BARTON 581-4 E 358 56 RVILS HYD ISLf4 OVERTRAVEL 57.4.2 LIS 916 LEVEL INDICATIPC SMITCH BARTON 581-4 E 358 45 RVILS HYD ISLf4 OVERTRAVEL 57.4.2 LIS 920 LEVEL INDICATItC SHITCH BARTON 581-4 E 358 45 RVLIS HYO ISLN OVERTRAVEL 57.4.2 LIS 921 LEVEL INDICATING SCTCH BARTON 581-4 E 358 45 RVLIS HYD ISLf4 OVERTRAVEL 57.4.2 LIS 3216 LEVEL INDICATIPC SHITCH BARTON 288A P 219 77 CCH SURGE TK T204A 33.4.2 LIS 3217 LEVEL INDICATItC SHITCH BARTON 288A P 219 77 CCH SURGE TK 2048 33.4.2 LS 3752 A LEVEL SHITCH BARTON 28CA F 234 45 ALDC BLDG HI LYL 33.4.2 LS 3752 8 LEVEL SMITCH BARTON 288A F 234 45 AUX BLDG HI LYL 33.4.2 LS 4905 A LEVEL SHITCH BARTQ4 288A T 85 45 EDG TK LVL T-111A 33.4.2 LS 4905 8 LEVEL SHITCH BARTON 288A T 86 45 EDC TK LYL T-1118 33.4.2 LS 4909 A LEVEL SMITCH BARTON 288A T 90 45 DSL DAY TK T-152 LYL 33.4.2 LS 4909 8 LEVEL SHITCH BARTON 288A T 90 45 DSL DAY TK T-152 LVL 33.4.2 LS 4911 A LEVEL $ HITCH SARTON 288A T 85 45 DAY TK T-111A BACK UP 33.4.2 LS 4911 8 LEVEL SMITCH AARTON 288A T 86 45 DAY TK T-1118 BACK UP 33.4.2 o SUILDItC CODE: A=AtNILIARY C=CD4TAltefNT E= ELECTRICAL F= FUEL M: MAIN STEAM PzPIPE T= TURBINE G= GENERIC COMPO4ENTS USED BUILDItG PENETRATION BUILDING SUPPORT PEFETRATIOtt SUILDItG IN MANY LOCATIOtG STRUCTURE o O O O O O
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C7/26/88 SHEET 23 OF 65 TABLE 3-2 ELECTRICAL EQUIPNENT EtWIRota1 ENTAL QUALIFICATION 10 CFR 50.49 MASTER LIST LOCATION EQS PLANT ID 5 COMP 0 TENT MAtAJFACTURER t10DE L
- BLDG./Rtt/ELY SERVICE PAJt1BER LS 5201 C LEVEL SHITCH ROCHESTER ET-1214 T 90 45 Ct4DS STOR TK LVL MILD LS 5265 LEVEL SNITCH ROCHESTER ET-1214 T 90 45 CNOS STOR TK LVL MILD LT 185 LEVEL TRAPCMITTER BARTON 345 F 254 41 VCT LVL EXEMPT LT 459 LEVEL TRAPGttITTER BARTON 7M C 0808 % PZR LVL 38.4.2 LT 460 LEVEL TRAPCitITTER SARTON 7M C 0B08 60 PZR LVL 38.4.2 LT 461 LEVEL TotANSMITTER BARTON 7M C OBS8 % PZR LYL 38.4.2 LT 501 LEVEL TRANSitITTER BARTON 7M C OBSF 48 STM CEN LP 1 LEVEL 38.4.2 LT 502 LEVEL TRArcitITTER BARTON 7M C OBSF 48 STM CEN LP 2 LEVEL 38.4.2 LT 503 LEVEL TRAtcttITTER BARTON 7M C OBSF 48 STM GEN LP 3 LEVEL 38.4.2 LT 504 LEVEL TRAFCMITTER BARTON 7M C OBSF 48 STM CEN LP 4 LEVEL 36.4.2 LT 517 LEVEL TRAPCitITTER BARTON 7M C OBSF 45 STM CEN LP 1 CHAN D 38.4.2 LT 518 LEVEL TRAPCMITTER BARTON 7M C OBSF 45 STM CEN LP 1 CHAf4 C 38.4.2 LT 519 LEVEL TRAPCitITTER BARTON 7M C OBSF 45 STM GEid LP 1 CHAF4 8 38.4.2 LT 527 LEVEL TRAFCitITTER BARTON 7M C OBSF 45 STM CEN LP 2 CHAN O 38.4.2 LT 528 LEVEL TRAttttITTER BARTON 7M C OBSF 45 STM GEN LP 2 CHAN C 38.4.2 LT 529 LEVEL TRAPCitITTER BARTON 7M C OBSF 45 STM CEN LP 2 CHAN A 38.4.2 LT 537 LEVEL TRAPCMITTER BARTON 7% C OBSF 45 STM CEN LP 3 CHAN D 38.4.2 LT 538 LEVEL TRAPCitITTER BARTON 7M C OBSF 45 STM CEN LP 3 CHAF4 C 38.4.2 LT 539 LEVEL TRAtcetITTER BARTON 7M C OBSF 45 STM GEN LP 3 CHAN A 38.4.2 l
e BUILDIPC CODE: A= AUXILIARY C=CQ4TAItafNT E= ELECTRICAL F= FUEL MzMAIN STE?.ft PzPIPE TzTUR8INE G=CENERIC COMPONENTS USED BUILDItC PENETRATION BUILDIPC TAJPPORT ! PENETRATION BUILDIFC IN MANY LOCATIONS ' STRUCTURE - a ;i.
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- BLDG./Rtt/E LY SERVICE Nut:BER LT 547 LEVEL TRAtCMITTER BARTON 7M C OBSF 45 STM GEN LP 4 CHAN D 38.4.2 LT 548 LEVEL TRAtcitITTER BARTQ4 7M C OBSF 45 STM CEN LP 4 CHAti C 38.4.2 LT 549 LEVEL TRAtCitITTER BARTON 764 C OBSF 45 STN GEN LP 4 CHAN 8 38.4.2 LT 893 LEVEL TRAlcitITTER BARTQ4/HESTINCHOUSE 752 A 209 77 RVLIS LYL MtTR HILD LT 894 LEVEL TRAPCatITTER BARTON 752 A 209 77 RYILS LYL XHTR HILD LT 895 LEVEL TRAtCitITTER BARTON 752 A 209 77 RVILS LYL X'tTR HILD LT 913 LEVEL TRArct1ITTER BARTON 752 A 203 61 RVLIS LVL M1TR MILD LT 914 LEVEL TRAFCi1ITTER BARTON 752 A 203 61 RVLIS LVL Xt1TR ttILD LT 915 LEVEL TRArcitITTER BARTON 752 A 203 61 RYLIS LYL MtTR MILD LT 1898 LEVEL TRAtcrtITTER C LRTrX4 386 O OUT 45 RHST LYL MILD LT 18'9 LEVEL TRAPCttITTER BARTON 386 O CUT 45 REFUEL HTR STOR TK LVL MILD LT 1900 LEVEL TRA!CttITTER BARTON 386 0 OUT 45 REFUEL HTR STOR TK LYL MILD LT 1901 LEVEL TRAtCttITTER t5ARTON 386 0 OUT 45 REFUEL HTR STOR TK LYL HILD LT 2069 A LEVEL TRAttitITTER FISHER / PORTER 13D2493 A 143 25 SODIt21 HYDROXIDE TK LVL EXEMPT LT 2069 8 LEVEL TRAttt1ITTER FISHER / PORTER 13D2493 A 143 25 SODIutt HYDROXIDE TK LVL EXEttPT LT 4208 Al LEVEL TRAPCitITTER BARTO8 7M C 0858 58 HTR LVL NARROH RFC 38.4.2 LT 4208 A2 LEVEL TRAPCMITTER BARTON/HESTI!CHOUSE 764tLOT4) C OBSB 58 HTR LYL HIDE RFC 53.4.2 LT 4208 81 LEVEL TRAtCHITTER BARTON/HESTIPCHOUSE 764tLOT4B C 0B08 58 HTR LYL 74ARROH Ric 53.4.2 LT 4208 82 LEVEL TRAPCt1I1TER BARTON 7M C 0B08 58 HTR LYL HIDE RPG 38.4.2 o BUILDItG CODE: A= AUXILIARY C=CONTAIt#1ENT E= ELECTRICAL F= FUEL H:NAIN STEAtt P= PIPE T= TURBINE G= GENERIC COMPONENTS USED BUILDItG PENETRATION BUILDItc SUPPORT PENETRATION BUILDItG IN 81ANY LOCATIONS STRUCTURE W
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- BLDG./RM/ELY SERVICE NUtBER l LT 4900 A LEVEL TRANSMITTER FISHER / GOVERNOR CO. 2340-5498P O OUT 45 DSL OIL STOR T-119A MILD LT 4900 8 LEVEL TRANSMITTER FISHER / GOVERNOR CO. 2340-34%P O CUT 45 DSL OIL STOR T-1198 MILD l LT 5201 LEVEL TRANSMITTER ITT BAATON 7M 0 OUT 45 CteS STOR TK LYL/AFw TRIP 38.4.2 LT 5265 LEVEL TRANSMITTER ITT SAETON 7M 0 OUT 45 CteS STOR TK LVL/AFM TRIP 38.4.2
; MF 101 A MOTOR E STINGHOUSE $80P O OUT 45 SH SYS STR 43.4.2
) MF 101 5 MOTOR NESTINGHOUSE 580P O OUT 45 SH SYS STR MILD MFCY 610 MOTOR OPERATED VALVE LIMITORQUE 578-00 A 127 5 RHR RECIRC EXEMPT MFCV 611 MOTOR OPERATED VALVE LIMITORQUE Ste-00 A 122 5 RHR RECIRC. EXEMPT MO 112 S MOTOR OPERATED VALVE LIMITORQUE StS-00 P 167 45 VCT DISCH EXEMPT MD 112 C MOTOR OPERATED VALVE LIMITORQUE Ste-00 P 167 45 VCT DISCH EXEMPT MD 112 9 MOTOR OPERATED VALVE LIMITORQUE Ste-O A 153 25 CCP SPLY FROM RMST EXEMPT MD 112 E MOTOR OPERATED VALVE LIMITORQUE Ste-O A 153 25 CCP SPLY FROM RNST EXEMPT MD 2050 A MOTOR OPERATED VALVE LIMITORQUE Ste-00 A 3?* 5 REFUELING HTR TO CNT SPRY SY EXEMPT I MD 2050 3 MOTOR OPERATED VALVE LIMITORQUE Ste-00 A 130 5 REFUELING MTR TO CNT SPRY SY EXEMPT MD 2052 A MOTOR OPERATED VALVE LIMITORQUE Ste-2 P 170 45 CNT SPRAY PtW8 A SUCT EXEt1PT MD 2052 8 MOTOR OPERATED YALVE LIMITONQUE Ste-2 P 169 45 CNT SPRAY Pts' B SUCT EXEMPT MD 2053 A MOTOR OPERATED VALVE LIMITORQUE SPS-1 P 170 45 CNT SPRAY RING HDR 1 INLET EXEMPT MD 2053 S MOTOR OPERATED VALVE LIMITORQUE Ste-1 P 219 77 CNT SF11tAY RING HDR 2 INLET EXEFFT MD 2056 A MOTOR OPERATED VALVE LIttITORQUE Ste-000 A 143 25 -SPRAY ADOITIVE EDUC SUCT EXEMPT l e DUILDING CODE: AzAUKILIARY CaCONTAIreENT E= ELECTRICAL FsFUEL MzMAIN STEAM P= PIPE TaTURSINE G= GEM RIC COMPONENTS USED DUILDING PENETRATION BUILDING T.AJPPORT PEETRATION BUILDING IN MANY LOCATIONS STRUCTURE . gg C H i Oe 3 C a Ge B
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- O O C7/26/88 SNEET 27 OF 65 TA8LE 3-2 ELECTRICAL EQUIPtENT ENVIROt4 ENTAL QUALIFICATION 10 CFR 50.49 MASTER LIST LOCATION EQS PLANT ID 8 COMOENT MAtAJFACTUREE MODEL e8LDG./RM/ELY SERVICE PAJtBE R MD 3293 MOTOR OPERATED VALVE LIMITORQUE Ste-000 C 08S8 81 TRAIN A CNT AIR CLR CLG MTR 45.4.2 NO 1294 HOTOR OPERATED VALVE LIMITORQUE Ste-00 C IBS 77 CCM TO RCP LO COOLER. LET ON HX 1.4.2 MD 3296 MOTOR OPERATED VALVE LIMITORQUE Ste-000 C IBS 77 CCM TO RCP LO COOLER. LET DN HX 3.4.2 MD 3500 MOTOR OPERATED VALVE LIMITORQUE Ste-00 C IBS 77 CCM FM RCP LO COOLER. LET DN HX 1.4.2 MO 3301 A MOTOR OPERATED VALVE LIMITORQUE Ste-00 C OBS8 81 CCM TO CNT AIR CLR 201A 1.4.2 MD 3101 8 MOTOR OPERATED VALVE LIMITORQUE Ste-00 C 0808 70 CCM TO CNT AIR CLR 2018 1.4.2 MO 3302 A MOTOR OPERATED VALVE LIMITORQUE Ste-00 C IBSA 81 CCM TO CNT AIR CLR 201A 1.4.2 MO 3302 8 MOTOR OPERATED VALVE LIMITORQUE Ste-00 C 0808 69 CCM TO CNT AIR CLR 2018 1.4.2 MD 3305 A MOTOR OPERATED VALVE LIMITORQUE Ste-00 C 0858 81 CCM TO CNT AIR CLR 202A 1.4.2 MD 3305 8 HOTOR OPERATED VALVE LIMITORQUE Ste-00 C OBS8 70 CCM TO CNT AIR CLR 2028 1.4.2 MO 3306 A MOTOR OPERATED VALVE LIMITORQUE Ste-00 C OBS8 77 CCM FROM CNT AIR CLR 202A 1.4.2 MD 1306 8 MOTOR OPERATED VALVE LIMITORQUE Ste-00 C 0B08 69 CCM FROM CNT AIR CLR 2028 1.4.2 MD 3309 A MOTOR OPEdATED VALVE LIMITORQUE Ste-00 C OBS8 81 CCM TO CNT AIR CLR 203A 1.4.2 MD 3309 8 MOTOR OPERATED VALVE LIMITORQUE Ste-00 C OBS8 70 CCM TO CNT AIR CLR 2038 1.4.2 HD 3310 A MOTOR OPERATED VALVE LIMITORQUE Ste-00 C IBSA 81 CCM FROM CNT AIR CLR 203A 1.4.2 MD 3313 8 HOTOR OPERATED VALX LIMITORQUE Ste-00 C OBSS 69 CCM FROM CNT AIR CLR 2048 1.4.2 MD 3313 A MOTOR OPERATED VALVE LIMITORQUE Ste-00 C 0858 81 CCM TO CNT AIR CLR 204A 1.4.2 MD 3313 8 MOTOR OPERATTO VALVE LIMITORQUE Ste-00 C 08S8 73 CCM TO CNT AIR CLR 2048 1.4.2 HQ 3314 A MOTOR OPERATED VALVE LIMITOrQUE Ste-00 C OBS8 81 CCM FROM CNT AIR CLR 204A 1.4.2 8 BUILDING CODE A= AUXILIARY C=CONTAlteENT E= ELECTRICAL F= FUEL MzMAIN STEAM P= PIPE T=TURSINE C=CENERIC COMPONENTS USED BUILDING PE E TRATION BUILDING SUPPORT PENETRATION BUILDING IN ttANY LOCATIONS STRUCTURE
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$ PLANT LOCATION EQS ID 8 COMPOPENT MANUFACTURER NODEL *BLOG./RP1/E LV SERVICE NUMBER 70 3314 8 HOTOR OPERATED VALVE LIMITORQUE stb-00 C 0858 69 CCH FROM CNT AIR CLR 2038 1.4.2
#10 3120 MOTOR OPERATED VALVE LIMITORQUE 2B-000 C IBS 77 CCM FM RCP LO COOLER, LET DN HX 1.4.2 HQ 3346 MOTOR OPERATED VALVE LIMITORQUE Ste-00 P 168 45 CCH ISL-CLASS ItCNTI 46.4.2 FC 3347 HOTOR OPERATED VALVE LIMITORQUE Ste-000-5/408C C OBS8 62 TRAIN 8 CAC CLG HTR 45.4.2 to 4005 MOTOR OPERATED VALVE ROTORK 11 NAT 1 C OBSF 42 REAC COOL DR TK OUT 16.4.2 to 4180 MOTOR OPERATED VALVE LIMITORQUE stb-000 C OBSF 50 CNT SLR1P Pt1P DISCH 45.4.2 NO 4300 POTOR OPERATED VALVE LIMITORQUE SMB-000 C 0808 63 RAACT CAS CLTG HDR 45.4.2 to 4903 A HOTOR OPERATED VALVE LIMITORQUE SIB-000 T 85 45 INL TO T-111A MILD HQ 4903 8 910 TOR OPERATED VALVE LIMITORQUE SMB-000 T 86 45 IPA TO T-1118 MILD MD 4907 A MOTOR OPERATED VALVE LIMITORQUE Ste-OOO T 90 45 FR T-119A TO T-152 t1ILD to 4907 8 HOTOR OPERATED VALVE LIMITORQUE "MB-000 T 90 45 FR T-1198 TO T-152 MILD EO 5651 A POTOR OPERATED VALVE LIMITORQUE SMS-0C0 C OBSB 55 ACCUM T205A SMPL ISLN VLV 45.4.2 70 5651 8 HOTOR OPERATED YALVE LIMITORQUE Ste-000 C OBS8 55 ACCUM T2058 St1PL ISLN VLV 45.4.2 to 5651 C 710 TOR OPERATED VALVE LIMITORQUE SPB-000 C 0B08 55 ACCOM T205C SNPL ISLN VLV 45.4.2 MO 5651 0 POTOR On, RATED VALVE LIMITORQUE Ste-000 C 0B08 55 ACCUtt T205D St1PL ISLN VLv 45.4.2 PO 5653 HOTOR OPERATED VALVE LIMITORQUE "tB-000 C IBSA 54 RCS HOT LEG TO SMPL SYS 45.4.2 PO 5654 UTOR OPERATED VALVE LIMITORQUE SMB-OOO C IBSA 54 RCS HOT LEG TO St1PL SYS 45.4.2 to 5456 MOTOR OPERATED VALVE LIMITORQUE Ste-000 C IBSA 54 PRSRZ TO SMPL SYS 45.4.2 HG 5458 POTOR OPERATED VALVE LIMITORQUE Ste-000 C ISSA 54 PRSRZ TO SP1PL SYS 45.4.2 o BUILDItG COOE AzAUXILIARY CzCONTAIt#ENT E= ELECTRICAL F= FUEL M: MAIN STEAtt PzPIPE T=TURBIPE GrGEPERIC COMPOPENTS USED BUILDItG PENETRATION BUILDING SUPPORT PENETRATION BUILOIPT, IN mat # LOCATIONS STRUCTURE e
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l C7/26/88 SHEET 30 OF C5
^g TABLE 3-2 cu $5 to U ELECTRICAL EQUIPMENT ENVIR0t#1 ENTAL QUALIFICATION re o ,S 10 CFR 50.4? HASTER LIST LOCATION EQS
- PLAMT ID 8 COPPOtENT HAFAJFACTURER HODEL eBLDG./RtVE LY SERVILE NUtCER t10 8110 HOTOR OPERATED VALVE LIMITORQUE 2 6-00 A 151 25 CHG Pt1P HIN FL LN ISLN EXEHPT P10 8111 MOTOR OPERATED VALVE LIMITORQUE 2B-00 A 151 25 CHG PHP MIN FL LN ISLN EXEMPT HD 8112 NOTOR OPERATED VALVE LIMITORQUE 2 8-00 C OBS8 67 RCP SEAL HTR RETURN ISLN 45.4.2 MD 8700 A MOTOR OPERATED VALVE LIMITORQUE stb-3 A 125 5 RHR PHP A SUCT EXEMPT P10 8700 B MOTOR OPERATED VALVE LIMITORQUE 2B-3 A 123 5 RHR PtP B SUCT EXEMPT P10 8703 HOTOR OPERATED YALVE LIMITORQUE 2 0-2 P 168 45 RNR HOT LEG INJN 1.4.2 HQ 8716 A HOTOR OPERATED VALVE LIMITORQUE DB-2 A 127 5 MOT LEG IPLJN FROM TRAIN A PCR-86-132 PO 8716 S MOTOR OPERATED VALVE LIMITORQUE 2B-2 A 122 5 HOT LEG ItLJN FROM TRAIN B PCR-86-132 21 0 6801 A MDTOR OPERATED VALVE LIMITORQUE stb-0 P 168 45 BIT DISCH 46.4.2 HD 8801 8 HOTOR OPERATfD VALVE LIMITORQUE 26-0 P 168 45 BIT DISCH 46.4.2 PO 8802 A ROTOR OPERATED VALVE LIMITORQUE 26-0 P 185 63 SI TO HOT LEG 2 & 4 46.4.2 to 8802 8 HOTOR OPERATED VALVE LIMITORQUE 2B-0 P 185 63 SI TO HOT LEG 1 & 3 46.4.2 to 8803 A 710 TOR OPERATED VALVE LIMITORQUE 2 B-0 A 141 25 BIT INL 46.4.2 PO 8803 8 HOTOR OPERATED VALVE LIMITORQUE 2B-0 A 141 25 BIT INL 46.4.2 PO 8806 A POTOR OPERATED VALVE LIMITORQUE 26-2 A 127 5 RHR HX A Out' TO CHARG PPS PCR-86-132 t10 8804 8 POTOR OPERATED VALVE LIMITORQUE Ste-2 A 122 5 RMR HX B OUT TO $1 PPS PER-86-132 71 0 8806 POTOR OPERATED VALVE LIMITORQUE stb-0 A 121 5 SI PHP SUCT EXEMPT to 8807 A HOTOR OPERATED YALVE LIMITORQUE stb-00 A 121 5 SIP /CCP SUCT NCR-86-132 71 0 8807 8 710 TOR OPERATED VALVE LIMITORQUE 28-00 A 121 5 SIP /CCP SUCT PCR-86-132 o BUILDING CODE: A=AUKILIARY C=CONTAltafMT E= ELECTRICAL F= FUEL MzitAIN STEAM P PIPE T= TURBINE CzCEtERIC COMPOtENTS USED BUILDItG PEFETRATION BUILDING SUPPORT PEtETRATION BUILDItG IN P1ANY LOCATIOtG SIRUCTURE m
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SHEET 31 OF 65 TA8LE 3-2 ELECTRICAL EQUIPMENT ENVIMtetENTAL QUALIFICATION 10 CFR 50.49 MASTER LIST LOCAT?ON EOS PLANT ID 8 COWOffMT MMRKACTURER MODEL *8LDd. 4tM/ELV SERVICE NUtBER MD 8809 A MOTOR OPERATED VALVE LIMITORQUE SMB-3 P 170 45 RHR COLD LEG INJN NCR-86-132 MD 8809 8 M0!JR OPERATED VALVE LIMITORQLE *JS-3
. P 169 45 RHR COLO LEG INJN NCR-86-132 MD 8811 A M TOR OPERATED VALVE LIMITORQUE Ste-1 P 170 45 RHR TRAIN A CNT SIA9 ISLN EXEMPT MG 8811 B PWTOR OPERATED VALVE LIMITORQUE Ste-3 P 169 45 RHR TRAIN 8 CNT St.RF ISLN EXEtFT MG 8812 MOTOR OPERATED VALVE LIMITORQUE Ste-3 A 14.s 25 RHR Pff SUCT EXEMPT MD 8813 MOTOR OPERATED VALVE LIMITORQUE "JS-00 A 148 25 SI Per HIN FL LN ISLN EXEMPT MD 8814 MOTOR OPERATED VALVE LIMITORQUE *JS-00
. A 148 25 SI Ptr MIN FL LN ISLN EXEMPT PW 8821 A MOTOR OPERATED VALVE LIMITORQUE Ste-00 P 185 63 SI PHP A DISCH TO RCS CLD LG 46.4.2 MD 8821 S MOTOR OPERATED VALVE LIMITORQUE Ste-00 P 185 63 SI PMe B DISCH TO RCS CLO LG 46.4.2 MD 8835 MOTOR OPERATED VALVE LIMITORQUE Ste-o P 185 63 COLD LEG SI 46.4.2 MD 8923 A MOTOR OPERATED VALVE LIMITORQUE Ste-00 A 121 5 SI PMP A SUCT SLK VLV NCR-86-132 MD 8923 3 MOTOR OPERATED VALVE LIMITORQUE *JS-00
. A 121 5 SI Pfr 8 SUCT BLK VLV HCR-86-132 MO 0924 MOTOR OPERATED VALVE LIMITORQUE SPS-00 A 127 5 CHARGING PHP TO SI Pfr SUCT NCR-86-132 MD 10005 MOTOR OPERATED VALVE LIMITORQUE Ste-00 E 358 82 H2 VENT SPLY 45.4.2 MD 10006 MOTOR OPERATED VALVE LIMITORQUE *JS-00 E 358 82 H2 VENT SPLY 45.4.2 MD 10007 MOTOR OPERATED VALVE LIMITOidQUE Ste-00 C 0858 78 H2 VENT SPLY 45.4.2 MD 10008 MOTOR OPERATED VALVE LIMITORQUE ".JS-00 C 08SB 78 H2 VENT SPLY 45.4.2 MO 10009 MOTOR OPERATED VALVE LIMITORQUE Ste-00 C 08S8 77 H2 VENT EXM 45.4.2 MD 10010 MOTOR OPERATED VALVE LIMITORQUE Ste-00 C 0558 59 H2 VENT EXH 45.4.2 e DUILDING CODES A*AUKILIARY CzCONTAIIGENT E= ELECTRICAL F= FUEL M* MAIN STEAM PzPIPE TuTURBINE CzGENERIC COMPONENTS USED OUILDING PENETRATION DUILDING SUPPORT PENETRATION SUILDING IN MANY LOCATIONS STRUCTURE S.h c
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- > C7/26/88 SHEET 32 OF G
>b TA8LE 3-2 C s)
$ o.
$a:s ELECTRICAL EQUIPMENT EtNIROr#1 ENTAL QUALIFICATION y.v ". 10 CFR 50.49 HASTER LIS'.
$ LOCATION EQS PLANT ID 8 COMPOENT mat &JFACTURER t100EL *BLOG./RM/ELV SERVICE NUtBER to 10011 MOTOR OPERATED VALVE LIMITORQUE SNS-OO P 168 45 H2 VENT EXH 45.4.2 to 10012 MOTOR OPEPATED VALVE LIMITORQUE Ste-00 P 168 45 H2 VENT EXH 45.4.2 PO 10013 MOTOR OPERATED VALVE LIMITORQUE stb-000 C 0608 81 CHLD HTR RTH 45.4.2 NO 10016 MOT (Xt OPERATED VALVE LIMITORQUE stb-000 C MA 81 CHLD HTR SPLY 45.4.2 MP 108 A F10 TOR HESTINGHOLGE VSH1 I 394 25 'H PHP A MILD
#1P 108 8 HOTOR HESTINGan FS VSH1 I 3% 23 SH PHP B HILD P1P 108 C ICTOR HESTINGHOUSE VSH1 I 3% 25 LH PMP C HILD P1P 1% A NOTOR CRANE CO. O OUT 45 DSL OIL PHP FOR T-119A MILD
#1P 1% 8 MOTOR CRAPE CO. O OUT 45 DSL OIL PMP FOR T-11'4 NILD PP 148 A t10 TOR ALLIS-CHALHERS 142 A IM 45 $4 BSTR PMP A EXEMPT P1P 148 8 t10 TOR ALLIS-CHALMERS 142 A 164 45 SH BSTR PHP 8 EXEt1PT 99 148 C POTOR ALLIS-CHALHERS 142 A 164 45 SH BSTR PMP C EXEMPT F1P 148 D PCTOR ALLIS-CHALMERS 142 A 164 45 SH BSTR PHP D EXEMPT P1P 168 POTOR SALDOR 27384-11925 T 90 45 DSL AFH L 0 PMP SPD INCRS8t MILD 79 202 A POTOR KSTIPCHOLCE VLHI A 127 5 RHR PHP P202A 23.4.2/9.4.10 f1P 202 8 P10 TOR HESTINGHOUSE VSHI A 122 5 RHR PHP P2023 23.4.2/9.4.10 PP 203 A MOTCR HESTINCilOUSE HSDP A 121 5 SI PNP 203A 23.4.2/9.4.10 MP 203 8 HOTOR HESTINC?n FJ HSDP A 120 5 SI Pt1P 2038 23.4.2/9.4.10 71P 2C4 A HOTOR ALLIS CHALMERS TYPE GV A 129 10 CNT SPRAY Pt1P P204A 22.4.2/9.4.10 0 BUILDING CODE: A= AUXILIARY C=CONTAIttiNT E= ELECTRICAL F= FUEL H: MAIN STEAM P= PIPE T= TURBINE C=CEtERIC COMPONENTS USED BUILDItG PEtETRATION BUILDItG SUPPORT PENETRATION BUILDItG IN HAf# LOCATIOtG STR'JCTURE D
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C7/26/88 SHEET 33 OF 65 TASLE 3-2 ELECTRICAL EQUIPMENT ENVIRODGENTAL QUALIFICATION 10 CFR 50.49 MASTER LIST LOCATION EQS PLANT ID 8 Cop 90ENT MApaXACTURER MODEL *BLOG./RM/ELV SERVICE PA#eER MP 204 86 MOTOR ALLIS CHALMERS TYPE GV A 130 5 CNT SPRAY PMP P2048 22.4.2/9.4.10 N 205 A MOTOR NESTINGHOUSE HSDP A 153 25 CNTFGL CHG PHP P205A 23.4.2/9.4.10 ff 205 S MOTOR ESTINGHOUSE HSDP A 156 25 CNTFGL CMG Pf@ P2058 23.4.2/9.4.10 MP 210 A MOTOR ALLIS-CHALMERS 142 F 228 45 CCM Ptp TRAIN A EXEMPT w 210 S MOTOR ALLIS-CHALIERS 142 F 228 45 CCM PrP TRAIN 8 EXEHPT MP 210 C MOTOR ALLIS-CHALMERS 142 A 164 45 CCM Pf9 TRAIN A/B EXEMPT
#9 218 A MOTOR ALLIS-CHALMERS RCV F 228 45 CCM 99 TUP Ptr TRAIN A EXEMPT 89 218 8 MOTOR ALLIS-CHALMERS RCV F 228 45 CCN REUP Ptr TRAIN 8 EXEMPT MP 221 A MOTOR HESTINGNOUSE $80P A 153 25 CCPA AUX LUS OIL 43.4.2 39 221 S MOTOR HESTINGHru PS $80P A 156 25 CCPS AUX LtB OIL 43.4.2 W 143 A MOTOR ESTINGHrm $80P C 45 77 CA8LE SPREADING RM 43.4.2 PfV 143 8 3R M STINGHOUSE $80P C 45 77 CABLE SPREADING RM 43.4.2 ffV 143 C fuTOR ESTINGHru r# $80P C 45 77 CABLE SPREADIts RM 43.4.2 W 143 9 MOTOR HESTINGHOUSE $80P C 45 77 CABLE SPREADING RM 43.4.2 fW 143 E MOTOR 9ESTINGHCUSE 580P C 45 77 CASLE SPREADING RM 43.4.2 MV 143 F MOTOR NESTINGHOUSE SBOP C 45 77 CA8tE SPREADING RM 43.4.2 MW 145 A MOTOR NESTINGHOUSE TBOP C 38 65 EONT BLOG ELEC AUX RM MILO
! PfV 145 3 MOTC4 NESTINGHOUSE TBOP C 34 61 CONT SLOG ELEC AUX RM MILO l fW 145 C MOTOR HESTINGHOUSE TSOP C 34 61 CONT SLOG ELEC AUX RM MILO O BUILDIaG CODE: AzAUKILIARY C=CONTADGENT EzfLECTRICAL F* FUEL M MAIN STEAM PzPIPE TzTURBINE C= GENERIC COP 90ENTS USED f SUILDING PENETRATION SUILDING SUPPORT PEETRATION SUILDING IN MANY LOCATIONS 4 STRUCTURE I j-> 4 it " l, 0. 8a. ' <* e e-= rs GD G l G i.v 1-t
C7/26/88 SHEET 34 OF CS my TABLE 3-2 Nb om :s
$$ ELECTRICAL EQUIPMENT EINIROr&1 ENTAL QUALIFICATION
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$ 10 CFR 50.49 ttASTER LIST C
** LOCATION EOS
", PLANT ID 8 COff0 TENT MAtaJFACTURER HODEL
- BLDG./Rtt/ELV SERVICE PAJtOER PW 145 O HOTOR M STINGHOUSE TBDP C 38 61 CONT BLDG ELEC AUX RH HILD tw 145 E NOTOR BESTINGHOUSE TBDP C 38 61 cot 4T BLDG ELEC AUX RM MILD IN 163 A FAN POTOR HESTINGHOUSE TBOP T 107 69 SHrdt RM CLG 124IT HILD tN 163 8 FAN POTOR HESTItsGHOUSE TBDP T 107 69 SHGR RM CLG UNIT HILD PW 163 C FAN HOTOR HESTINGHOUSE TBDP T 107 69 SHGR Rt* CLG tRIIT HILD PN IM FAN HOTOR HESTINGHOUSE TBOP T 107 69 SHGR RM CLG L.*41T HILD IN 251 A FAN HOTOR HESTINGHOUSE SBDP A 153 25 CENT CHARGIFC PHP A RM CLR 63.4.2/9.4.8 FW 251 B FAN HOTGR HESTINClint FS SBDP A 156 25 CENT CHARCIts PHP 5 RM CLR 63.4.2/9.4.8 PN 252 A FAN HOTOR HESTItaGHOUSE SBDP A 129 5 CNT SPRAY Pt1P A RM CLR 63.4.2/9.4.8 PW 252 8 FAN FOTOR HESTINGHOUSE SBDP A IIC 5 Ct4T SPRAY PMP S RM CLR 63.4.2/9.4.8 PN 253 A FAN HOTOR HESTINGHOUSE SBDP A 123 5 RHR PHP A Rtt CLR 63.4.2/9.4.8 PN 253 8 FAN P10 TOR HESTINGHOUSE SBDP A 125 5 RHR Pt1P B RM CLR 63.4.2/9.4.8 PN 254 A FAN HOTOR HESTINGHOUSE SBDP A 121 5 SIS PHP A RM CLR 63.4.2/9.4.8 PN 254 8 FAN P10 TOR HESTINGHOUSE SBDP A 120 5 SIS Pf1P B Rtt CLR 63.4.2/9.4.8 tw 256 A FAN HOTOR HESTItJGHOUSE SBDP F 228 45 CCM PHP A CLR 43.4.2 tN 2CS S FA*a 210 TOR HESTINGHOUSE SBDP F 228 43 CCM PitP S CLR 43.4.2 PN 256 C FAN HOTOR HESTINGHOUSE SBDP A 164 45 CCM PMP C CLR 43.4.2 PN 304 A FAN HOTOR M STINGHOUSE SBDP A 164 45 SH BSTR PHPS A 8 C CLR MILD PN 304 8 FAN HOTOR M STINGHOUSE SBDP A IM 45 SH BSTR Pt1PS B & D CLR ttILD u BUILDItC CODE. A=AtJKILIARY C=CONTAIt&ENT E= ELECTRICAL F= FUEL tt=HAIN STEAN PaPIPE T= TURBINE G=CEtERIC COMPONENTS USED BUILDIts PENETRATION BUILDIPC SUPPORT PENETRATIOrt BUILDIts IN ttAtw LOCATIONS STRUCTURE W
W 9 O O
3 V C7/26/as SHEET 35 0F 65 TASLE 3-2 ELECTRICAL EQUIPfENT ENVIR0pe1 ENTAL QUALIFICATION 10 CFR 50.49 MASTER LIss' LOCATION EQS PLANT ID 8 Cof90E NT MADEXACTURER MODEL
- BLDG./RM/ELV SERVICE NUMBER l
MVC 131 A MOTOR RELIANCE TYPE P T 85 45 DIESEL GEN EXH FAN HILD MVC 131 S MOTOR RELIANCE TYPE P T 85 45 D*A GEN EXM FAN MILD-MVC 132 A MOTOR RELIANCE TYPE P T 86 45 DSL CEN EXN FAN MILD MVC 132 S MOTOR RELIANCE TYPE P T % 45 D*A GEN EXH FAN MILP fWC 14Z A MOTOR DESTINGHOUSE $8DP C U 105 CTRL RM RECIRC FAN, CS-1 HILD MVC 142 S NOTOR E STINGHOUSE SBDP C 77 105 CNTR RM RECIRC FAN. CS-1 MILD MVC 146 A MOTOR GE 61109-11722 C 38 65 STRY RM EXH FAN, CS-7 HILD MVC 146 3 MOTOR GE 61109-11722 C 38 65 STRY RM EXH FAN, C5-7 MILD MVC 163 MOTOR RELIANCE TYPE P T 85 45 OSL CEN CLC FAN HILD MVC 162 MOTOR RELIANCE TYPE P T 86 45 DSL GEN CLC FAN MILD MVC 165 MOTOR RELIANCE 4YZ65908Al-LY M ROOF 93 AFN PPP CLG FAN MILD - MVC 166 MOTOR RELIANCE TYPE P T 91 45 AFN PPP CLG FAN MILD MVC 167 MOTOR RELIANCE TYPE P T 87 45 DIESEL AFN PHP RM CLG FAN 88.4.2 MVC 16e MOTOR RELIANCE TYPE P T 89 45 AFN PMP CLC FAN MILD ffVC 181 A MOTOR RELIANCE 600288 I ROOF 45 SN PHP RM FAN HILD IWC 181 S MOTOR RELIANCE 600288 I ROOF 45 SN PHP RM FAN HILD MVC 201 A MOTOR RELIANCE 600287-2 C OBSA 205 CNT AIR CLR VC201A 10.4.2 MVC 201 B MOTOR RELIANCE 600287-2 C OBSA 205 CNT AIR CLR VC2018 10.4.2 fWC 202 A MOTOR RELIANCE 600287-2 C 0854 205 CNT AIR CLR VC202A 10.4.2 e BUILDING CODE A=AUKILIARY C=CONTAIletENT E* ELECTRICAL F= FUEL H= MAIN STEAM P= PIPE TsTURSINE CzGEIERIC COP 90NENTS USED SUILDING PENETRATION BUILDING SUPPORT PENETRATION BUILDING IN MANY LOCATIONS STRUCTURE C.ir c
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9 1 C7/26/88 SHEET 36 OF 65 icu (( TABLE 3-2
$5 i 88 Q ELECTRICAL EQUIPHENT EtNIR0t#1[NTAL QUALIFICATION l ~$ 10 CFR 50.49 MASTER LIST 1
e > os vi , *O LOCATION EQS I PLANT ID 3 COtPOrENT HAPAJFACTURER HODEL = BLDG./Rtt/ELY SERVICE Hut 1BER l l ff%C 2C2 8 HOTOR RELIANCE 600287-2 C OBSA 205 CNT AIR CLR VC2028 10.4.2 l l PNC 203 A r10 TOR RELIANCE 600287-2 C OBSA 205 CNT AIR CLR VC203A 10.4.2 l ! NYC 203 8 HOTOR RELIANCE 600287-2 C OBSA 205 CNT AIR CLR VC2038 10.4.2 PfVC 204 A HOTOR RELIANCE 600287-2 C CBSA 205 CNT AIR CLR VC204A 10.4.2 tr/C 204 8 HOTOR RELIANCE 600287-2 C OBSA 205 CNT AIR CLR VC2048 10.4.2 i tWC 220 A P10 TOR RELIANCE w00287-3 C OBSA 205 H2 POCG FAN CHAN A 10.4.2 l PWC 220 8 710 TOR RELIANCE 600287-3 C OBSA 205 H2 HXG FAN CHAN B 10.4.2 C) 6991 CONTROL STATION CE EB25A08B A 225 93 PERSOt#EL AIR LOCK LEAK DET 13.4.4 N 6992 CONTROL STATION GE EB25A08B A 225 93 PERSOt#EL AIR LOCK LEAK DET 13.4.4 PE 48 IEUTRON FLLDC DETECTOR CAtt1A HETRICS 200574113 C IBSF 51 PEUTRON FLtDC HONITOR 72.4.2 341 48 AFFLIFIER GAtt1A HETRICS 900113101 C 36 61 NEUTRON FLUX t10NITOR 72.4.2 NTS 301 SPLICE POINT RAYCHEM NCSF-N C OBSA 93 SV10158 & SV10168 9.4.2 NT3 302 SPLICE POI:4T RAYCHEM NCSF-N C OBSA 93 SV1015A & SV1016A 9.4.2 NT3 534 TERMINAL BOARD BUCitANAN NQB108 H 442 77 ZS-2216 17.4.2 NTS 535 TERttINAL BOARD BUCHANAN NQB108 M 442 82 ZS-2216 17.4.2 NT3 536 TERT 1INAL BOARD BLCHANAN NQB108 M 443 77 ZS-2276 17.4.2 NTS 537 TERitINAL BOARD BUCHANAN t2 108 M 444 82 25-2256 17.4.2 NTS 538 TERitINAL BOARD BUCHANAN NQB108 M 444 82 25-2256 17.4.2 NTS 539 TERitINAL BOARD BUCHANAN NQB108 M 443 82 25-2276 17.4.2
- DUILDING CODE A*AUXIL U RY C=CONTAIt#ENT E= ELECTRICAL F= FUEL tt: MAIN STEAtt P= PIPE T*TURBIPE C=CEFERIC COMPONENTS USED BUILDING PENETRATION BUILDING SUPPORT PLNETRATION BUILDItC IN ttANY LOCATIONS STRUCTURE
,O e O O O
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- S = - L I P A L T
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0 11 11 11 111 21 0 0 0 3 31 4 1 4 5 6 7 12 SRT - 3 RM I V 1 1 1 1 1 1 1 1 1 NPU OC - 0 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 6 IPR - N 9 1 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 2 AUT E E 4 6 4 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 MSS - L 0 1 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 = - L T 0 E 1 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 M - N 5 D B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 B E O Q 0 0 0 0 0 ,5 0 0 0 0 0 0 0 0 0 0 0 0 0 MR M N 9 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 5 G . ~ A P F N I C I - T U D Q 0 E L 1 LL EI UU FS A s C I R T R S C F 8 C E I L(D E L E R U s R T AI CT - T C A m a a n EOLN L L L L L L L L L L L L L L L L O G G G C O O G O G O D O O D G N N N N N M N N M N N N N N N NE IA RR TT - a At E E E E E E E E E E E E u N M N N PN M N N N PN N EEM N N M N E E E C EE - R r Aer NP - mG A A M AWP A MAM A MNNPA A A M AMANP A MAMWNMN 8 A LE EP M A A A A = E T . . N E - 0 t I - A - T G N E C
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Q l l l l C7/16/88 SHEET 38 OF C5 gg co TABLE 3+2 N$ e s ELECTRICAL EQUIPt1[NT Et#IR0ta1[NTAL QUALIFICATION 1 <+ u 3 10 CFR 50.49 MASTER LIST l c
$ LOCATION EQS v PLANT ID 8 COff0 TENT NAtaJFACTURER MODEL
- BLDG./RM/ELV SERVICE nut 1BER NZ 21 PE ETRATION AMPHENOL 50003326-12 C OBS8 57 L.V. POHER 8.4.2 l
NZ 22 PENETRATIQ4 AMPHENOL 50003326-18 C 0858 57 L.V. POHER & CONTROL 8.4.2 NZ 24 PENETRATION AMPHENOL 50003326-19 C L858 57 L.V. POHER 8.4.2 NZ 29 PENETRATION AMPHENOL $0003326-17 C 0858 53 MISC ItGTRUNENTATION 8.4.2 NZ 30 PENETRATION AMPHENOL 50003126-17 C 0BS8 53 Carli ATM TEMP 8.4.2 NZ 31 PENETRATION AFFHENOL 50003326-17 C 0858 66 IN-CORE ItGTRUMENTATION 8.4.2 PDIS 3702 A PRESS DIFF SMITCH NOT ACCESSIBLE O OUT 25 SH PHP DISCH HDR STNR DIFF MILD POIS 3702 8 PRESS DIFF SMITCH POT ACCESSIBLE O OUT 15 SH PMP DISCH STNR DIFF MILO PDS 3399 A PRESS DIFF SMITCH BARTO4 288A A IM 45 CCH PHP A DIFF PRESS EXEMPT PDS 3399 8 PRESS DIFF $ HITCH BARTQ4 288A A IM 45 CCH Pt1P 8 DIFF PRESS EXEt1PT PS 3072 C PRESSURE SMITCH ROCHESTOR ET 1215 T 89 45 AFH PP A SUCT PRESS MILD PS 3072 D PRE *4,URE SMITCH ROCHESTOR ET 1215 T 90 45 AFH Ptf 8 $UCT PRESS MILD PS 3073 X PRESSURE SHITCN MERCOID CQ4 TROL DA33-804 T 90 45 P1028 SPEED INCREASER L 0 MILD PS 3701 A PRESSURE SMITCH MERCONTROL DA7033-804 I 194 23 SH SYS Pt1P DISCH PRESS HIL D PS 3701 8 PRESSURE SHITCH PERCOt4 TROL DA7033-804 I 394 23 SHS PHP DISCH PRESS MILD PS 3711 A PRES % IRE SHITCH P1ERCONTROL DA7033-804 A IM 45 SH BSTR PHP EXEMPT PS 3711 8 PRE
- M SHITCH MERCONTROL DA7033-804 A IM 45 SH BSTR PHP EXEMPT PS 3711 C PRESS:JRE SHITCH MERCONTROL DA7033-804 A IM 45 SH BSTR PHP EXEPPT PS 3711 D PRES $URE SMITCH PERCONTROL DA7033-804 A IM 45 SH BSTR PMP EXEtPT e BUILDING CODE AxAUXILIARY C=CDdTAItaENT E= ELECTRICAL FxFUEL M41AIIs . J1 PsPIPE T=TURBIFE C=CEFERIC COMPOtENTS USED BUILDING PENETRATION BUILDING SUPPC PEtETRATION BUILDItG IN P1ANY LOCATIOtG STRutsutE e
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- PLANT ID S CD1POENT taABE R MAtaKACTUPER MODE L *SLDG./RPVE LV "J RVICE OV 10501 SOLENDID VALVE C 53 93 RECIRC AIR OtPR CD4T C8-2 MILD LV 10502 00tttOID VALVE C 53 91 RECIRC AIR OfR CONT CS-2 MILO OV 10503 00LEtOID VALVE C 53 93 EXH AIR DNPR CONT C8-12 MILD OV 10504 00LEto!D WALVE C 53 95 LPLY AIR DNPR CQif CB-2 MILD "Y 1189 A CHARGE COff4RTER TEC 5041. C (BOA 129 'J 1189A CHARCE CO NERTER 26.4.3 SV 1189 8 CHARGE CO NERTER TEC 504A C OBOA 129 " 11895 CHARGE COP"4 RTE 2 J 26.4.3 OY 1189 C CHARst Car 4RTER TEC 504A C OBSA 129 LE1189C CHARGE CONERIER 26.4.1 TE 410 A RfD ROSEMOUNT 17 KF C ISSA 62 RCS LP 1 HOT LEG AT/TAVG 15.4.2 TE 410 8 RTD ROLE 70UNT 176KF C ISOA 62 RCS LP 1 COLD LEG AT/TAVG 15.4.2 TE 411 A RTD ROSEtOLNT 176KF C 180A 62 RCS LP 1 HOT LEG AT/TAVG 15.4.2 TE 411 8 st f D ROSEMOL24T 176KF C ISSA 62 RCS LP 1 COLD LEG AT/TAVG 15.4.2 TE 413 A RTD ROLEMOLDIT 176KS C ISSA 62 RCS LP 1 HOT LEG 15.4.2 TE 413 8 RfD ROSEMOUNT 176KS C IBSA 62 RCS LP 1 COLD LEG 15.4.2 TE 420 A RTD ROSEPOUNT 17MF C IF3A 62 RCS LP 2 HOT LEG AT/TAVG 15.4.2 TE 420 8 RTD ROSEMOLR4T 176KF C 180A 62 RCS LP 2 COLD LEG AT/TAVG 15.4.2 TE 421 A RTD ROSEMOLHT 176KF C ISSA 62 RCS LP 2 HOT LEG AT/TAVG 15.4.2 TE 421 8 RTD ROSEMOUNT 176KF C IBSA 62 RCS LP 2 C9tD LEG AT/TAVG 15.4.2 T5 421 A RTO ROSEMOUNT 176%S C ISSA 62 RCS LP 2 HOT LEC 15.4.2 TE 421 8 RTD ROSEMOL24T 176KS C ISOA 62 RCS LP 2 COLD LEG 15.4.2 O BUILDIts CODES As ALIXILI ARY C =CadTAIref MT E= ELECTRICAL F= FUEL M41Af te STEtM PsPIPE T=TURBIta C=CEtE TIC COMPO4ENTS L20E0 DUILDIPG PLPETRATIO4 BUILDIPC SUPPORT PEfETRATION BUILE?tC IN 99Ar# LOCATIO C STRUCTURE S
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0 O % Q s v C7/26/88 SHEET 51 OF 65 TABLE 3-2 ELECTRICAL EQUIPMENT ENVIROPMENTAL QUALIFICATION 10 CFR 50.49 MASTER LIST LOCATION EOS PLANT 10 8 COPPOpKNT MMAXACTURER MODEL =8 LOG./RM/ELV SERVICE #AA18tR TE 450 A RfD ROSEMOLMT 176* F C ISSA 62 RCS LP 3 HOT LEC AT/TAVG 15.4.2 TE 450 8 RTD RO*,E MDLNT 176KF C 2854 62 RCS LP 3 COLD LEC AT/TAVG 15.4.2 TE 451 A RfD ROSEMOLNT 176KF C ISSA 62 RCS LP 3 HOT LEG AT/TAVG 15.4.2 TE 451 8 RfD ROSEMOUNT 176KF C IB5A 62 RCS LP 3 COLD LEG AT/TAVG 15.4.2 TE 453 A RTD ROGE!93 TNT 176KS C IBSA 62 RCS LP 3 HOT LEC 15.4.2 TE 455 8 RTD EeOSEMOUNT 176K3 C 180A 62 RCS LP 3 COLD LEC 15.4.2 TE 440 A RTO ROLEMDLNT 176KF C IBSA 62 RCS LP 4 HOT LEG AT/TAVG 15.4.2 TE 440 8 RTO ROSEMOLNT 176KF C LRSA 62 SCS LP 4 COLD LEC AT/TAVG 15.4.2 YE 441 A RTD ROLEMOLNT 176KF C 180% 62 2CS LP 4 HOT LEG AT/TAVG 15.4.2 YE 441 8 RTD ROLEMOLNT 176KF C ISOA ".2 RCS LP 4 CDu:aEG AT/TAVG 15.4.2 TE 445 A RTO ROLEMOLNT 176KS C IBSA 62 RCS LP 4 HOT LEG 15.4.2 YE 445 8 RTD ROSEMOLNT 176KS C 180A 62 RCS LP 4 COLD LEG 15.4.2 TE 604 RfD PYCO 122-6012-06-17.8 A 127 5 RHR NT EXCHR A OUT 48.4.2 1L 605 RfD PYCO 122-6012-06-17.8 A 122 5 RHR NT EXCHR S OUT 48.4.2 TE 899 RTD MINCO $8809 C 0808 92 avtIS DE EITY CPRSR 54.4.2 YE 900 RfD MINCO $8809 C OBOA 96 RVLIS DEEITY CPROR 54.4.2 TE 901 RTD MItJCO $8809 C 180A 94 RYLIS DEEITY CPROR 54.4.2 TE 902 RTO MINCO $8809 C 1854 62 RYLIS DE EITY CPROR 54.4.2 YE 905 RTD MINC3 $8809 C 180A 66 RYLIS DENSITY CPROR 54.4.2
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$ LOCATION EQL PLANT ID e COMP 0 TENT MAtAJFACTURER MODEL eBLDG./RFVELV OERVICE RARBER TE 904 RTD MINCO 08809 C IBSF 41 DVLIS DEtGITY CPROR 54.4.2 TE 905 RTD P11tCO 58809 C IBOF 24 RVLIS DEtGITY CPROR 54.4.2 TE 906 RTD HINCO 08809 C IBSA 92 RVLIS DEPCITY CPROR 54.4.2 TE 907 RTD MItCO 58809 C OBSA 96 RVLIS DEtCITY CPROR 54.4.2 TE 908 RfD MIFCO $8809 C IBOA 84 RVLIS DEPCITY CPRfJt 56.4.2 TE 909 RTD MIPCO 58809 C IBSA 61 RVLIS DEFCITY CPROR 54.4.2 YE 910 RTD MItCO 08809 C IBOA 65 RVLIG DEICITY CPROR 54.4.2 TE 911 RTD HIPCO $8809 C IBOF 43 RVLIO DEtGITY CPRSR 54.4.2 TE 912 RfD MIPEO 58809 C IBOF 26 RVLIS DEIGITY CPROR 54.4.2 TE 3273 A2 TEt1PERATURE ELEtENT CAPCO 1/2F 304 F 234 45 EXIT TEt1P FROrt CCH HX-2040 LXEt1PT TE 3283 A2 TErrERATURC ELEPENT CAF1CO 1/2F 304 F 234 45 EXIT TEMP FRCH CCM HX-204A EXEMPT TE 10134 RTD MEED N9017D-1A C 0808 65 Ct4T ATM TEMP 76.4.2 UCDA 1 St10KE DETECTOR PYROTRONICS N/A T 86 45 DOL CEN RM Ot10KE DET MILD LNH 187 HEATER CHRONALOX LUH1CMAROLO-00-38-08 C 39 65 STRY RM HTR HILD UVH 188 HEATER CHRONALOX LUH1036AROLO-00-38-08 C 40 65 STRY RM HTR HILD UX 318 A RECoreltER H[STINGHOUSE IVA C OBOA 93 H2 RECOPSIPER A 7.4.2 UX 318 8 RECOtBIFER K OTINGHQ CE N/A C OBOA 93 H2 RECQtIFER S 7.4.2 VE 159 A DUCT HEAT [R MIEGAte DV OF EPERSON DHI18H024L-022KH %0V3 C 77 105 CNTL RM EFER IMIT REHT COIL MILD VE 159 8 D E T HEATER MIEGAte DV OF EtER00N DHI18H024L-022KH%0V3 C 77 105 CNTL Rtt EF1ER UNIT RENT COIL MILD o BUILDIts CODES A s ALDCILI ARY C=CONTAlteENT FrELECTRICAL F= FUEL t1: MAIN STEAM PzPIPE T=TUR8IPE G=CEtKRIC COMP 0 TENTS LEED BUILD 1tG FEtETRATION SUILDIts SUPPORT PEtKTRATIQ4 BUILDIIC IN mat # LOCATIOrG STRUCTURE O O O
1 l C7/26/se $8eEET $3 OF 65 TABLE 3-2 ELECTRICAL EQL*IPPENT ENVIR000 ENTAL QUALIFICATION la CFR 50.49 MASTER LIST LOCATION EGS PLANT 10 S COWOWNT MAftfFACTURER MODEL
- SLOG./RM/ELY SERVICE PERSER VE 161 A DUCT 8eEATER WIEGANB DV OF EDERSON DeeFI2N024L-010K8e%0V3 C 77 305 CNTL 1W8 EMER UNIT RENT COIL MILD VE 161 S DUCT HEATER MIEGANS DV OF EMER'A N DMF12M024L-010KN%0V3 C 77 105 CNTL RM EMER LDdIT RENT COIL MILD NR 424 THREE PHASE RECEPTACLE CROUSE-MIpes AR342-M72 A 164 45 PMR RCPT FOR HV 256C MILD tet 425 TesREC PleASE RECEPTACLE ratu u .NI m AR342-M72 A 164 45 Pte RCPT FOR MV-256C MILD X 11 TRANSFORMER T 107 69 750 KVA LC XFMR S 1 MILD X 12 TitACFORMER ITE C 38 65 750 KVA LC XFMR S 2 MILD X 13 TRANSFORMER T 107 69 750 KVA LC XFPet S 3 MILD X 14 TRANSFOspKR ITE C 38 65 750 KVA LC XFMR S 4 MILD X 40 TRANSF009ER 88EVI-0UTY 8tSIF7.5A il PMASE 9 T 107 69 7.5KVA 480/240 TO 240/120 VAC 47.4.2 l
l X 41 TRA CF00gER HEVI-SUTY 0001FF.5A i1 PMASED C 41 65 7.5KVA,480/240 TO 240/120 VAC 47.4.2 i X 61 TRANSFORPER HEVI-SUTY ELECTRIC CO BtSIF7.5A A 226 93 CMAS EA-TRAINI PNR 47.4.1 l X 62 TRAEFORfER 90EVI-SUTY ELECTitIC CO NS1F7.5A A 216 77 CMAS IS-TRAINI Plet 47.4.1 i Y 11 INSTRUDENT SUS N[3TINGMOUSE C 38 65 120 VAC PFD I ETR SUS CHAN A MILD Y 13 INSTRUPENT SUS NESTINGemm u C 38 65 128 VAC PFD IETR SUS CHAN C FILD Y 15 IssVCRTER ELGAst CORP. 752-1-107 C 38 65 120 V SPLY TO SUS Y11 MILD Y 17 INVERTER ELGAR CORP. 752-1-107 C 38 65 120 V SPLY TO SUS V13 MILD j Y 22 INSTRLMENT SUS NESTINGNOUSE C 38 65 120 VAC PFB IETR SUS CHAN 5 MILD ! Y 24 ICTIRDENT SUS 9dESTIIsize000E C 38 65 120 VAC PFD It20TR SUS CHAN D MILD t Y 26 INWERTER DESTIDsGIOUSE C 38 65 120 V SPLY TO SUS Y22 MILD e SUILDING CODES A=AUXILI AEnf CsCONTAZ89E9ff E* ELECTRICAL F=FU[L M40AIN STEAM P= PIPE TmTURSDEE C=CENERIC COMPONENTS USED SUILDING PE9ETRATION SUILDING SUPPORT PEPETRATION SUILDING IN MANY LOCATIONS STRUCTURE
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mw
", LOCATIO1 EQS PLANT ID 5 COPWTN[NT ttANUFACTUR.*JI MODEL
- BLDG./RtVE LY SERVICE tAASER
*N02-N00277 POME R AND COP (TROL CA8tf G[tERAL CABLE 2/C.314s AMG. G C8L1 WA VARIOUS 4.4.2
*H024400525 POWR Ate COUROL CABLE APERICAN IPCUL. MIRE 2/C.514 AMG. G CBL1 N/A VARIOUS 3.4.2
*H05-H00277 POMR Af40 CONTROL CABLE GENERAL CASLE 3/C.814 AHG. G CBL1 WA VARIOUS 4.4.2
*#405-N00523 PCHER Arm COUROL CA8tf APERICAN 19641. MIRE 3/C.514 ANG. G C8L1 WA VARIOUS 3.4.2
*H05-9400277 POM[R AND COiTROL CASLE GLFERAL CABLE 5/C.314 AMG. G CSL1 WA VARIOUS 4.4.2 et95-H00523 POM[R AND COUROL CABLE APERICAN IPCUL. NIRE 5/C.514 AMG. G CSL1 WA VARIOUS 3.4.2
*tA 7-N00277 POMER AFS COdTROL CA8tf GEH[RAL CA8tf 7/C,814 AMG. G CBL1 WA VARIOUS 4.4.2
*HO'-NOO325 P0HER Are CursTROL CA8tf APERICAF4 IPCUL. MIRE 7/C.514 AMG. G CBL1 N/A VARIOUS 3.4.2
*HIS P0HER AND CGITROL CASLE CE9ERAL ELECTRIC IC 510ANG. SIS G CSL1 WA VARIOUS 58.4.2
*N12 -N29255 POER AND CorsTROL CA8t* BOSTON INSULATED MIRE BOSTRAD 7E G CSL1 WA VARIOL*S 41.4.2 et420-N29253 POMIR Ate CONTROL CABLE 803T04 ItCULATED MIRE BOSTRAD 7E G CSL1 WA VARIOUS 41.4.2
*N2',-N29255 POER Ate COETROL CABLE 80STO4 ItCULATED MIRE BOSTRAD 7E G CSL1 WA VARIOUS 41.4.2
*N25-N29253 PopKR AND Cor4 TROL CA8tf 80STON ItGULATED NIRE BOSTRAD TE G CSL1 WA VARIOUS 41.4.2 at427-N29251 POM[R AND COUROL CABLE BOSTON IPCULATED HIRE BOSTRAD TE G CBL1 WA VARIOUS 41.4.2
*N2'J POM[R AND CONTROL CA8tt GEPERAL ELECTRIC IC SIZAMG. SIS G CBL1 WA VARIOUS 58.4.2
*t430 POM[R AND CD4 TROL CA8tf GEFERAL ELECTRIC IC 314AMG. SIS G CBL1 WA VAJtIOUS 58.4.2
*P01-H04681 P0HER CA8tt OKONITE 1/C,500KCit G CBL5 WA 125VDC STATIO4 SATTERY CABLItG HILD
=P01-N00277 POM[R CABat CEPERAL CABLE 1/C.350KCtt G CBL1 N/A VARIOUS 4.4.2
*P05-N00277 PODER CA8LE GEPERAL CA8LE 1/C,84/0 AHG. G CBLE WA VARIOUS 4.4.2 e BUILDIPC CODES AsAUXILIART CsCONTAIfeENT E=[LECTRICAL F aitE L MrMAIN STEAtt PsPIPE T=TURBIPE G=CEFERIC CorPOPENTS LEED BUILDING PEPEsRATION BUILDIfC *APPOR T
. PE9ETRATIOP4 BUILDIPC IN ttAt# LOCATIOrG STRUCTURE h
l l l h 9 O O
- 0 C7/26/SS '.AeEET 63 0F 6E TASLE 3-2 J
1 ELECTRICAL ESUIP9ENT Eter!BOISEENTAL SUALIFICATION IS CFR 58.49 MASTER LIST LOCATION '9S
" N MT ftISWFACTURER MODEL *BLSC./gSq/ELY $ERVICE ML89ER
=> 9@kR CABLE SGSTtB8 INSULATES MIAE SO5TRAS X G CSL1 WA VARIOUS 41.4.2 l
e 2T7 NDeLR CASLE GE0KAAL CASLE 1/C 81/8 AMG. C CSLI WA VARIOUS 4.4.2
-H2925' # GEER ramt F SOGTON 38GULATES MIAE SOSTRAS 7E G CSLI WA VARIOUS 41.4.2 J . *C*)482-153 atmER CASLE SOSTON INSULATES MINE SOGTRAS 7E C CSL1 98/A VARIOUS 41.4.2
*P31-4888277 POMER CASLE GEsEAAL CASLE 1/C.82 AMG. G CSLR WA VARIOUS 4.4.2
*P12-et2*f55 poser CASLE 805Y(38 INSULATES SERE SOGTRAS 7E C CSL1 N/A VARIOUS 41.4.2 j *Pl!resou2F' FistA CABLE GE9ERAL CASLE 3/C.SS AMG. G CSL1 WA VARIOUS 4.4.2 f
- pap; sus 0325 PEDER Age Capfretw. CASLE AfE RICAff 200542.. NIAE 3/C.SS AMG. G CSL1 WA VARI (123 3.4.2
*P16-top 0!T7 PODER CASLE GE9ESAL CASLE 3/C.818 A84G. G CSL1 WA VARIOUS 4.4.2
*Pir-F.$0323 *0BER Ae# CONTSOL CASLE AfERICAfd IDEUL. MIRE 3/C 818 AMG. C CSL1 N/A VARIOUS 3.4.2
*P A F-AJS2TT POME R CAf** E M9dERAL CASLE 3/C.812 AMG. C CSL1 WA VARIOUS w.4.2
- Ply-te88523 PEDER 20 CONTROL CASLE APERICAff IeCUL. MIrlE 3/C.812 AMG. C CSL1 N/A VARIOU5 3.4.2
*P13-N00277 PUBER CASLE GEIEftAL r m E 3/C,86 A88G. C CSL1 94/A VAftIOUS 4.4.2
*P18-0808323 PODER AMS CSNTROL tm F AMERICAft 195ML. 8dERE 3/C.86 AssG. C CSL1 N/A VARIOUS 3.4.2
*Pl*-te00323 PCsE[R Ace CONTACE. CASLE AfERICaff 1985. IeIRE 1/C.812 AssG. G CBL5 WA VARIOus setts of'28-0008277 poser CASLE McKaAL CASLE 2/C 812 AMG. G CDL1 94/A VARIOUS 4.4.2
*P28-4tSOf23 Ponder AMS CepfTROL CASLE AfERICAff 29ESUL. OdIAE 2/C.812 AteG. G CSL1 S&/A VARIOUS 3.4.2
*P22-eeBS2F7 PCBER CADLE GE9ESAL CASLE 2/C.818 AseG. G CBL1 WA VAftIOLG 4.4.2
*P22-es00123 PoteER CASLE AfERICABI 10CUL. SEIItE 2/C.818 AMG G CSL1 94/A VARIOUS 3.4.2
# SUILSIOC CODES A* AUKILI Afff CaCENSTAI9SEssT EsELFCTRICAL FeFUEL pketAIN STEAft PePIPE T=TURBISE G=GE9ERIC CEDWOBENTS L85ES SUILDIGIG PE9ETRATI(Di SUILSISS SUPPORT PE9ETWATIGO SUILSISC IN ftANY LOCATIONS
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10 CTR 50.49 MASTER LIST on un 08 LOCAT10>4 EQS PLANT ID 5 COMP 0pKNT MAtaK ACTURE R MODE L *BLDC./RWE LV LE RVICE BRAf4R
*P234400277 PODER CABLE CEtKRAL CABLE 4/C.310 ADC. C CBL1 WA VARIGJS 4.4.2
*P234400323 POER CABLE APERICAN ItCUL. MIRE 4/C.510 AMG G CBL1 N/A VARIOUS 3.4.2
*P24-9429253 PONER CABLE 800TG4 IPCULATED MIRE 805TRAD 7E G C8L1 WA VARIOUS 41.4.2
*P324429253 POtta CASLE BOSTON ItCULATED MIRE 80GTRAD 7E G CBLI N/A VARIOUS 41.4.2
*PI74429253 POWR CASLE 80LTD4 IPCLEATED MIRE BOOTRAD 7E G CBL1 WA VARICRJS 41.4.2
*P40-N29253 PO(R CABLE 80STW4 DEULATED MIRE BOSTRAD 7E G C8L1 WA VARImC 41.4.2
*P41-N29253 POMER CABLE 800TW4 DCULATED MIRE 80STRAD 7E G CBL1 WA VARIOUS 41.4.2
*P42-9429253 PODER CABLE 800 TON DCULATED MIRE 80STRA3 7E G C8L1 WA VARIG.G 41.4.2
*P44-N29253 POMER CASLE 805TD4 ItGULATED MIRE 800TRAD TE G CBLE WA VARIOUS 41.4.2
*RG6 IM;1mRENT CA8tE SIM/VICTOREEN 8 78-1-9 G CBL1 WA CNT AREA RADIATION M001ITGtIts 28.4.2/28.4.4
*RG7 ItCTRt2ENT CASTE SIM 1/C.s24AMG 300V. COAX G CBL1 WA CNT AREA RADIATIOP4 Mut4ITORIts 28.4.2
*LPLICE CA8tf 'J AL SAYCHEM HCSF-N G "JAL WA VARIOUS 9.4.2
*002-N00323 IPCTRUPENT CABLE APERICAN IPC 6: IRE 2/C.*.Jt.sI6 AMG G CBL2 N/A VARICUS 3.4.2
*TP' YERMIt4ATION TAPE SCOTCM 43MI S33 GPVCD G TAPE N/A TERT 98 DCULN 36.4.2 cTP6 TERMINATION TAPE SCOTCat E3MI 82510 A TAPE WA TERT 94 IPCULN 34.4.2 CTP7 TERMINATION TArf OCOTCM f IM I SCOTCHFILL A TAPE WA TEstr9i DCULN 36.4.2
*T54 MI CABLE / COP 8KCTORS COPSUOTION ENG C CBL1 WA COftE EXIT TC 71.4.2 CTS 5 MI CA8tt / CDaECTORS COP 9USTION ENG. C CBL1 WA CORE EXIT TC 71.4.'
*TXC TRIAX CABLE CAP 91A METRICS 200T12048 C 0858 >53 NEUTRON FLLM MONITOR 72.4.2
- SUILDIPC CODE s A=ALTKILIARY C=CGdTAItefNT E= ELECTRICAL Fartf L MrMAIN STEAN PsPIPE TsTURBIPE GzGDERIC COMPOPENTS USED BUILDIts PENETRAIIOrd SUILDIPC SUPPORT PDE TR ATIO8 BUILDItC IN MANY LOCATID G STRUCTURE e
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I CT/26/88 SesEET 65 0F 65 YASLE 3-2 ELECTRICAL EQUIPMENT ENVInopOEENTAL SUALIFICATION IS CFR 50.49 MASTER LIST LOCATIOps EGG PLANT IS S COPMBENT MAfREACTURER MOSEL eSL9G./5WWELY SERVICE M.eSER e202-es00525 Ite5TAIDEENT rema r AfEERICAN 106. 98ESE 2/C 088,816 ANC. G CSL1 WA YARIOUS 3.4.2
#205-9800525 1885 TEE 9ENT CASLE AfERICApe IOC. NISE 3/C,088.816 A00G. G CSLI N/A VARIOUS 3.4.2 TETAL COMPUBENTS IN 88AR500 ENVIAEpeE9fTs 218 9e i.7 OG D C CL in U
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second condition assumed the RCS remained intact, with the same sourco term as above contained within the RCS. The TIDs were dotormined for soveral doso point locations, both inside and outside of the Containment. In addition, doses woro calculated for equipment operation times ranging from I hour to 1 year, in order to determino qualification icvols for the maximum time equipment is required to function following an accident. Maximum T TID istues for general areas at Trojan are summarized in Table 8A-1 and Figurco 8A-1 through 8A-10. These values are conservative estimates based on contact dose rates from the largest sourecs in each area. Beta TIDs for materials in contact with reactor coolant and materials exposed to the Containment atmosphere are also provided in Table 8A-1. Figures 8A-11 and 8A-12 provide volume correction factors used to deter-mine 8 integrated doses for finite volumes in the Containment atmosphere. The 40 year background radiation TIDs are presented in Tablo 8A-1 for areas inside and outside Containment. These values are conservativo estimates based on the highest expected sources in each area. The overall TID to a component was determined by summing the normal back-ground dose for 40 years and 110 percent of the y and 8 accident doses @l at that location for the assumed time the component is required to operate post accident, i Appendix 8.A outlines the method for specific component calculations i I and contrins example dose calculations for typical locations insido and outside the Containment. ] i 4.4,1,2 Radiation Damate Threshold Levels
' Because different materials exhibit a wide range of tolerance to radiation damage, radiation threshold levels have been established to exempt enLiln O
i 4 i 4-11 Amendment 4 (August 1987) 1
i i equipment f rom demonstration of its radiation qualification by testing or analysis. The bases for establishing threshold levels are discussed below; selected threshold values are given in Section 4.4.2. References 6 through 8 provide surveys of radiation threshold ef fects on organic materials and electronic devices. Because inorganic and metallia materials are much less susceptible to radiation damage they are not separately considered as part of the qualification review. Information presented in Reference 6 concerning organic materials used in Plant equipment suggests an exclusion from test or further analysis should be allowed for nonelectronic equipment subjected to 10 rads or less. Nonelectronic equipment which contains no Teflon and is subjected to <10 rads should likewise be excluded. At these levels, there is no significant degradation of mechanical or permanent electrical properties of the listed materials. Also at this level, no indications were found in the literature search of significant synergistic effects of radiation combined with other environmental stresses or sensitization to subse-quently imposed stresses. In general, equipment failures occur at some higher level involving considerably more than threshold degradation of coeponent materials. Reference 7 essentially confirms the results of Reference 6. Although Ci four materials in addition to fluorocarbons (Teflon) were identifled as having a change threshold between 10 and 10 rada, the 25 percent 5 damage dose level for these materials ranged above 10 rads. For Teflon, the 25 percent damage level is quoted in the range of 3 to 5 x n O 104 rads. For use as an evaluation criterion, the 25 percent damage level is considered more indicative of radiation damage than the lowest rwported change lhreshold because the changes are real at this level and are not an artif act of the experiment or due to sample variation. Chapter 5 of Reference 8 summarizes the radiation tolerances of various electronic components. Guidelines are also presented for component selection. Radiation damage thresholds are quoted as low as 10 rads O Vendment 5 4-12 (August 1988)
t i (2) DBE test profile to ensure equivalent thermal degradation of test prof 11e is equal to or exceeds the qualification ] requirement temperature profile (see s' 8 3ure 4-4). [ ! (3) Qualification requirement temperature profile (see Fis- ; 1
- ure 4-4) for comparison in (2) above, f' 6
l l I (4) Post-accident operating time. ! I 1 t l ) To illustrate use of the Arrhenius method, consider the following example t I where post-accident operating time is detemined. Assume the required j post-sceident operating time is 1 year at 120'F (322*K). A conservative t representation of the example specimen DBg test. profile is given by: 1 j f l Interval, t, Temperature. T, e j 0.5 hours 250'r (394*K) f 1.4 hours 120*F (322*K) f l 24 hours 250*F (294'K) [ 1000 hours 220'F (377'K) r j Using a conservative activation energy $ = 0.5, and applying the cri- l I 4 teria of Section 4.5.2.1(3) below, post-accident operating time is i detemined from plateau portion of above curve (220'F): i
- I
.5eV 1 1 - t equivalent * .8617 x 10'4eV/*K ' '
i . j = 13,859 hours at 120'r !
! This far exceeds the required post-accident operating time of 1 year (8760 hours),
f I } similar calculations are used to determine equipment qualified life and equivalent themal degradation of the Dat test profile. 1 1 !O 4-19 Ar.endment 5 j (August 1988) 4 l i
4,5,2.1 Selection of Activation Enerr.y for Use In Arrhenius Methodoloir Limiting activation energies provided by the equipment vendor or test latoratory are used in extrapolation for pro-aging tests or post-accident operating times. When activation energies are not provided by equipment vendor, the solection of activation energies should be based upon a detailed review of oven-aging data for the materials involved in the component being tested. These activation energies should be used in all aging tests subject to the following criteria (1) Thermal pre-accident aging is to be dono at a temperature equal to or less than the maximm temperature the activation energy was determined at. (2) Extrapolation of LOCA test data to detemine post-accident operating time may be perfomed using the activation energy determined in a dry even, as atmospheric conditions in the LOCA test chamber closely approximate those found in an actual post-LOCA Containment atmosphere. O Using the above dry oven activation energy will result in a more conservative approach, since the high humidity environ-- ment of the LOCA test will exclude oxygen from the test chamber resulting in less thermal degradation. (3) The above extrapolation of LOCA test data to determine post-accident operating time should only be perfomed on the plateau portion of the temperature test curve that is equal to or less than the maximum temperature the activation energy was detemined at. The above criteria should be applied in all cases unless another approach can be justified. If the activation energy of an organic material used in the conTonent cannot be determined, a value of 0.5 eV can be assured. O Amend.ent 4 4-20 (August 1987)
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$7/26/88 SHEET 3 OF 14 TROJAN NUCLEAR PLANT ENVIROt#1 ENTAL COpeITIONS HORMAL ACCIDENT LOCATION TENERATLRE PRESS 4 ate IRMIDITY RADTN e PEAK RADIATION e EFI (PSIG8 8%8 I RA:IS D tRADSD BUILDING ELEV ROOM EDWIR MAX NORM MIN MAX N9tM MIN MAX NONM MIN Eli,GRie TEN PRESS HLMID GAfttA BETA TABLE 8A-1 REF EFTl DesR (F3 PSIG 5%)
N 25 158 HARSH 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 WA WA WA 5.5E3 , WA HIGHER OF M OR J AUMILIARY 45 161 MARSH 104 30 50 ATM ATM ATM 95 WA 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J AUKILIARY 45 162 HAPSH 104 80 50 ATM ATM ATM 95 WA 2C 6.613 WA l#A WA 5.5E3 WA HIGMER OF M OR J AUKILIARY 45 163 HARSH 104 80 50 ATM ATH ATM 95 WA 20 6.6E3 WA WA WA 5.5E3 WA HIGHER OF M OR J ALIXILIARY 45 164 MARSH 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J AUKILIARY 45 171 HARSH 104 60 50 ATM ATM ATM 95 WA 20 6.6E3 WA WA WA 5.5E3 WA HIGHER OF M OR J AUKILIARY 45 172 HARSH 104 80 50 ATM ATH ATT1 95 WA 20 6.6E3 WA WA WA 5.5E3 WA HIGHER OF M OR J AUKILI AstY 4, 178 HAR$H 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J AUKILIARY 45 179 MARSH 104 80 50 ATM ATM ATM 95 WA 20 6.6E3 WA WA WA 5.5E3 WA HIGHER OF M OR J AUKILIARY 45 180 MAASH 104 80 50 ATM ATM ATM 95 WA 20 6.6E3 WA WA WA 5,5E3 WA HIGHEN OF M OR J AuKILIARY 61 186 flaRSH 104 80 50 f.TM ATM ATM 95 WA 20 4.5EL WA WA 5.5E3 WA HIGHER OF h OR J g idA AUKILIARY 61 187 104 50 95 WA 20 HARSH 80 ATM ATM ATM 0.5ES j WA WA WA 5.5E3 WA HIGHER OF M OR J AUKILI ARY 61 188 HARSH 104 80 50 ATH AsM ATM 95 WA 20 4.5ES WA WA WA 4.4E7 WA K AUKILIARY 61 191 HARSH 104 80 50 ATM ATH ATM 95 WA 20 4.5ES WA WA WA 4.4E7 WA K AUKILIARY 61 192 HARSil 104 80 50 ATM ATM ATM 95 WA 20 4.5ES WA WA WA 4.4E7 WA K AUFILIARY 61 193 HARSH 104 80 50 ATM AIM ATM 95 WA 20 4.5ES WA WA WA 4.4E7 WA K AUKILIARY 61 194 HARSH 104 80 50 ATM ATM ATM 95 WA to 4.5ES WA WA WA 4.4E7 WA K AUKILIARY 61 197 HARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5ES WA WA WA 4.4E7 WA K I e RADIATION DOSES CIVEN ARE 40 YEAR SACKGROtJe TIDS. 3 RADIATION DOSES GIVEN ARE 1 YEAR POST-ACCIDENT TIDS. FOR DOSES LESS THAN ODE YEAR. SEE TABLE SA-1. NOTE: SPECIFIED TID FOR ENVIROt#1 ENTAL QUALIFICATION SHALL BE 1.1 X ACCIDENT PEAK (GAtt1A PLUS BETAl PLUS 40 YEAR BACKGROL.De TIDS. c. 00 3 C CL Em EE on 3
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9n11OIiv' 313A MOOS 34MId 4lYX NOMH HIN WVX NOMH HIN HYX 1t0MH HIN 3 M NO 131M dft3SS tnilO SYWHY 931v 1Y913 9Y-I M33 331( 443B 53( dCIS I%1 YnXI1IYMA 91 I69 HYESH I0 90 SO Y1H ?1H Y1H 65 IMY 20 4*535 4MY 4MY 4MY 9 Y32 4MY M YlMIII 4 91 I66 HYNOH 106 90 SO Y1N Y1H Y1M 6S N/Y 20 9*53S N/Y 4MY N/Y 9 Y32 N/Y M TDDlIYBA 91 Z00 HYMOH I09 90 50 Y1H Y1H VIH 65 N/Y 20 9*53S N/Y 4MY 4MY 9V3Z JMY M YDD1IYNA 91 Z01 HYNOH I09 90 SO Y1N Y1N Y1H 65 N/Y 20 9*53S N/Y 4MY N/V 9 93L N/Y M YlMIIIYNA 91 ZOZ HYHSH 109 90 50 Y1N Y1H Y1N 65 N/Y 20 4*535 4MY 4MY N/Y 9 V34 4MY M YnXIlif5A 91 Z01 HYHSH !09 90 50 Y1N Y1H Y1H 65 N/V ZO I*131 N/V 4MY 4MY S*53E 4MV HIOH3H OJ H 08 r YnXIlIYNA 91 Z09 HYBSH I09 90 50 Y1N Y1H VIH 65 4MV ZO 9 53S N/Y 4MY 4MY 9*931 4MY M YnXI11YNA 91 20S HYHSH 106 90 50 Y1H Y1M Y1H 65 N/V 20 9*53S N/Y N/V N/Y S*531 N/Y HIDH3H OJ N 0U r YDD1IY5A 91 209 HYBSH 109 90 50 Y1H Y1H Y1H 65 4MY 20 9*53S N/V N/Y N/V 9V3Z N/V M YlMIlIYNA ZZ 209 HYNOH IOi* 90 50 Y1M Y1H Y1H 65 4MY ZO v*535 4MY N/V 4MY S*531 4MY HIDH3M OJ N 08 r YlMI1IYNA ti 206 HYNOH ;09 90 50 Y1H Y1W Y1H 65 N' Y ZO I*131 4MY 4MY 4MY S*531 N/Y HISH3H OJ H 08 r YnXIIIYBA 41 ZIO HYNOH 10* 90 50 Y1N VIH VIH 65 N/V 20 9*S3S N/Y 4MY 4MY S'53T N/Y H19H33 03 N OB r Y1MIIIYBA 11 ZTI HYNOH 10* 90 50 Y1N Y1H Y1H 65 N/Y ZO 9*53 S 4MY 4MY N/Y S*531 4MY HIOH3H OJ W 05 r YDDlIYNA 21 ZIZ HYNOH 106 90 50 Y1H Y1H Y1H 65 4MY 20 9*S3S N/Y 4MY eMY S*S3E 4MY HIDH3M 03 H OU F TIMIIIYNA 21 ZTi HYNOH I09 90 SO Y1H Y1H Y1W 65 4MY 20 9*535 4MY 4MY 4MY 9*932 N/Y M YnXIIIYBA ZZ 219 HYNOH ' 109 90 SO Y1N Y1N Y1H 65 4MY 20 9 535 4MY N/Y 4MY 9 932 4MY M YlMIlIYBA 14 ZIS HYNOH 109 90 50 Y1H Y1M Y1H 65 4MY 20 9*S3S 4MY N/V N/Y 5*531 4MY HISH3H OJ H 08 r YDDlITRA li Z19 HYNOH I09 90 50 Y1H Y1H Y1H 65 4MY ZO v*535 4MY 4MY 4MY S*531 4MV HIOH3U 03 H 05 r e C UYGIY1I09GOS3S MYCIY1IOF GOS3S SIA3N SIA3N Y53Y33 90 A3YB I A3YN 9Y3M3801KtO d001-Y33IG3NI 110 AIG5'$* 30B GOS3S 130S 1Hni OP3 A3YM* 033 1Y813 9Y-I* N0133 Cd33IJI30 IIC JOU 3NAI30213NIVI" 0rY1IJI3Y1IOF SHVll 93 I*I X Y33I03N1 d3YM B SnaiV dlitS 93LY( dlnS 90 A3YU 9Y3M0801#tO lIGS* 'M O O O
(3 x._) TABLE 4-1 C7/26/88 SHEET 5 OF 14 TROJAN 84JCLEAR PLANT ENVIROPMENTAL CODOITIONS NORMAL ACCIDENT LOCATICH TEMERATIRE PRES'AJRE edMIDITY RADIN
- PEAA RADIATION 3 EF8 IPSIG3 8%8 E RAlY
- IRADSB BUILDIE ELEV 'tOOM ENVIR MAX M)RM MIN ftAX NORM MIN MAX NORM MIN BKG * '(TEW PRESS HLMID GAP 9tA BETA TADLE 8A-1 REF SFil leer IFB PSIG 8%)
TLEL 77 217 HARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5E5- N/A WA N/A 5.5E; WA HIGHER OF M OR J AIDCILIARY 77 218 HARSH 104 to 50 ATM ATM ATil 95 WA 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J FUEL 77 270 HARSH 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 WA N/A WA 5.5E3 WA HIGHER (J M OR J AUXILIARY 93 221 MARSH 104 80 50 ATM ATM ATM 95 N/A 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J AUXILIACf 93 222 HARSH 104 80 50 ATM ATM ATM 95 N/A 20 1.1E3 N/A N/A N/A 5.5E3 WA HIGHER OF M OR J AuKILI ARY 93 223 MARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5ES WA WA WA 5.5E3 N/A HIGHER OF M OR J AuKILIARY 93 224 MARSH 104 80 50 ATM ATM ATM 95 N/A 20 4.5ES N/A WA N/A 5.5E3 N/A HIGHER OF M OR J AuKILIARY 93 225 MARSH 104 80 50 ATM ATM ATM 95 WA 20 6.6E3 WA N/A WA 1.1E7 WA G AuKILIARY 93 226 HARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5ES N/A N/A N/A 1.1E7 WA C CHLORIIE 45 397 MILD 104 WA 50 ATM ATM AIM 95 N/A 20 5.0E2 WA WA WA 4.0E2 WA FOOTNOTE D CHLORINE 45 398 MILD 104 WA 50 ATMlATM ATM 95 WA 20 5.0E2 N/A WA WA 4.0E2 N/A FOOTNOTE D CHLORINE 45 400 ftILD 104 N/A 50 ATM ATM ATM 95 N/A 20 5.0EZ WA N/A N/A 4.0E2 N/A FOOTNOTE O CONTAIfetENT 33 <53 ISSF HARSH 120 110 50 60 ATM -1.1 100 N/A 20 2.2E 7 303 66 100 6.5E7 2.1E7 D' AND D CONTAlfGEENT >=53 ISSA HARSH 120 110 50 60 ATM -1.1 100 WA 20 2.2E7 303 66 100 3.3E7 1.4E8 A AND C CONTAIt#ENT 33 <53 08SF HARSH 120 110 50 60 ATM -1.1 100 N/A 20 1.0E7 303 66 100 6.5E7 2.1E7 D' AND D CONTAIIetENT 53-93 0835 HARSH 120 110 50 60 ATH -1.1 100 WA 20 1.0E7 303 66 100 3.3E7 1.4E8 A AND C CONTAlfGENT >93 OrSA MARSH 120 110 50 60 ATM -1.1 100 N/A 20 1.0E7 303 66 100 1.3E 7 1.4E8 8 AND C CONTAIpetENT <130 PRZR HARSH- 145 130 50 60 ATM -1.1 100 N/ta 20 2.2E7 303 66 100 3.3E7 1.4E8 EHIGH A, 8) &C i e RADIATION DOSES CIVEN ARE 40 YEAR SACKGROUW TIDS. 3 R4 IATION DOSES GIVEN ARE 1 YEAR POST-ACCIDENT TIDS. FOR DOSES LESS THAN ONE YEAR,'IE TABLE 84-1. NOTE: SPECIFIED TID FOR ENVIROPMENTAL QUALIFICATION SHALL BE 1.1 X ACCIDENT PEAK (GAtttA PLUS BETAl PLUS 40 YEAR BACKGROUND TIDS. 33 EQUIPPENT LOCATED BELON POST-LOCA FLOOO LEVEL.
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"--$C7/ W d8 SHEET 6 OF 14 c TROJAN PUCLEAR PLANT EfWIROt#1 ENTAL COtJDITIONS co u m
30RitAL ACCIDENT LOCATIO4 TEMPERATURE TRESSURE M tIDITY RADTN e PEAK RADIATION a IF) 4PSIG5 8%I IRADSB IRADSB EiUILDIIG ELEV ROOH [tWIR HAX 30Rit MIN ttAX NORit HIN ttAX ICRM MIN BEGRND TEMP PRESS HlatID GAtt1A BETA TABLE 8A-1 REF IFT8 t#ER IFI PSIG E%B T DF4 TROL 45 01 HILD 104 75 50 ATM ATH ATM 95 <50 20 5.0E2 tVA PVA WA 4.0E2 IVA FOOT:JOTE D cot 4 TROL 45 02 ttILD 104 75 50 ATM ATM ATM 95 <50 20 5.0E2 IVA PUA tVA 4.0E2 PUA FOOTra0TE O CO4 TROL 45 03 HILD 104 75 50 ATH ATH ATH 95 <50 20 5.0E2 tVA PUA WA 4.OE2 WA FOODJOTE D CO4 TROL 45 04 ttILD 104 75 50 ATM ATH ATM 95 <50 20 5.0E2 WA WA WA 4.0E2 PUA FOOTIJOTE D CO4 TROL 45 05 HILD 104 75 50 ATH ATH ATH 95 <50 20 5.0E2 WA WA WA 4.0E2 WA FOOTNOTE D 004 TROL 45 06 HILD 104 75 50 ATM ATH ATH 95 <50 20 5.0E2 WA PUA tVA 4.0E2 tuA FOOTt0TE D COtiTROL 45 07 f1ILD 104 75 50 ATM ATH ATtt 95 <50 20 5.0E2 WA tVA PUA 4.0L2 tuA FOOTIOTE D CalTROL 45 08 HILD 104 75 50 ATM ATM ATH 95 <50 20 5.0E2 tUA PUA WA 4.0E2 tuA FOOTIJOTE D C04 TROL 45 09 ttILD 104 75 50 ATH ATH ATM 95 <50 20 5.0EZ IVA WA PUA 4.0E2 PUA FOOTIOTE D CONTROL 45 10 HILD 104 75 50 ATH ATM ATH 95 <50 20 5.0E2 PUA WA WA 4.0E2 PUA FOOTNOTE D cot 4 TROL 45 11 ttILD 104 75 50 ATH ATM ATM 95 <50 20 5.0E2 WA WA WA 4.0E2 WA FOODJOTE D CG4 TROL 45 12 ftILD 104 75 50 ATM ATH ATM 95 <50 20 5.0E2 PUA PUA WA 4.0E2 PUA FOODJOTE D cot 4 TROL 45 13 ftILD 104 75 50 ATH ATH ATH 95 <50 20 5.0E2 WA WA WA 4.0E2 WA FOODOTE D cot 4 TROL 45 14 ftILD 104 75 50 ATH ATH ATM 95 <50 20 5.0E2 PUA WA PUA 4.0E2 WA FOODOTE D CONTROL 45 15 HARSH 104 75 50 ATM ATH ATH 95 <50 20 1.1E3 tUA tVA tVA 4.0E2 WA FOOTtJOTE D CalTROL 45 16 HARSH 104 75 50 ATH ADt ATM 95 <50 20 1.1E3 WA WA PUA 4.0E2 WA FOOTFOTE D cot 4 TROL 45 17 HARSH 104 75 50 ATH ATH ATM 95 <50 20 1.1E3 WA WA WA
- 9E2 PVA FOOTtJOTE D CONTROL 45 IS HARSH 104 75 50 ATM ATH ATM 95 <50 20 1.1El WA FUA tVA 4.0E2 WA FOODOTE D e RADIATIOtt DOSES GIVEN ARE 40 YEAR BACKGROLND TIDS.
3 RADIATION DOSES GIVEN ARE 1 YE AR POST-ACCIDENT TIDS. FOR DOSES LESS THAN ONE YEAR. SEE TABLE 8A-1. NOTE: SPECIFIED TID FOR EtWIROt:1Et4TAL (JUALIFICATION SitALL BE 1.1 X ACCIDENT PEAK (GAtt1A PLUS BETAl PLUS 40 YEAR BACKGROL20 TIDS. m W O O O
V V U TABLE 4-1 C7/26/88 SHEET 7 OF 14 TROJAN t0 CLEAR PLANT EtWIROt&1 ENTAL C0t4DITIONS IJORMAL ACCIDENT LOCATIO4 TEMPERATURE PHL"'ZURE BRktIDITY RADIN
- PEAK RADIATIOti 3 8F3 (PSIG) 8%8 IRADSB (RADS)
EUILDING ELEV ROOM EtNIR MAX NORM l MIN MAX ICRit MIN MAX NORM MIN BKGRt4D TEMP PRESS tRhiID GAtttA BETA TABLE 8A-1 REF IFTI t#BR IF5 PSIG 8%8 004 TROL 45 19 IEfl 104 75 50 ATM ATM ATM 95 (50 20 1.1E3 WA WA WA 4.0EZ IVA FOOTt0TE D CO4 TROL 45 20 HARSH 104 75 50 ATH ATH ATM 95 <50 20 4.5ES WA WA WA 4.0E2 PVA FOOTNOTE D C0tiTROL 45 21 HARSH 104 75 50 ATM ATM ATM 95 <50 20 1.1E3 tvA WA PVA 4.0E2 WA FOOTtJOTE D Cot 4 TROL 45 22 HARSH 104 75 50 ATM ATM ATM 95 <50 20 1.1E3 WA tvA WA 4.0E2 tvA FOOTNOTE D cot 4 TROL 45 23 HARSH 104 75 50 ATM ATM ATM 95 <50 20 1.1E3 PVA WA WA 4.0E2 PVA FOOTIOTE D COITROL 45 24 HARSH 104 75 50 ATM ATil ATM 95 <50 20 1.1E3 PVA WA WA 4.0E2 WA FOODOTE D C0t4 TROL 45 25 HARSH 104 75 50 ATM ATM ATM 95 <50 20 4.5ES WA WA WA 4.0E2 WA FOOTNOTE D C04 TROL 45 27 HARSH 104 75 50 ATH ATM ATM 95 <50 20 4.5ES WA PVA PVA 4.OE2 PVA FOOTIOTE D Cot 4 TROL 61 33 MILD 104 75 50 ATM ATH ATM 95 <50 20 5.0E2 WA WA tVA 4.0E2 PVA FOOTIOTE D CD4 TROL 61 34 MILD 104 75 50 ATM ATM ATM 95 <50 20 5.0E2 tVA WA WA 4.0E2 PVA FOOTIOTE D COtsTROL 61 35 MILD 104 75 50 ATM ATM ATM 95 <50 20 5.0E2 WA WA PVA 4.0E2 WA FOOTicTE D Cot # TROL 61 36 MILD 104 75 50 ATM ATM ATM 95 <50 8 5.0E2 PVA WA WA 4.0E2 FVA FOOTIOTE D COITROL 61 37 HILD 104 75 50 ATH ATH ATM 95 <50 20 5.0E2 WA PVA WA 4.0E2 WA FOOTFOTE D CG4 TROL 61 38 HILO 104 <95 50 ATH ATM ATM 95 <50 20 5.0E2 tvA PVA WA 4.0EZ tvA FOOTtJOTE D C04 TROL 65 39 MILD 104 <95 70 ATM ATM ATM 95 <50 20 5.0E2 PVA tvA tvA 4.0E2 PVA FOOTNOTE D COITROL 65 40 MILD 104 <95 70 ATH ATM ATM 95 <50 20 5.0E2 fvA tVA PVA 4.0E2 PVA FOOTNOTE D CG4 TROL 65 del MILD IM <95 50 ATH ATM ATM 95 <50 20 5.0E2 PVA PVA PVA 4.0E2 PVA FOOTNCTE D C04 TROL 77 45 MILD 104 <95 50 ATM ATM ATM 95 <50 20 5.0E2 WA tVA WA 4.0E2 WA FOOTFOTE D
- RADIATION DOSES GIVEN ARE 40 YEAR BACKGRGAD TIDS.
3 RADIATION DOSES GIVEN ARE 1 YEAR *OST-ACCIDEt4T TIDS. FOR DOSES LESS Titud ONE YEAR. SEE TABLE 8A-1. 20TE 2 SPECIFIED TID FOR (NVIROt#1 ENTAL QUALIFICATION SHALL BE 1.1 X ACCIDENT PEAK IGAtt1A PLUS BETAl PLUS 40 YEAR BACKGROlkJD TIDS.
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$ $ C7/26/88 SHEET C OF 1*3 TROJAN PAJCLEAR PLANT EtWIROa1 ENTAL CQ4DITIONS g ".s CD 4 $ NORMAL ACCIDENT LOCATIO4 TEMPERATURE PRE"E.URE HUiTDITY RADIN
- PEAK RADIATION 3 8FI EPSIGI 8%) (RADS) (RADSB E4JILLIIE ELEV ROCH EtWIR MAX NORit MIN MAX NORH MIN MAX IORM MIN BKGkra TEMP PRESS HUMID GAtttA BETA TABLE 8A-1 REF EFT 8 tacR (FI PSIG 4%8 T O4 TROL 77 47 HILD 104 75 50 ATM ATM ATM 95 (50 20 5.0E2 IVA IVA WA 4.0E2 tVA FOOTNOTE D CO4TRCL 93 53 MILD 110 75 50 ATM ATM ATM 95 <50 20 5.0E2 PVA WA tVA 4.0E2 PVA FOOTNOTE D CD4 TROL 93 54 MILD 110 75 50 ATM ATit ATM 95 (50 20 5.0E2 IVA tVA WA 4.0E2 WA FOOTtOTE D CD4 TROL 105 77 MILD 104 WA 50 ATM ATM ATM 95 PVA 20 5.0E2 WA WA WA 4.0E2 PVA FOOTFOTE D ELEC PENETRATION 45-93 358 HARSH 105 80 -5 ATM ATM ATM 100 WA 20 4.5ES PVA PVA WA 4.4E7 tVA K IUEL 45 228 HARSH 1% 80 50 ATH ATM ATM 95 WA 20 1.1E3 WA PVA IVA 5.5E3 tVA HIGHER OF M OR J FUEL 45 229 H UC,H 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 PVA PVA FUA 5.5E3 PVA HIGHER OF M OR J FUEL 45 250 HARSH 104 80 50 ATM ATil ATM 95 WA 20 4.5ES tVA WA WA 5.5E3 tVA HIGHER OF M OR J FUEL 45-77 231 KARSH 10, 80 50 ATM ATM ATM 95 WA 7*. 4.5ES WA WA PVA 4.4E7 PVA K FUEt 45-77 232 HAR",H 104 80 50 ATM ATH ATM 95 WA 20 4.5 5 WA tVA WA 4.4E7 WA K FUEL 45-77 233 HARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5ES PVA WA PVA 4.4E7 IVA K FML 45 234 HARSH 104 80 50 Am ATM ATM 95 tVA 20 1.1E3 WA WA PVA 5.5E3 WA HIGHER OF M OR J FUEL 45 235 HARSH 104 80 50 A.M ATH ATM 95 PVA 20 4.4E4 WA PVA WA 5.5E3 WA HIGHER OF M OR J IUE L 45 236 HARSH 104 80 50 ATH ATM ATM 95 PVA 20 4.4E4 WA PVA PVA 5.5E3 PVA HIGHER OF M OR J FU[L 45 237 HARSH 104 80 50 ATM ATM ATM 95 PVA 20 1.1E3 PVA tVA fvA 5.5E3 PVA HIGHER OF M OR J FUEL 61 190 HARSH 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 tVA PVA PVA 5.5E3 PVA HIGHER OF M OR J fu[L 61 250 HARSH 104 80 50 ATM ATM ATM 95 PVA 20 6.6E3 WA tVA tVA 5.5E3 WA HIGHER OF M OR J FUEL 61 253 HARSH 104 80 SJ ATM ATH ATM 95 PVA 20 6.6E3 WA WA PVA 5.5E3 PVA HIGHER OF M OR J o RADIATION DOSES CIVEN ARE 40 YE AR BACKGROJO TIDS.
O RADIATION DOSES CIVEN ARE 1 YE AR POST-ACCIDENT TIDS. FOR DOSES LESS THAN 04E YEAR. SEE TABLE SA-1. TOTE: SPECI*IED TID FOR EtNIRO31 ENTAL QUALIFICATION SHALL BE 1.1 X ACCIDENT PEAK IGAlttA PLUS BETA) PLUS 40 YEAR BACKGROLkJD TIDS. 0 0 0 - -- - -
7 v TABLE 4-1 C7/2uS8 SHEET 9 OF 14 TROJAN IAJCLEAR PLANT ENVIROPMENTAL COHOITIONS MOL'.tAL ACCIDENT LOCATI(N6 TEIMRATWE PRES 2JRE IRklIDITY RADIN
- PEAK RADIATION a EF8 IPSIG9 8%I IRAOS) ( RAOS I ItUILDING ELEV ROCH [NVIR MAX NORM MIN MAX telel MIN MAX DORM MIN BKGRps TEN PRESS HLMID G4f994 BETA TABLE 8A-1 REF IFT) Deer (F3 PSIG 1%)
FUEL 61 254 HARSH 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J FUEL 61 255 NARSH 204 80 50 ATM ATM ATM 95 WA 20 4.5ES WA WA WA 5.5E3 WA HIGHER OF M OR J FUEL 61 256 HAltSH 104 80 50 ATH ATM ATM 95 WA 70 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J FUEL 61 257 HARSH 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J FML 61 259 HARSH 104 80 50 ATM AT7 ATM 95 WA 20 4.5E5 WA WA WA 5.5E3 WA HIGHER OF M OR J FML 61 260 HARSH 104 80 50 ATM '.fM ATM 95 WA 20 6.6E3 WA WA WA 5.5E3 WA HIGe;ER OF M OR J FUEL 61 261 HARSH 204 80 50 ATM ATM ATM 95 WA 20 4.5ES WA WA WA 5.5E3 WA HIGHER OF M OR J FIFL 77 265 MARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5ES WA WA WA 4.4E7 WA K. FUEL 77 266 HARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5ES WA WA WA 5.5E3 WA HIGHER OF M OR J FUEL 77 267 HARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5E5 WA WA WA 5.5E3 WA HIGHER OF M OR J FUEL 77 268 HARSH 104 80 50 ATM ATH ATM 95 WA 20 4.5E5 WA WA WA 5.5E3 WA HIGHER OF M OR J FUEL /7 269 HARSH IC'e 80 50 ATM ATM ATM 95 WA 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J FUEL 77 271 HARSH 104 80 50 ATM ATM ATM 95 WA 20 1.1El WA WA WA 5.5E3 WA HIGHER OF M OR J l FUEL M 272 HAltSH 104 80 50 ATH ATM ATM 95 WA 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J , FUEL 77 273 HARSH 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J FUEL 77 274 HARSH 104 80 50 ATH ATM ATM 95 WA 20 4.5E5 WA WA WA 5.5E3 WA HIGHER OF M OR J FUEL 77 275 HARSH 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 WA WA WA 5.5E3 WA HIGHER OF M OR J ] FUEL 93 276 MARSH 104 80 50 ATM ATM ATM 95 WA 20 1.1E3 WA WA WA S.5E3 WA HIGHER OF M OR J l{
- RAOIATION DOSES GIVEN ARE 40 YEAR BACKGROtAe TIDS.
3 RADIATION DOSES CIVEN ARE 1 YEAR POST-ACCIDENT TIDS. FOR DOSCS LESS THAN OBE YEAR. SEE TA8LE 8A-1. l NOTE: SPECIFIED TIO FOR ENVIROpeENTAL QUALIFICATION SHALL BE 1.1 X ACCIDENT PEAK IGAtttA PLUS SETA) PLUS 40 YEAR SACKGROLAe TIDS. 1 I_- > c. Om *3 C CL n-
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- TROJAN PJJCLEAR PLANT EtNIRot41 NS ENTAL CONDITIO SHEET 10 OF 14 LOCATION NORMAL ~~
M itA& ~TEPTPlTURr---~ (F# r~FRI55[]RE s PUNIM iy ArcIDENT IPSIG) 4%8 RA N
~iUEL 1 EL F##BR IFTl W TINTlf b 1 #DRM FTtINetur~ I RADS t PEAK !
RAUfAII0t3 a ~ max IRADS) 9F~ 277 FUEL 93 2 78 RIR53T W 80 50
~ATIFWW75 W N NTEM EPRESS { IF8 PSIG (MTM EXB BETA I IAECE8A-1 REa FUEL HARSH 104 80 N/A 20 93 280 HAR$H 80 50 ATM ATM ATM 95 WA 20 6.6L5 1WAW tVA ' $.ht5 fVA FUEL WA 65 ATM 6.6E3 WA IVA HIClifrDTTI N 93 281 ATM ATM 95 tVA WA 5.5E3 PVA FUCL HARSH 104 80 50 50 4.5ES 93 ATit ATM PVA tVA WA HIGHER OF M OR 282 ATM 95 WA 5.5E3 WA FUEL HARSH 104 80 50 20 1.1E3 ATM ATM WA WA HIGHER OF tt OR 93 234 ATit 95 WA WA 5.5E3 HARSit 104 80 20 4.5ES tVA If4TAKE STRUCTURE 10 50 J ATM ATM WA tVA IVA HIGHER OF M OR 395 ftILD ATM 95 tVA 5.5E3 IVA 104 WA 20 4.5ES INTAKE STRUCTURE 23 392 50 ATM ATM ATM 95 tVA tVA PVA HIGHER OF M R ftILD 104 tVA 20 5.5E3 PVA tuA 70 !
ATit 5.0E2 WA , PVA HIGttER OF tt OR INTAKE STRUCTURE 23 393 ATM ATM tVA MILD 104 95 WA 20 4.0E2 PL*A WA 50 ATN 5.0E2 PVA FOOTroTE D INTAKE STRUCTURE 23 394 ATM ATM PVA tVA MILD 104 95 WA 20 4.0E2 WA WA 50 5.0E2 PVA FOOTra0TE D INTAKE STRUCTURE 45 ROOF ATM ATM ATM 95 WA fVA HILD 105 tVA 20 4.OE2 PVA ttS$$ 80 -5 5.0E2 WA FOOTFOTE D 45 149 ATM ATM , ATM 100 WA WA HARSH 104 80 ' tVA 20 4.0E2 PVA MSSS -5 ATM ATM I ATM I 5.0E2 PVA WA FOOTHOTE D 45 350 100 , WA WA 4.0E2 WA MSSS HARSH 104 80 -5 20 4.5ES FOOTIOTE D 44 ATM ATM 227 5 1"1 HARSH 104 ATM 100 PVA 100 5.5E3 WA PtGSS 80 20 4.5ES 45 352
-5 Artt ATM ATM 227 5 100 HIG.tER OF tt OR J HARSH 104 80 100 FVA 20 5.5El tVA ttSSS -5 ATM ATM 4.5ES 227 5 HIGHER OF M OR J 45 435 ATM 100 100 5.5E3 ttSSS HARSH 104 80 tVA 20 PVA
-5 ATM ! ATM 6.6E3 227 5 HIGHER OF tt OR J 45 436 ATM 100 100 5 5E3 qftS$$ ItARSH 104 80 WA 20 PVA 45
-5 A Pt ATM 5.0E2 227 5 HIGHER OF M OR Ji 437 HARSH 104 Artt 100 WA 100 5.5E3 WA l_ 80 -5 20 4.5ES I 227 5 HIGHER OF M OR JI ATM l ATM 100 i
i ATM 100 WA 5.5E3 WA
= i 20 1.1E3 3 RADIATION DUt.,tS GIVEN ARE 40 YEAR BACKGR i ! 227 5 100 HIC..ER OF tt OR J 5.5E3 WA RADIATION POTE: DOSES GIVEN - OUND ARE TIDS.
1 YEAR POST ACCIDE i 1 HIGHER OF M OR J NT TIDS. SPECIFIED TID FOR EtNIROR1 ENTAL trJALIFICATIONFCR A-1. DOSES LESS THAN OPE YEAR, SEEJ T SHALL BE 1.1 X ACCIDENT PEAK (GAtt1A PLUS BET A ? PLUS 40 YEAR BACKGROUND TIO W O 9 9
V' TABLE 4-1 C7/26/88 SHEET 11 OF 14 TROJAN 84JCLEAR PLWT EtNIROpeENTAL CONDITIONS NORHAL ACCIDENT LOCSTION TENERATURE PRESSURE HUNialTV RADTN
- PEAK RADIATION 3 SF8 E PSIG 8 (Z3 (RADSB (RADS)
MNG ENVIR MAX NORM MIN MAX I.ORM MIN MAX NORM MIN BKGRie TEN PRESS IAktID GAtttA BETA TABLE 8A-1 REF
' ELE (71 -{8TX)H 4eSR IF) PSIG 8%I MU -- 59 435 MAEH 104 80 -5 ATM ATH ATM 100 WA 20 5.0E2 227 5 100 5.5E3 WA HIGHER OF M OR J MSSS M j 439 MARSH 1% 80 -5 ATM ATH ATM 100 WA 20 5.0E2 227 5 100 5.5E3 WA HIGHER OF M OR J PCSS 59 4%0 HAEH 104 80 -5 ATM ATM ATM 100 WA 20 5.0E2 227 5 100 5.5E3 WA HIGHER OF M OR J l
# CSS 59 M1 HARSH 104 80 -5 ATH ATM ATM 100 WA 20 5.0E2 227 5 100 5.5E3 WA HIGHER OF M CR J
# CSS 69 442 t%RSH 104 80 -5 ATM ATM ATM 100 WA 20 5.0E2 274 5 100 5.5E3 WA HIGHER OF M OR J MSSS 49 443 HARSH 104 80 -5 ATM ATM ATM 100 WA 20 5.0E2 274 5 100 5.5E3 WA HIGHER OF M OR J PCSS 69 4% HAR".H 1% do -5 ATM ATM ATM 100 WA 20 5.OE2 274 5 100 5.5E3 WA HIGHER OF M OR J PCSS 69 445 MAEH 104 80 -5 ATM ATM ATM 100 WA 20 5.0E2 274 5 100 5.5E3 WA HIGHER OF M OR J PCSS 93 446 HARSH IC4 80 -5 4TM ATM ATM 100 WA 20 5.0E2 274 5 100 5.5E3 WA HIGHER OF M OR J PCSS 93 447 HARSH 104 80 -5 ATM ATM ATM 100 WA 20 5.0E2 274 5 100 5.5E3 WA HIGHER OF M OR J PCSS 93 448 HARSH 3% 80 -5 ATM ATM ATM 100 WA 20 5.0E2 274 5 100 5.5E3 WA HIGHER OF M OR J PCSS 93 449 HAEH IM 80 -5 ATM ATM ATM 100 WA 20 5.0E2 274 5 100 5.5E3 WA HIGHER OF M OR J PCs 100 446 NAEH 1% 80 -5 ATM ATM ATM 100 WA 20 5.0E2 328 5 100 5.5EI WA HIGHER OF M OR J tcSS 100 447 HAEH 1% 80 -5 ATM ATM ATM 100 WA 20 5.0E2 328 5 100- 5.5E3 WA HIGHER OF M OR J PCSS 100 448 HAEH 104 80 -5 ATM ATM ATM 100 N/A 20 5.0E2 328 5 100 5.5E3 WA HIGHER OF M OR J PCSS 100 449 HACH 104 80 -5 ATM ATM ATM 100 WA 20 5.0E2 328 5 100 5.5E3 WA HIGHER OF M OR J OUTSIDE 45 OUT MILD 105 80 -5 ATH ATM ATM 100 WA 20 5.0E2 WA WA WA 4.0E2 WA FOOTNOTE D AUKILIARY 45 166 HARSH 104 80 50 ATM ATM ATM 95 *t/A 20 4.5ES WA WA WA 5.5E3 N/A HIGHER OF M OR J
# RADIATION DOSES CIVEN ARE 40 YEAR BACKGROUDe TIDS.
3 RADIATION DOSES GIVEN ARE 1 YEAR POST-ACCIDENT TIDS. FOR DOSES LESS THAN ONE YEAR SEE TABLE 8A-1. NDIEt SPECIFIED TID FOR ENVIROpe1 ENTAL QUALIFICATIiJN SHALL BE 1.1 X ACCIDENT PEAK IGAfflA PLtJS BETA) PLUS 40 YEAR BACKGROL.ND TIDS.
- a y
> 13 c a a
o n n o Ch tr _ . = _
m
^ '> ?b gg TABLE C-1 e a C7/26/88 SHEET 12 OF IS ou ~
3 TROJAN PAJCLEAR PLAT 4T EtNIRGt1 ENTAL CONDITIONS
=o an u CJ R30RitAL ACCITANT LOCATIG4 TEMPERATURE PRSSURE HLAtIDITV RADTN
- PEAK RADIATIOt3 a EF8 (PSIG3 8Z8 ERACSI GRADS)
BUILDING ELEV ROOH EtNIR MAX NORM MIN MAX NORM MI'd MAX NORM MIN BKGRFO TEMP PRESS hut 1ID GAttiA BETA TABLE 8A-1 REF EFT 3 ftBR IFR PSIG 8%) PIPE PE14LIMATIG4 45 167 HARSH 104 80 50 ATM ATH ATM 95 WA 20 4.5ES WA WA WA 5.5E3 PVA HIGHER OF M OR J PIPE PENETRATION 45 168 HA3N8 1% 80 50 ATM ATM ATM 95 j WA 20 4.5ES WA WA WA 1.1E7 fuA G PIPE PENETRATION 45 169 HARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5ES WA PVA WA 4.4E 7 PVA K PIPE PENETRATION 45 170 HARSit 104 80 50 ATM ATM ATM *5 WA 20 4.5ES tVA WA WA 4.4E 7 WA K PIPE PEPETRATION 61 189 HARSH 104 80 50 ATM ATM ATM 95 PVA 20 4.5ES PVA FVA WA 4.4E 7 WA K PIPE PEPETRATION 45-61 195 HARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5ES PVA WA PVA 4.4E7 tVA K PIPE PENETRATION 63 185 MARSH 104 80 50 ATM ATM ATM 95 WA 20 4.5ES WA WA WA 4.4E7 tVA K PIPE PEPETRATION 77 219 HARSH 104 80 SC ATM ATM ATM 95 WA 20 1.1E3 WA WA WA 1.1E7 PVA G TURSINE 45 100 HARSH 104 80 50 ATH ATM ATM 95 WA 20 5.0E2 342 50 100 4.0E2 tVA FOOTNOTE D TURSDE 45 101 HARSH 104 80 50 ATM ATr1 ATM 95 WA 20 5.0E2 342 5.0 100 4.0E2 WA FOODOTE D l TURSINE 45 83 MILD 104 WA 50 ATM ATM ATM 95 WA 20 5.0E2 IVA PVA WA 4.0E2 ' WA FOOTNOTE D TUR8IPE 45 84 HARSH 105 80 -5 ATM ATM ATM 95 WA 20 5.0E2 342 5.0 100 4.0E2 WA FOOTIOTE D TUR8INE 45 85 MILD 116 WA 50 ATH ATM ATM 95 WA 20 5.0E2 WA tu A IVA 4.0E2 WA FOOTNOTE D TURBINE 45 86 ttILD 116 WA 50 ATM ATM ATM 95 PVA 20 5.0E2 PVA PVA PVA 4.0E2 WA FOOTNOTE D TURBINE 45 87 HARSH 104 80 50 ATM ATH ATM 95 WA 20 5.CE2 342 5.0 100 4.0E2 WA FOOTNOTE D TURBItE 45 89 MILD 104 WA 50 ATM ATM ATM 95 WA 20 5.0E2 DVA WA WA 4.0E2 WA FOOTIOTE D TURSItE 45 90 MILD 116 WA 50 ATM ATM ATM 95 WA 20 5.0E2 WA WA WA 4.0E2 WA FOOTIOTE D TURBIPE 45 91 MILD 104 WA 50 ATM ATM ATM 95 WA 20 5.0E2 tVA WA WA 4.0E2 WA FOOTtJOTE D o RADIATIG4 DOSES GIVEN ARE 40 YEAR BACKGROL24D TIDS. 3 RADIATION DOSES GIVEN ARE 1 YEAR POST-ACCIDENT TIDS. FOR D0:2S LESS THAta GJE YEAR. SEE TABLE 8A-1. 140TE z SPECIFIED TID FOR EtNIRG21 ENTAL QUALIFICATION SHALL BE 1.1 X ACCIDENT PEAK E GAtttA PLUS BETA l f* US 40 YEAR BACKGROL2JD TIDS. O O O
/
k y w) w TABLE 4-1 C7/26/88 SHEET II OF 14 YROJAtt taJCLEAR PLAtJT ENVIR0tt1NTAL CaeITIDG NORMAL ACCILEteT LOCATION TEMPERATURE PRESSURE HtJ1IDITY RAGTN a PEAK RADIATIOta a GFB (PSIG8 (%8 (RADS) (RADSB EUILDIfJG ELEV ROOH EtuIR HAX HORH HIN HAX NORM HIN MAX ICRM HIN BKGRtJD TEMP PRESS HLA1ID GAlt1A BLTA TABLE BA-1 REF GFTl P&DR IFI PSIG (%I TURBINE 45 91 HARSH 104 80 50 ATH ATH ATH 95 WA 20 5.0EZ 342 5.0 100 4.0E2 PVA FOOTNOTE D TURSINE 45 94 HARSH 104 80 50 ATH ATM ATM 95 PVA 20 5.0E2 342 5.0 100 4.0E2 FVA FOOTIJOTE D TUR3INE 45 95 HARSH 104 80 50 ATH ATH ATM 95 tVA 23 5.0E2 342 5.0 100 4.0E2 PVA FOOTIOTE D TURBIPE 45 96 HARSH 104 80 50 ATM ATH ATH 95 tVA 20 5.0E2 342 5.0 100 4.0E2 Ne A FOOTt0TE D TURBItJE 45 97 HARSH 104 80 50 ATil ATH ATM 95 PVA 20 5.bE2 342 5.0 100 4.0E2 PVA FOOTroTE D TURBIFK 45 99 HARSH 104 80 50 ATtt ATM ATtt 95 tVA 20 5.0E2 342 5.0 100 4.0E2 tVA FOOTtJOTE D TURBIFE 61 102 HARSH 104 80 50 ATH ATM ATH 95 PVA 20 5.0E2 342 5.0 100 4.CE2 PVA FOOTFOTE D TURBItJE 61 104 HARSH 104 80 I 50 ATH ATH ATM 95 PVA 20 5.0EZ 342 5.0 100 4.0E2 IVA FOOTIOTE D TURBIPE 61 105 HARSH 104 80 50 ATM ATit ATH 95 tVA 20 5.0E2 342 5.0 100 4.0E2 WA FOOTNOTE D TUR81tE 61 106 HARSH 104 80 50 ATM ATit ATH 95 WA 20 5.0E2 342 5.0 100 4.0E2 PVA FOOTNOTE D TURSIPE 61 109 ftILD 104 WA 50 ATH ATH ATH 95 DVA 20 5.0E2 PVA tVA PVA 4.0E2 tVA FOOTIOTE D TURSIPJE 63 103 HARSH 104 80 50 ATH ATM ATM 95 WA 20 5.0E2 342 5.0 100 4.0E2 WA FOOTtJOTE D TURBIPE 69 107 ttILD 104 WA 50 ATH ATH ATH 95 WA 20 5.0E2 PVA WA WA 4.0E2 PVA FOOTtCTE D TURBIPE 69 108 HARSH 104 80 50 ATM ATH ATH 95 tVA 20 5.0E2 342 5.0 100 4.0E2 WA FOOTt0TE D TURBINE 93 113 HARSH 104 80 50 ATH ATH ATH 95 tVA 20 5.0E2 342 5.0 100 4.0EZ IVA FOOTIOTE D CO3TAltt1ENT PVA CSL1
- HARSH 145 WA 50 60 ATH -1.1 100 PVA 20 2.2E7 303 66 100 6.5E7 1.4E8 C Af4D D PCSS fvA CBL2
- HARSH 116 WA -5 ATH ATH ATM 100 PVA 20 4.5ES 328 5 100 5.5E3 WA HIGHEP OF M OR J OUTSIDE PVA CBL3
- HARSH 105 80 -5 ATH ATH ATM 100 DVA 20 4.5ES N/A WA PVA 4.4E7 WA K o RADIATIG4 DOSES GIVEN ARE 40 YE AR BACKGROLRS TIDS.
3 RADIATIOri DOSES GIVLN LRE 1 YEAR POST-ACCIDENT TIDS. FOR DOSES LESS THAN DE YEAR. SEE TABLE 8A-1. TOTE: SPECIFIED TIO FOR Et#IRastENTAL QUALIFICATI0ri SHALL BE 1.1 X ACCIDENT PEAK (GAf ttA PLtG BETAl PLUS 40 YEAR BACKGROUND TIDS. e THESE DEVICES ARE LOCATED IN P10RE THAN GJE AREA OF THE PLAT 4T. EtNIRGJHEt4TAL 50tJDITIOG ARE MADE UP FR0tt A SET OF HORST-CASE PARAt1ETERS. SEE NEXT PAGE FOR DEFINITIGG OF THESE DEVICES. ~ m ;p
>a ce OQ 3 C Q.
48 U es a W vt n CD 4,n as @ . v
J l TA3tE C-1 l C7/26/88 SHEET 14 OF 13 gg cu TROJAte #8JCLEAR PLANT D4/IRGi#1 ENTAL cot 4DITIOtG
$ ct PORMAL ACCIDENT 1 o I"o LOCATION M ENITORE PRESSURE HLhIDITY RADTN e PEAK RADIATIOt3 a l
y % IFS IPSIGs EZB ERADSB tRADS9
$w c3 LUILDINF,
- ELEV IFil ROCH tar,R DUIR HAX t#RH HIN MAX IKDh HIld HAX IORM ' HIN MGRf4D TEHP EFI PDESS ' Htk1ID GAtttA PSIG EX)
BETA TABLE 8A-1 REF ALI6 FUEL .CG4 TROL WA CBL4 e HIR5H 104 80 50 ATH ATH ATH 100 IVA 20 4.5E5 tVA PC 7UA 4.4E 7 tVA K CHLORDE, INTAKE WA CBLS e t1ILD 116 WA -5 ATH ATH ATM 100 tua 20 5.0E2 fuA tVA PVA 4.0E2 tVA FOOTt40TE O TURBItE WA CBL6 + HACH 116 80 -5 ATH ATH ATH 95 tua 20 5.0EZ 342 5.0 100 4.0E2 PVA FOOTNOTE D l tua WA LTG e HAEH 116 WA -5 ATH ATH ATH 100 #FA 20 4.5ES tuA WA WA 5.5E3 tuA HIGHER OF M OR J l l HORST-CI.SE WA CBL e HACH 145 150 -5 60 ATH -1.1 100 PVA 20 2.2E 7 342 66 100 6.5E7 1.4E8 C AND D HOET-CASE WA SEAL e HARSH 145 WA -5 60 ATH -1.1 100 WA 20 2.2E7 303 66 100 3.3E7 1.4E8 A A140 C FORST-CASE WA TAPE e HARSH 104 80 50 ATit ATH ATH 100 WA 20 4.5ES WA WA WA 4.4E7 tUA K
- RADIATTON LOSES CIVEN ARE 40 YE AR BACKGROL24D TIDS.
O PADIATIOr4 DOWS CIVEN ARE 2 VEAR POST-ACCYDEf4T TIDS. FOR DOSES LESS TetAre Or4E YEAR. SEE TABLE 8A-1. tof it SPECIFIED TID FOR EtN1 rot:1 ENTAL QUALIFICATIG4 *.JiALL BE 1.1 X ACCIDENT PEAK (Gaff 1A PLUS BETA l PLtG 40 YEAR BACKGRout40 TIDS.
- THESE DEVICES ARE LOCATED IN HORE THAM DJE AREA OF THE PLANT. UNIROttiDITAL CG4DITIOtG ARE MADE UP FRON A SET OF HORST-CASE PARAt1ETERS.
DEFINITIQ4 FOR THESE DEVICIS ARE AS FOLLONS: CBL1 = At# MIRE ItGIDE CD4TAlltENT. CBL2 = ANYtatRE IN tGSS. G.L3 = ArnN:tRE OUTSIDE CG4TAlt2ENT EXCEPT FOR PGS IINCLUDES CABLE Rtit6tG OUTSIDE OF PLAT 3T BUILDItGl. CBL4 = IfGIDE BUILDIfGS OIHER THAN PCSO/CG4TAIf41ENT. EBL5 = CetLORIt4 CUILDItG. INTAKE STRUCTURE. CBL6 = TURB1t4E BUILDIfJG C8L = DOIGT-CASE ArnlatRE F08t CA8L2. SE AL = HORST-CASE APClatRE. TAPE = HORST-CASE OF THE FOLLQ4ItG ROOMS: 1) RHR, 2 8 SATETY INJECTIOd. Il CG4TAlt#1ENT SPRAY, 4) CENTRIFUGAL CHARGItG PUHP. 0 0 0 - - --
Figure 5-2 provides an overview of the review procedure for qualifying g new and replacement equipment. 5.1.2.3 Nonconforminst Equipment In cases where an engineering review identifles that a piece of equip-l ment important to safety is not environmentally qualified in accordance b' with the criteria of Items 1 through 4.b of * ..lon 2.2, corrective 4 action is initiated in accordance with the guidelines of Nuclear ] Division Procedure (NDP) 600-0, "Corrective Action Programs" . m If the problem is a minor documentation deficiency or affects equip-ment in only one train of a safety system, a Noaconformance Report (NCR) is processed in accordance with NDP 600-1, "Control of Nonconforming Materials, Parts, and Components" . NDP 600-1 , establishes the measures for the identification, documentation, and - n control of nonconforming materials, parts, and components and provides U! for the documentation and verification of the resulting corrective action. If the problem affects redundant trains of a safety system, I an Event Report (ER) is processed in accordance with NDP 600-3, "Event l Reports" . NDP 600-3 is a higher level corrective action program i used to document and correct significant environmental qualification
^
problems. Both NDP 600-1 and NDP 600-3 are used to determine the 3 operability of equipment with an environmental qualification problem, establish plans and schedule ~ for correcting the problem, and document ; justification for continued operation. Equipment qualification prob-lems are also evaluated for reportability, in accordance with the , guidelines of Generic Letter 88-07, by using NDP 600-1 or NDP 600-3. 1 ^! , f f
).2 REVIEW OF ELECTRICAL EQUIPMRNT IN MILD ENVIRONMENTS ;
l Environmental qualification of electric equipment located in a mild
^
environment (defined in Sections 3.3 and 4.0) is not included within i
- the scope of 10 CFR 50.49. In general, this means that electric equipment in mild environments are not required to be environmentally qualified by type testing.
- O 5-7 Amendment 5 (August 1988) i
..,---, - ., _ , , . _ , , _ , _ ., _ _ _ - - _ - ~ - . . , , --
Existing Plant equipment in mild environments is considorod to be already qualified on the basis of operating experienco and current Plant proceduros. This is becauso equipment failures occurring in normal environments have proved to be generally random in naturo and are identified and corrected in accordance with existing Plant mainto-nance, inspection and testing programs. Critical equipment (eg, in control room) is also protected against off-normal environments by redundant, cmergency powered heating, ventilating and air conditioning systems. For new Plant equipment, the requirements of 10 CFR 50 Appendices A and B are considered sufficient to ensure adequato performance of g electric equipment important to safety located in a mild environment. Design or purchase specifications will contain a description of the funettonal requirements and the specific environmental conditions dur-ins nonnal and abnormal conditions. Existing Plant survoillanco/ maintenance programs and periodic testing will also encuro that such equipment will perform its specified safety function during its anti-cipated installed life. 5.3 REVIEW OF OTHER EQUIPMENT SUBJECT TO O ENVIRONMENTAL QUALIFICATION _ As discussed fn Section 3.4, cortain post-accideat monitoring instru-mentation located in a harsh environment and installed in accordance with NUREG 0737 requirements was not initially subject to environ-montal qualification review. This instrumentation includes the Post-Accident Sampling System, the noblo gas offluent monitors, and the iodino and particulato sampilns capability. The environmental quali-fication requirements applicable to thoso instruments is sutt.narized in Tablo 3-4. The following approach has been taken for reviewing tho environmental qualification of tho subject equipment: l (1) Regulatory Guido 1.97 Category 3 design and quellfi-cation critoria is applied to the subject equipment. Gl
'~0 Amendment 4 (August 1987) l
^ i' (8) TID = 1.1X(4.4E7) & 4.5ES rads = 4.9E7 rads. Dl
)
(9) Calculated TID less than rated TID, therefore the equip-ment meets qualification standards. I i i l l l l f l 1 i l 1 1 -l BA-9 Amendment 5 (August 1988) j l
TABLE 8A-1 07/26/88 CALCULATED TROJAN TOTAL INTEGRATED DOSES lEl Y ANO 8 IRADSI ACCIDENT DOSE FIRST FIRST FIRST FIRST FIRST q LEVELS - It4 SIDE CONTAf tMENTt HRf A I DAYiAI HEEKfAl HONTHf A I YRfAl (Al LOCA, Y DOSE, BELOH EL 93 FT 1.4E6 7.!E6 2.0E 7 2. 7E 7 3.3E7 IB) LOCA, Y DOSE, AB0VE EL 93 FT 1. 7E 6 5.5E6 1.0E 7 1.3E7 1.3E7 (Cl LOCA, 5 AIR DOSE. 8.1E6 4.6E7 9. 6E 7 1.4E8 1.4E8 IIHFINITE CLOUDHB1 IDI LOCA 00$f TO COMPONENTS IN CONTACT HITH REACTOR COOLEPR CONTACT B DOSE 2.7E5 2. 7E 6 1. 0E 7 1.3E7 2.1E 7 CONTACT Y DOSE 1.4E6 7.1E6 2.0E7 2. 7E 7 3.3E7 (D'l LOCA, Y DOSE TO SUBHERGED 1.0E6 1.0E7 3.3E7 4.6E7 6.5E7 COMPONENTS lEl INTACT RCS, Y DOSE, BELOH 7. 7E S 4. 7E 6 1.2E7 1.7E7 2. 3E 7 EL 93' INTACT RCS 8 ANO Y DOSE WA WA WA WA WA A80VE EL 93' IFl IttTACT RCS DOSE To COMPONENTS IN CONTACT HITH RE ACTOR C00 LENT: CONTACT B DOSE 3.4E6 2.4E7 7. 5E 7 9. 9E 7 1.5E8 CONTACT Y DOSE 4.7E6 2.9E7 7.6E7 1.0E8 1.4E8 ACCIDENT DOSE _ LEVE LS - CUTSIDE CONTAINP*ENT:
' 101 LOCA, Y DOSE, AREAS DIRECTLY 1.8E 5 1.8E6 6.2E6 4.4E6 1.1E7 EXPOSED TO HIGH SOURCE i l tCROSSHATCH11C1 !
IHI LOC A 00SE TO CCt*PONENTS IN CONTACT HITH REACTOR C00 LENT: , CONTACT S DOSE 2.7ES 2. 7E 6 1.087 1.3E7 2.1E7 l CONTACT Y DOSE 1.4E6 7.1E6 2.0E 7 2. 7E 7 3.3E7 j t ] (J) LOCA Y DCSE ALL OTHER AREASIDI 7.6El 7.7E2 3.1E3 4.1E3 5.5E3 l IKI INTACT RCS, Y DOSE. AREAd 1. 5E 6 9.0E6 2. 3E 7 3.2E7 4.4E7 l DIRECTLY EXPOSED TO HIGH SOURCE 1 ICROSSHATCHitC) IL) INTACT RCS DOSE To CCNPONENTS IN CCNTACT HITH REACTOR C00LEt# CONTACT 8 00*E 3.4E6 2.4E7 7.5E 7 9.9E7 1.5E8 CONTACT Y DOSE 4.7E6 2.9E7 7.6E 7 1.0E8 1.4E 8 (M) INTACT RCS, Y COSE, ALL OTHER 1.6E2 1.1E3 2.9E3 3.9E3 5.5E3 AREASIDI i BACFG800No DOSE LEVELSTt g (H) Y BACKCRCta.0, !>GIDE CONTAINMENT: OUTSIDE 8!0$HIELD 1. 0E 7 ! INSIDE BIOSHIELD 2. 2E 7 101 Y BACKGROUND, CUTSIDE i CCHTAIPetENT 2CCE I 5.0E2 ' 3 ZONE I! 1.IE3 1 ZONE !!! 6.6E3 i j ZONE IV 4,4E4 i , Z&lf V ( AND !!e. IIIo.1 Val 4.5ES [ I l ), (Al EQUIPMEt# REQUIRED TO OPERATE BETWEEN 0-1 HR Shout 0 USE THE 1 HR TOTAL INTERGRATED DOSE ITIDie 1 HR TO 1 DAY USE 1 DAY 1 DAY TO 1 NEEK USE 1 NEEKe ETC. , it) SEE FIGURES 8A 11 AND SA 12 FOR FINITE CLOUD 8 CORRECTION FACTORS. I
; e i ICI SEE FIGURES 8A 1 THROUGH 4A-10 FOR IDENTIFICATION OF CROSSHATCHED AREAS OUTSIDE CONTA!te1ENT. ;
! IDI INCLUCES THE FOLLONING ARE AS THAT ARE NOT CROSSHATCHED: AUXILIARY SUILDIPM. FUEL DUILDIPC, f MAIN STE AM !AJPPORT STRUCT1.FRE e PIPIPG F ACADE ARE A e AND ELECTRIC AL PENETRARION ARE A. FOR ALL REMAINING ARE AS OUTSIDE CONTA!Pf9ENT, USE 4Et aAD PCST* ACCIDENT DOSE REGAROLESS OF POST-ACCIDENT , f EXPOSURE TINE. I
! (E) DO NOT Ust TABLE 8A 100SES FOR LOC ATIONS IN THE RE ACTOM VtSSEL, REACTOR VESSEL AMAJLUS ANO !
. UPPER RE FUELIP4 C AVITY. Cat #ACT THE PA>CLE AR SAFETY AND REGULATION DEPARTMENT FOR DOSE EVALUATION. SEE TA8LE SA 2 FOR A LIST OF DOSE EVALUATI0tes. Amendment 5 0 1 (August 1988) i ]
. . .____m _ . _ _ _ _ _ . . ._.___m.-.__. _ . _ , . _ - _ _ , _ . _ _ . . . . - _ _ _ _ . _ _ . . _ _ . __ _ -._. .._. __ . _ - . __ . _ . . .
i e l l - Pap i d 4 taste SA-2 REVltW OF TOTAL 13elEGRAILD DOSE CALCULAll0N5* INP Approval i _ No. aate . r_-_t location Dose Assigned Comments 82-IF 05/08/94 Hydrogen nonitors C-4004, 93'e1. A 9.37E5 Rads c-4os Aas A u. side. C-4o0A h. 220 s 3.72t4 Reds C-400s, 77 et. A m. side. #-yr. sackyound . 30 days
- m. 270/200 Post-Accident 82-26 08/17/82 Resistance on the 31 in. I.D. Not Leg Outside surface of 31 in. pipe Temperature Reactor Coolant Systen (RL5) INTACT 3.63E7 R l Detectors (RID) Pipe and the 2 in. RIO mai- LOCA 5.17E7 a fold bypass line Inside surface of 31 in. pipe INTACT 2.24E8 R LOCA 1.19ES R S
Centerline of 31 in. pipe INTACI 4.39ES A LOCA- 2.32[8 R Outside surface of 2 in. line INTACT 3.12E7 R LOCA 3.85E7 R , Inside surface of 2 in. line INTACT 3.47E7 R LOCA 4.62E7 R Calculations completed prior to issue date of PGE-1025 (July 1982) are not included. ' SN c. a 3 o 5 _ _ _ _ _ _ . _ . - _ _ . _ . __..___m. _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ -- . , _ _ _ m - - ~ . , , ,-._, ,,- ,.,, - . ,.- _,_-.___. _m3,, ._. r m e-~~-w r - > - - w - - w - y
Page 2 of 4 A ?I IA81E 8A-2 c* 7a
- 8:s G"* TM* Approval No. Date Corrponent location _ Dose Assignad Cmunents 83-3F 05/08/84 Component Cooling Piping Facade LIS-3216 and L15-3217 1.54E5 Rads Water surge Tank CV-10014 and CV-10015 limit Level Switches switches 5.9E4 Rads and Valve Limit Switches 84-21 05/14/84 Residual Heat Aux. Bldg. 5*el. 5.0E6 R Reinoval (RIIR)
Ptsp Motor Containment Spray Aux. Bldg. S'el. 9.3E5 R (CS) Pupp Motor Safety injection Aux. Bldg. S*e1. 1.7E6 R (51) Ptsrp Ntor Centrifugal Charging Aux. Bldg. 25'el. l.4E6 R Ptsrp (CCP) Motor 84-22 05/02/84 Containment 45*el. Electrical 1-yr. Post-LOCA + 40-yr. bkgd. Penetrations Penetrations Area Maxiansa 1.0E8 R AI & BI-1,3,&5 84-24 05/15/84 various Containment i Hour 1.06E6 R superceded by INP-84-43 Caponents Sutunerged in Sump I Day 1.06E7 R 1 Week 3.3E7 R 4 Weeks 4.7E7 R 1-Yr. 6.6E7 R LOCA doses without background O O O
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Page 3 of 4 TACsE 8A-2 Tur Approval No. Date Component location Dose Assigned Cauments M-28 05/11/84 Terminal Block Pipe Facade 1-yr. + 40-yr. bkgd. Lifetime qualified dose of ATS-466 66*el. INIACI 8.905 Rads terminal block AIB-466 is i LOCA 1.1Et Rads 3.8E7 Rads. l 84-31 08/20/85 Various various Bases for TID Values used in PGE-1025. 84-43 08/09/84 Various submerged in Containment Point A Point 8 Time for Barton Transmitters to Samup 1 Hour 1.1[6 Rads 1.0[6 Rads reach a total integrated dose of 1 Day 1.1E7 1.0E7 5.3E7 Rads is 12 weeks. I Week 3.4E7 3.3E7 4 Weeks 4.9E7 4.6E7 1-Yr. 6.9E7 6.4E7 86-16 04/08/86 various Next to the Reactor 2.26E11 Rads Neutron TID of TNP 86-16 is Detectors Pressure Vessel 1-yr. post-accident + 2.1E11 Rads. 40-yr. bkgd. SE-32 07/24/86 MD 8923 Ass, 5*el. Aux. Bldg. 6t6 Rads 8807 A48 1-yr. Post-LOCA 40-yr. bkgd. 86-33 07/24/86 MD 8809 A88 45*el. Pipe Facade 8.7[6 Rads 1-yr. Post-LOCA 40-yr. bkgd. 86-34 07/24/96 710 8804A, 8816A 5*el. Aux. Bldg. SE6 Rads and 8024 1-yr. Post-LOCA 40-yr. bkgd. S$ i 0&
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i i 1 ! i APPENDIX 8.C l \ ~ I, i > I r
+
l TilERMAL-HYDRAULIC ANALYSIS _1 l OF HI. Cit-ENERGY LINE BREAKS Im ! IN Tite TURB1NE BUILDING is
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I, i I i i 1 l. ) i ! I i i l 1 , l l 6 i l l t i T l i l l ! i ! { i l l l 1 l l l i Amendment 5 (August 1989)
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i 1 j 1.0 INTHODUCTION AND BACKGROUND i ! This appendix describes the thermal-hydraulle analysis of high energy 3; line breaks (HELBs) in the Trojan Turbine Building. ! l The analysis predicts the accident environments in the Turbine j Building, resulting from a HELB, for the purpose of environmental j qualification of equipment important to safety. The HELBs evaluated ] for equipment qualification in the Turbine Building are full and 3 j 4 . I partial area main steam line breaks (MSLB) and a full area main ! ) feedwater line break (MFLB). I 7l
~
i ! i This analysis was performed in response to a Westinghouse i' i notification. Westinghouse letter POR-84-573, dated June 6, 1984, and i
^
NRC Information Notice 84-90, Main Steam Line Break Effect on 3 , gnvironmental Qualification of Equipment, that identifled a potential l defleiency in the analyses of HELBs outside Containment for I i i r Westinghouse plants. l i O During review of the Westinghouse methodology for calculating mass i ! and energy releases for postulated MSLB accidents, the NRC noted that I 3 Westinghouse did not account for steam generator tube bundle uncovery [ and the associated superheating of the steam. The original Trojan ! j HELB analyses completed in 1975, and the resulting effects on equip- ; ment, were based on a saturated steam environment. l ,
- et The Westinghouse Owners Group (WOC) fomed a subgroup to address the superheated blowdown issue. The subgroup contracted with Westinghouse to perfom superheated blowdown analyses and provide implementation I guidelines so that new Plant-specific HELB evaluations could be per-f o med . f l !
i i i
; in October 1985. Westinghouse issued WCAP-10961 Revision 1 '
l "Steamline Break Mass / Energy Releases for Equipment Environmental i { Qualification Outside Containment". WCAP-10961 provides MSLB mass [ !O ! l 8C-1 Amendment 5 j (August 1988) {i l ' 1 i i [ 1 ,
and energy release data, including applied assumptions, to be used for Plant-specific analysco. It was subsequently determined that this blowdown data did not accurately portray the first second of the full acea break transient. PGE contracted with Bechtel to provide
^ additional mass and energy releases for the early portion of the full area MSLB transient .
A multicompartment model of the Turbine Buf.lding was coveloped using the thermal-hydraulle code RELAP4/ NOD 6. Transients utilizing accident assumptions and the blowdown data from Westinghause and Bechtel were run for both MSLBs and NFLBs. Although MFLB blowdown was not part of l the NRC issue, the analysis was performed to update the original analysis and maintain a consistency in the methods of analysis for lI HELBs. l The proceeding sections describe the method of analysis, key assump-tions, results, and conclusions of the HELB evaluation of the Trojan Turbine Building. O 1 l l l l l l l @ l Amendment $ BC-2 (August 1988) l l
)
l b , s 2.0 METHOD OF ANALYSIS AND KEY ASSUMPTIONS I 1 - i A high-energy line blowdown into un enclosed or partially enclosed , A v i space is a complex phenomenon involving fluid flow, heat transfer, and 33 l
- 1 1 themodynamic principles. In order to accurately model the resulting l environments, a thermal-hydraulic computer code must be utilized. The [
- RRLAp4/ MOD 6 computer code was chosen to predict the environmental j conditions of the Turbine Building during and fol- lowing a f
! high-energy line break (HELB) transient, f i i t Several distinct steps were required for this analysis. These weret l (1) Review of the Turbine Buildina. high-enorry olpe j l locations. and safety-related eculement loestlan_3,. n l This task required that the Turbine Building be I l thoroughly investigated. Compartment sizes and *Jnt 7
; paths were calculated. Pipe break locations were
- i 1 +
identified for both the main steam line and main feed-- j water line, i ! (2) Construction of the RELAp4/ MOD 6 model of the Turbine i [ Buildina. Based upon the review performed in ( l paragraph 1 above, a themal-hydraulic model of the f Turbine Building was developed. This task included f calculation of loss coefficients for fluid flow paths, f t I flow areas. Choking criteria were chosen in accordance : with the NRC Standard Review Plan . i [ t I (3) RELAP4/M006 blowdown input for both the main steam line l ( j kreaks (MSLB) and the main feedwater line break '$ i t j iMFLB). Conservatlye mass and energy release rates for l each of the subject HELBs were provided by Westinghouse I d and Bechtel *
. 7f
! l t ' t (4) Execution of the computer simulation for each HELB. A computer simulation was perfomed for both the MSLBs and i} 8C 3 Amendment 5 l (August 1988) i
h the MFLB. Time step size was chosen to provide short term and long-term pressure and temperature histories. Service conditions for each Turbine Building compartment were obtained. A detailed discussion of this analysis is provided below.
2.1 DESCRIPTION
OF TifE FURBIllE BUILDING RELAP4 / MOD 6 MODEL The Turbine Building contains portions of the four main steam and main feedwater lines that run from each steam generator in the Containment to the main turbine and main feedwater pumps, respectively. The Turbine Building consists of three elevations (floors) that begin at grade elevation (45 feet) and extend to a ceiling elevation of 157 feet, 2 inches. The floor elevations are 45 feet, 63 feet, 69 feet and 93 feet. The Turbine Building can be characterized as large open areas and rooms containing safety-related and other equipment. Hatchways, h ventilation ducts, open areas, the railroad bay and physical barriers with associated failure pressures provide vent paths for steam following an HELB. 1 The main steam and main feedwater lines were evaluated to identify possible break locations. These locations are documented in Reference 3. For the main steam line, the critical break location is the first cibow af ter entering the Turbine Building f rom the Main Steam Support Structure (MSSS). For the main feedwater line, the { break is assumed to occur at the discharge to the main feedwater pump. Figures 8C-1 and 8C-2 show the isometric views of the main steam line and main feedwater lines and their respective break locations. The rooms and open areas of the Turbine Building are represented as volures in the RELAP4/ MOD 6 code. These volumes are nomally defined by physical barriers such as walls or floors but may also be defined by a com.only shared imaginary boundary. Themal-hydraulic exchange A::endme nt 5 BC-4 O (August 1988)
between volumes is via junctions which represent physical passages, 7 failed barriers or open spaces. C The primary RELAP4/M006 model of the Turbine Building consists of h_ ' j 24 volumes and 54 junctions which connect these volumes to one Z another. Additional volumes and junctions were added for the partial area MSLB analyseo in order to provide a better model of the Turbine Building response. These additional volumes and junctions are , associated with the Emergency Diesol Cencrator rooms and are located U ' internal to Volumes U and 18 of the primary model II3I II I. l Figures 8C-3 through 8C-5 illustrate the location of the primary volumes on each elevation in the Turbine Building. As indicated by these figures, most of the volumes have well defined boundaries, such e as walls or floors. In some cases, however, an arbitrary boundary C ,. ilne was chosen either between two Turbine Building regions. These arbitrary boundaries were chosen to separate regions that have ' n i different flow characteristics. Note that only 23 of the primary i$ , volumes represent Turbine Building regions. The other voluma (Volume 13) represents the outside atmosphere, and in tems of j RELAp4/M006 pro- vides the boundary conditions to the problem (ie, the atmosphere is assumed to have a constant thermodynamic state). j I ] The RELAP4/ MOD 6 code also requires information that charactecises flow ( l within a compartment and describes the junctions between compartments. These parameters are straightforward in piping systems, but for the I
- Turbine Building, where the flow path is diverse and the volumes of -
irregular shape and sise, this presents a challenge in modeling. Since the steam from an HELB has significant inertial forces acting on j it and is quite buoyant, equal credit was given for horisontal and vertical flow in calculating compartmental slow areas. Junction data were calculated utilising a modifled inertia equation and "best-
- estimate" exchange areas. Also, the use of loss coefficients was limited between compartments with unobstructed junctions. This proves to be a conservative assumption since energy le not being extracted from the system in these instances . {
{
!O l
i 8C-5 Amendment 5 (August 1988)
The model was constructed to maximize mass and energy dispersion into adjacent compartments, thus exposing as many safety components as possible to accident conditions. 2.2 MASS AND ENERGY BLOWDOWN DATA The RELAP4/ MOD 6 model of the Turbine Building can simulate a HELB only 7 ~' if the mass and energy discharge rates for the break of interest are known. When these are developed, they are input into the RELAP4/ MOD 6 model as a "fill table", which provides mass and energy release rates as a function of time. By specifying the location of the "fill junction" and providing a start signal, denoted by a "trip", the HELS into the Turbine Building can be simulated accurately. {i Tables 8C-1 to 8C-6 provide the blowdown data utilized in the Turbino - Building HELB analysis. This blowdown data was supplied to PCE by Bechtel Corporation and Westinghouse ( , 2i 2.2.1 liAIN FEEDWATER LINE BREAK BLOWDOWN DATA Table 8C-1 depicts the blowdown data developed for the MFLB for use in the RELAP4/M006 model of the Turbide Building. To maximize blowdown, and consequently the impact on the Turbine Building, the following were postulated for the Trojan simulation: (1) Initial condition of the Plant was 100 percent power ^ with the steam generator operating at 112F pounds per square inch absolute (psla). (2) The break is located at the mtin feedwat.r pump discharge as in Figure 8C-2. The break location is represented by Volume 5 in the model. (3) Mass available for blowdown is maximized. A.end:ent 3 BC-6 O (August 1988)
As mentioned above, the blowdown curve developed for the MFLB is extremely conservative. Some of the primary reasons for this are: 1 O (1) A break time of 0.005 seconds to attain a double-ended i 2 guillotine break is assumed. This is unrealistic and } } results in a rapid rise in discharge rate, which in turn adversely impacts the initial pressure rise in
- the break compartment. ,
a w ? t (2) No credit is taken for gradual decompression of the ; .. 1 i affected secondary side piping, which would tend to reduce mass discharge rates. ; 1 (3) Mass available for blowdown has been conservatively maximized. This extends the blowdown duration and f adversely affects the Turbine Building environment. ( I j The slaulation was run for 100.0 seconds. This provided an opportu- , nity to obtain "recovery" characteristics of the Turbine Building f a following blowdown. l 1 i ; i 2,2,2 FULL AREA MAIN STEAM LtWE BRS'AK BLOWDOWN DATA l i Ol
~
l Tables 8C-2 and 8C-3 list the blowdown data for two cases of a full l l area MSLB in the Turbine Building. The data in the Table SC-2 l replaced the data in Table SC-3 for the initial blowdown in order to 13,i i ) determine worst-case pressure effects fo* a full area MSLB. Table Tl 8C-3 was used to predict the worst-case temperature conditions as a 13 ! result of a full area MSLB. IG , 3 i Initial Plant conditions for the full area MSLB are O percent power l (hot standby condition) for maximum pressure effacts, and 102 percent I power for traximum temperature and humidity ef fects. At 0 percent [ t power, the steam generator pressure is at a maximum ( 1125 psig) ! which in turn results in the greatest mass discharge rates. At 102 1 iO 7 BC-7 Amendment 5 j (August 1988) J t - _ _ _ _
{I percent powce, steam generator inventory is at a minimum, this reduces the timo to tube bundle uncovery and, thus, results in maximizing the superhoated steam availablo for blowdown. Using the mass and energy retcaso rates provided in Tables 8C-2 and 8C-3, a "fill table" was ^ constructed for the RELAP4/ MOD 6 cimulation. The computer simulation was executed for 700.0 seconds for the 100 porcent power caso and 100 seconds for the o power case to allow some recovery of the Turbine Building environment to ambient conditions. 2.2.3 PARTIAL AREA MAIN STEAM LINE BREAX BLOWDOWN DATA Tables 8C-4 through 8C-6 list the blowdown data for three cases of a partial area MSLB. The data in these tabics represents blowdown fr a three different sizes of pipe breaks. The worst-caso results f rom each of these separate cases were combined to produce a bounding worst-case temperature profilo. Worst-case pressure ef fects are associated with the full area breaks and therefore were not reevaluated as part of ti.; small break analyses. $1 The initial plant condition for the partial area MSLBs is 102 porcent power for maximum temperaturo and humidity effects. At 102 percent power, steam generator inventory is at a minimum. This reducco the time to tube bundle uncovery and thus results in max!.nizing the superheated steam available for blowdown. Using the mass and energy release rates provided in Tables 8C-4, 8C-5, and 8C-6, "fill tables" were constructed for the RELAp4/ MOD 6 simulation. The computer simulation was executed for 800 seconds to allow for complete blowdown and partial recovery of the Turbine Building environment to ambient conditions. O Amendment 5 BC-8 (August 1998)
i 3,0 RKI.AP4/ MOD 6 COMPUTER SIMut.ATIOl( l Computer simulation of the MSLB and NFLB were executed using the , 1 RELAP4/M006 Turbine Building model described in previous sections. Initial conditions for each transient were: (1) Ambient temperature = 104*F, 95 percent humidity inside and 7; i 91*F. 50 percent humidity outside of the Turbine Butiding. l (2) Ambient pressure = 14.7 psia, and 1 (3) lio flow in the Turbine Building. j l At time, t = 0.001 seconds, the blowdown transient wks initiated using j the appropriate mass and energy release data. The break volumes, ; j Volume 5 for the MFLB and Volume 11 for the MSLh, are specified by [ tha location of the "fill junction". 10 ! l 1 1 A HELS rimulation can be separated into three periodst ! , (1) Initial Blowdown Period. This period occurs at the O j ! initiation of blowdown. It is dramatic since f 1 the Turbine Building is exposed to a rapid, nearly ] j instantaneous, transition situation of "no flow" to ! l "high flow" relative to the size of the break. For i the full area breaks, this transition also results in l 1 ) a pressure transient which may fail some physical l barriers (doors. metal siding, etc). f n (2) Steady Blowdown Period. During this period a ] ] relatively standy blowdown flow exists. Inertial j effacts are minimized. The break volume tereperature ( ) and pressure profiles stabilire. (Other compartments in thermal-hydraulic exchange with the break ) s t iO 8C 9 Amendment 5 ! (August 1988) l
compartment may still be trending toward a stable thermodynamic environment.) O (3) Post-Blowdown Pariod. Tt.rmination of the mass and energy release from the break marks the beginning of the post-blowdown period. During this period the { Turbine Building begins "recovery" to ambient conditions. The computer simulations utilized time step control features and output display options which capture the key parameters in each of these transient periods. Those key parameters being pressure and temperature for the volumes and of interest. O Amend =ent 5 BC-10 ( Augu st 1988) I
h j 4.0 RESULTS OF HIGH-ENERGY LINE BREAK (HELB) ANALYSIS 1 I Results for the HELBs are described below. The main fecdwater line , break (MFLB) and main steam line breaks (MSLB) are discussed in U separate sections that describe the break volume response, and the l response of neighboring volumes. i 4.1 RESULTS OF MFLB SIMULATION I 7! w 1 The computer simulation and results of the MFLB in the Turbine Building ; I are documented in Reference 7. ; t 4.1.1 VOLUME RESPONSg i ? Tables 8C-7 and 8C-8 show the pressure and temperature responses of 10 1 I
; Volume 5, the break volume, and other volumes of interest, to a simulated l i MFLB. I i; !
Both pressure and temperature rise rapidly in the break volume, reaching
)
i peak values of 15.2 pounds per equare inch absolute (psla) and 212*F, j i
, respectively. The break volume pressure drops to 14.7 psia almost j j immediately. The temperature in the break compartment decreases slowly i i 1
- following temination of blowdown. j l I t
A peak temperature on the order of 170*F is reached by several volumes y' i during blowdown. At termination of blowdown, the temperature coastdown
! for neighboring volumes vary. At 100 seconds into the transient,
) approximately 50 percent of the volumes are within 15'F of ambient. f j The temperatures of the remaining volumes are on the order of 160*F at ! l :
- 100 seconds and are slowly declining. The slower cooling rates of of these volumes is due to limited vent paths to surrounding cocpartments at f
lower temperatures. ' 1
) ) None of the volumes (excluding the break volume) exceeded a pressure of l 15 psia during the transient. Several volumes experience a pressure on i
8C-11 Amendment 5 j (August 1986) i
the order of 14.9 psia at various times during the transient. The k pressures of all volumes return to ambient within 5 seconds. O 4.2 RESULTS OF THE FULL AREA MSLB SIMULATION h The computer simulation and results of the full area MGLB in the Turt ino Butiding are documented in Reference 7. The results of the two full area MSLB simulations are combined in the following discussion to provido the bounding pressure and temperature conditions. 4.2.1 VOLUME RESPONSE 1 n
$ Tables 8C-9 and 8C-10 show the pressure and temperature response of Volume 11 the break volume, and other volumes of interest to a simulated $1 j h full area MSLB.
As in the MFLB case, both temperature and pressure in the break volume rise rapidly. The temperature response of the break volume peaks to 327'F at 90 seconds from the start of blowdown. The pressure response is a short-lived spike ( 0.04 seconds) to 16.4 psia. The pressure returns l l to ambient within 0.5 seconds from the start of blowdown. Temperature in l the break volume decreases more slowly than the MFLB simulktion, reaching l l the saturation temperature of 212*F 670 seconds into the transient. l The response of neighboring volumes to the MSLB is similar in nature to that exhibited for the MFLB. Several of the volumes reach temperatures j h close to that of the break volume, l l_ Due to the extreme temperatures resulting from the superheated blowdown I and limited vent paths to cooler surroundings, the temperatures of many { of the volumes decrease very slowly. Only those volumes representing ! ; enclosed rooms are at or near ambient conditions 700 seconds from the
- start of blowdown (ie, end of the simula.lon).
l 7 Pressures in neighboring volumes are less than 1.0 psia above ambiert
} during the transient.
Amendment 5 BC-12 O (August 1988) 1 1
4.3 RESULTS OF T1tE PARTI AldREA_MSLE STMULAT_ ION s The computer simulation and results of the partial area MSLB in the Turbine Building are documented in Reference 14 The following section providas a summsry of the results. ! 4.3.1 VOLUME RESPONSE l Table 8C-11 shows the worst-case temperature of Volume 11, the Break
*!olume, and other volumes of interest to a simlated partial area MSLB.
The table represents the worst-case temperatures compiled from the threo 9 mall break cases analyze
- as discussed tu Section 2.2.3.
Compa ed to the full areo ItELBs, both temperature and pressure in the break volume rise ruuch more gradually due to the slower release of energy from the break. The temperature response of the break volume peaks to i 469'F at 395 seconds from the start of blowdown for the worst-case break l 1 size (ie, 1.2 sq ft). Temperature in the break volume decreases more 0 ( slowly than the full area itELB simulation due to less ventilation area. f 1 l
\ The reduction in ventilation area is the result of barriers that fall under the load caused by the full area break pressure spike , but remain intact for the partial area break.
Due to the extreme temperatures resulting from the superheated blowdown l and limited vent paths to cooler surroundings, the temperatures of many l of the volumes decreaso slowly. Only those volumes repressnting enclosed l rooms tre at or near ambient conditions 800 seconds from the start of : blowdown (ie, end of the sim tation). Although the peak temperature of Volume 11 is outside the qua1Lfication profile for the Turbine Building, the safety-related components in this area are not required to funct -- in mitigating a small area MLLB. The only components in this area that perfom a safety ("nction are the steam generator and nain steam line pressure transmitters. For a small area ' MSLB. reactor trip and safety injection occur s n overpower AT and low pressuriser pressure, respectively. The steam generator and main O : l BC-13 Amendment 5 ( /.u gu s t 1923)
steam line pressure transmitters do not provido input to those protectivo functions. The pressure transmitters also perform the function of post-accident monitoring (PAM) in s t rumentation. Although the transmitters located in the Turbine Building may fail during a small area MSLB, rodundant transmitters are located in the main steam support structuro that woulo provido the required PAM capability. In addition to Vc.ume 11. The Break Volume, the following volumes are subject to temperature outsido the harsh environment qualification profilo or above normal temperatures assumed for mild environments: (1) Volu-c 5. Area outside the auxiliary feodwater pump rooms on tho 45-foot elevation of the Turbino Building. (2) Volumo 9. Area between the west wall of the Turbino Building and the condensors, and including the areas immediately north and south 0 of the turbine podestal betwoon Elevations 45 foot and 93 foot. (3) Volumes 17 and 18. The Emergency Diosol Generator (EDG) rooms. For the case of Volumo 5 the temperaturo peaks at 304*F momentarily before cooling to below the qualification profile temperature limit of 3uJ'F. No safety-related equipment is located in this volumo. Volumo 9 encompassos the area crutaining turbino first-stage pressure transmitters which provido inputs to reactor trip permissivo p-13 and Engincerod Safety Featuro Actuation System (ESFAS). The temperature in this volume peaks at 306*F momentarily before cooling below the qualifi-cation profilo limit of 303*F. This temperaturo peak occurs 310 seco:ds into the small eren HELB event. The safety functions associated with those transmitters would not have been called upon to mit Tto th- small break accident. In any caso, the safety functions would havo been Amendment 5 8C-14 9 (August 19SS)
performed prior to exceeding the temporaturo limits of the qualification proflie. Reactor trip and safety injection actuation would occur within 60 seconds for the small area HELBs. For Volumes 17 and 18, the EDC rooms, the elevated temperaturos predicted in the analysis aro not expected to occur. The analysis does not take into consideration the room cooling provided by the ventilation system. b 2 This system would actuato approximately 45 seconds into the 1.0 ft break event, which is the worst-case event for EDC room temperatures. In the analysis, the EDC room temperatures do not change considerably from ambient conditions until approximately two minutos into tho event. By this time, room cooling would be well established with tho vantilation fans supplying cool outsido air to the rooms. O O 8C-15 Amendment 5 (August 1988)
5.0 DISCUSSION AND CONCLUSIONS The results of the high-energy line break (HELB) analysis indicates that there are four types of volumes to consider for environmental qualification purposes. A description of each follows: (1) Break Compartment. Characterized by high temperatures and some pressurization. Slow temperature coastdown and step drop in pressure upon termination of blowdown. (2) Vented Compartments. Characterized by a faster temperature decrease than the break compartment as a result of unobstructed energy exchange with adjacent O compartments and/or the atmosphere. Limited pressurization occurs. (3) Closed Compartments (Rooms). Characterized by slower temperature rise and slow recovery period resulting from limited vent capability. Overall, the environ-mental conditions of these compartments change only slightly from the initial ambient conditions. (4) Neighboring Compartments: Characterized by temperature rise and recovary comparable to the break volume, except that less pressurization occLes. Table 8C-12 is an itemization of all equipment in the Turbine Building by Plant identification number, manufacturer, and model number. Also hh provided in Table 8C-12 is a description of each component's safety l} function and its location. Location is identified by Plant room number, elevation, and the volume number used in the thermal hydraulic analysis, - S Most equipment important to safety in the Turbine Building is located in closed compartments and would not be exposed to harsh conditions I l following an HELB. Equipment important to safety that is not located l l l 8C-16 Amendment 5 ) ( August 1988) I l l
l l l in room enclosures includes pressure transmitters, feedwater isolation components and cables to the A Train switchgear. I (m w) An environmental qualification review was parformed and a justifica-tion for continued operations written for all equipment required for safe shutdown located in open areas of the Turbine Building ( . In addition, a thermal lag analysis was performed for safety-related cables to demonstrate cable qualification for the peak temperature calculated via the RELAP analysis . These reviews concluded equipment required for safe Plant shutdown was either environmentally qualifled, was capable of performing its safety function prior to significant exposure to a harsh environment, or would f ail in a manner not detrimental to Plant safety. The following permanent modifica-tions were identified, In a Licensee Event Report, as necessary to ensure that safety-related equipment is either isolated from the effects of a HELB or L fully qualified for these effects . (1) Modification of portions of the Turbine Building metal siding to permit venting and, hence, HELB energy release to d the outside atmosphere. At some siding span lacations, existing fasteners were replaced with pecssure release fasteners which would release at reasonably low HELB overpressures but will resist design wind suction pressures. At other . span locations, fastence capacities were increased to preclude the siding from becoming a secondary miselle concern should venting occur. 1 (2) Modification of heating, ventilating, and air conditioning (HVAC) paths for the remote shutdown panel room, auxiliary feedwater pump room (A and B trains), engineered safety features switchgear room (A train) to effectively isolate safety-related equipment from potential Turbine Building ifELB environments. O Amendment 5 8C-17 (August 1988) ,
(3) Modification of roll-up doors and structural elements of other barriors as required to withstand potential HELB overpressuree such as to maintain acceptable environments l k for the emergency diesel generator (A and B trains)-mala air intake, diesel auxiliary foodwater pump room (B train) and - s. engineered safety features switchgear room (A train). (4) Replacement of the main steam line and turbine first stago pressure transmitters. (5) Replacement of the main feedwater control and bypass control alves solenoid valves, and a portion of cabling for the "A" th component cooling water makeup pump. 3 s All corrective action except for (5) above were completed during the 1987 refueling outage. Components in (5) above were replaced during i} the 1988 refueling outage, g In conclusion, the thermal-hydraulic analysis shows that in the event d of a HELB, areas of the Turbine Building can experienco elevated temperature and pressure conditions. In the event of a MSLB, these O
,.nditions may exist for several minutes. These elevated environ-mental conditic.ns and the associated steam environment, designate certain areas of the Turbine Building to be a harsh environment for equipment environmental qualification.
L 8C-18 Anendment 5 (August 1988) 1 I
l t 6.0 E6FERENCES 3 l f'\ ' i A ,/ 1. IE Bulletin 79-018. "Environmental Qualification of Class 1E Equlpment; Issued 1/14/80.
- 2. IE Bulletin 79-01; Issued 2/8/79.
! 3. PGE-1004, "Trojan Nuclear Plant Analyses of Pipe System Breaks, Outside Containment", prepared for Portland General Electric by i Bechtel Power Corporation Revision 3, October 1975. ; f
- 4. Babcock & Wilcox. "RELAP 4/ MOD 6 - A Computer Program for Transient _'
Thermal-Hydraulle Analysis". NPGD-TM-598, Revision J Volumes I and 3 II, August 1985.
- 5. WCAP 10961-P "Steamline Break Mass / Energy Releases for Equipment '
Environmental Qualification outside Containment - Report to the Westinghouse Owners Group High-Energy Line Break /Superheated Blowdowns outside Containment Subgroup", October 1985, by Westinghouse Electric Corporation.
- 6. Westinghouse Owners Group Letter WOC-HELB/SBOC-020. "Transmittal of Implementatlon Suggestions", November 1, 1985.
- 7. Portland General Electric Calculation No. TNP 87-21. "RELAP Analysis ,
of Modified Turbine Building", June 5, 1987. 13 l (j 8. Bechtel Western Power Corporation Letter, Portland General Electric Company. Trojan Nuclear Plant - Job 11760, High-Energy Line Breaks in Turbine Building - Blowdown Data, R. W. Fosse, February 3,1987. l
- 9. NRC Standard Review Plan, Section 6.2.1, "Subcompartment Analysis, j Revision 2", July 1981. ,
D'
- 10. Memorandum ANR-304-86M, "Trojan Nuclear Plant Evaluation of the r Environmental Qualification of Electrical Equipment (EEEQ) in the I j Turblne Building and Justlfication for Continued Operation",
] October 27, 1986.
- 11. Portland Conceal Electric Calculation No. TM-241, "Thermal Transient in cables Due to High Energy Line Break", July 16, 1987. 19 l,
- 12. Licensee Event Report 86-10, Revislca 1. Deficiencles Identifled in ,,
i the Analysis of High Energy Line Breaks in the Turbine Building", t i January 30, 1987.
- 13. Portland General Electric Calculation No. TNP 81-42, "Calculation of f
Temperatures in EDG Rooms Following HELB Using RELAP4/ MOD 6", January 7, 1988. ,3 i 14. Portland General Electric Calculation No. TNP 87-44, "Small Area Break Analysis of Turbine Building Using RELAP4/ MOD 6", May 11, 1988. i O 8C-19 Amendment 5
- (August 1988) 1 J
l J
i Table 8C-3 Mass and Energy Release for a Main Steam
/~T Line Break in the Turbine Building U Full Power ,
t m h SUPERHEAT SEC. LB/SEC. BTU /LBM NOTES BTV/LP_
~
0 0 1196.5 ! 0.001 509. 1196,5 0.002 6263. 1196.5 Inventory Blowdown 0.003 7970. 1196.5 Total 10000 lbs. t 0.0053 8574 1196.5 - Steam at 530*F, 0.01 8855. 1196.5 888 psia ' 0.04 10318. 1196.5 O.06 10648. 1196.5 l 0.957 10648. 1196.5 _
~
O.958 8049, 1194 Westinghouse SG 4.258 6885. 1198. - 810wdown; Turbine Stop 4.958 7597. 1198. _ Valves Open
~
Stop Valve Closed; 417, p 4.959 3115. 1198. d 10.358 2859. 1200. _- Correction Factor 2140, l 10.458 1200. 15.958 1756. 1203. l 31.058 1188. 1204 66.058 891. 1203. 0 One MSIV Failed Open; , 81.058 592. 1248. +49 - No Correction l 95.058 134 1282. +111 267.058 30.2 1311. +140 401.058 30.2 1314 +163 600.058 30.2 1316. +165 , 600.059 0 1316. ,, l !O l
! Amendment 4 (August 1987) l
TABLE 8C-4 MASS AND ENERGY RELEASE FOR A 0.8 ft2 MAIN STEAM LINE BREAK IN THE TURBINE BUILDING Full Power Time Flow Enthalpy Superheat* (sec) (lbm/sec)_ (Btu /lbm) (Btu /lbm). 0.0 1461 1194 10.0 1318 1196 16.0 1267 1197 2 24.6 1639 1192 59.6 1401 1197 100.1 1174 1201 150.1 997 1203 200.1 961 1203 250.1 960 1203 314.1 956 1203 400.1 835 1222 &l8 500.1 566 1247 +43 599.1 185 1278 +89
- Above saturation enthalpy.
Amendment 5 (August 1988)
. . . ,, - - . .. . . .. ~ . . . .. l TABLE 8C-5 MASS AND ENERGY RELEASE FOR A 1.0 ft2 MAIN STEAM LINE BREAK IN THE TURBINE BUILDING , Full Power Time Flow Knthalpy Supe rhea t.* (see) (1bm/sec) (Btu /lbm) (Btu /lbmL i 0.0 1805 1194 C; 13.5 1543 1198 13.6 1701 1198 21.6 1988 1193 50.1 1692 1198 > 100.1 1302 1203 l 150.1 1159 1204 200.1 1148 1204 319.1 1100 1211 +7 400.1 630.5 1253 +50 , 500.1 129.' 1287 +109 599.1 120 . 1284 +107
- Above saturation enthalpy.
[ i l l l l 1 O Amendment 5 (August 1988)
TABLE 8C-6 MASS AND ENERGY RELEASE FOR A 1.2 ft2 MAIN STEAM LINE BREAK IN THE TURBINE BUILDING Full Power Time Flow Enthalpy Superheat* (see) (1bm/see) (Btu /lbml (Btu /lbml_ 0.0 2141 1194 12.1 1801 1198 - 20.0 2310 1194 0 41.1 2006 1198 100.1 1422 1203 150.1 1324 1204 200.1 1318 1904 300.1 1114 1226 +24 350.1 470 1270 +72 400.1 147 1288 +111 450.1 12i 1289 +116 500.1 121 1288 +115 599.1 121 1285 +112 O
- Above saturation enthalpy.
Amendment 5 l (August 1988) 1 I l j
TABLE 8C-7 C- .' PRESSURE RESPONSE OF TURBINE BUILDING COMPARTMENTS k-./}
'4 FOR A MAIN FEEDWATER LINE BREAK AT 100 PERCENT POWER Time Compartment Number (seconds) 1 -5 7 8 9 11 _17 _18 19 .
0.0 14.7 14.7 14.7 14.7 14.7 14.7 14.7 14.7 14.7
- 0.01 - 15.0 14.7 14.7 14.7 - 14.1 14.7 14.7 0.02 - 15.2 14.7 14.7 14.7 -
14.7 14.7 14.7 0.03 - 15.2 14.7 14.7 14.7 - 14.7 14.7 14.1 0.04 - 15.1 14.7 14.7 14.7 - 14.7 14.7 14.7 0.05 - 15.0 14.7 14.7 14.7 - 14.7 14.7 14.7 0.06 - 14.9 14.1 14.7 14.7 - 14.7 14.7 14.7' O.07 - 14.7 14.1 14.7 14.7 - 14 . .' 14.7 14.7 0.08 - 14.6 14.7 14.7 14.7 - 14.7 14.7 14.7 " 0.09 - 14.6 14.1 14.7 14.7 - 14.7 14.7 14.1 0.10 14.7 14.6 14.7 1#.7 14.8 14.8 14.7 14.7 14.7 0.12 - 14.6 14.7 14.7 14.8 - 14.7 14.7 14.7 0.14 - 14.7 14.7 14.7 14.8 - 14.7 14.7 14.8 0.16 - 14.8 14.7 14.7 14.8 - 14.7 14.7 14.8 0.2 14.7 14.8 14.1 14.7 14.8 14.7 14.7 14.7 '14.8 ; 0.3 14.7 14.7 14.7 14.8 14.7 14.7 14.7 14.7 14.7 O.4 14.8 14.7 14.7 14.8 14.7 14.7 14.7 14.8 14.8 0.5 14.8 14.8 14.7 14.8 14.8 14.8 14.7 14.8 14.8 1.5 14.9 14.9 14.1 14.9 14.9 14.9 14.8 14.8 14.9 j Od 2.5 14.7 14.7 14.7 14.7 14.7 14.7 14.7 14.7 14.7 [
; 3.5 14.7 14.7 14.1 14.7 14.7 14.7 14.7 14.7 14.7 ;
4.5 14.7 14.7 14.7 14.7 14.7 14.1 14.7 14.7 14.7 5.0 14.7 14.7 14.7 14.7 14.7 14.1 14.7 14.7 14.1 ' 4 l l l i l O Amendment 5 ( August 1988) 1 l s
{l TABLE 8*-8 TEMPERATURE RESPONSE OF TURBINE BUILDING COMPARTMENTS TO A MAIN FEEDWATER LINE BREAK AT 100 PERCENT POWER Timo compartment Number (seconds) 1 3 5 7 8 9 17 18 19 0.00 104 104 104 134 104 104 104 104 104 0.10 104 103 134 104 104 105 104 104 105 0.40 105 105 168 105 105 105 105 105 105 0.50 105 106 174 105 105 105 105 105 105 2.00 104 127 206 105 106 105 105 105 106 5.00 104 154 212 104 102 105 104 104 104 10.00 104 169 212 102 102 127 104 104 108 15.00 104 170 212 100 102 157 104 104 120 20.00 104 174 209 99 104 170 104 104 137 25.00 105 170 179 98 107 175 103 103 150 30.00 106 169 169 97 110 175 103 103 159 35.00 106 170 170 96 112 173 102 103 163 40.00 106 169 110 95 113 171 102 102 166 45.00 107 168 169 95 115 170 101 102 167 50.00 107 167 168 94 116 169 101 101 168 55.00 107 166 167 94 117 168 100 101 168 60.00 107 165 166 94 119 167 100 100 168 65.00 107 164 165 93 120 166 100 100 168 10.00 108 163 164 93 120 165 99 100 167 15.00 108 163 163 93 121 164 99 99 151 80.00 108 162 163 93 121 164 98 99 166 85.00 108 161 162 92 121 163 98 99 166 9 0 . 0.' 108 160 161 92 121 162 98 98 165 91.00 108 160 160 92 121 161 97 98 165 100.00 108 159 160 92 121 161 97 98 164 l I Amendment 5 (August 1988) 1 l I
i t I , TABLR 8C-9 lu { i l' ' PRESSUME RESPONSE OF TURBINE BUILDING COMPARTMENTS FOR A MAIN STEAM LINE BREAK AT 100 PERCENT POWER (S v
- Time Compartment Number (seconds) 1 ,5 7 8 9 _11 17 _18_ 19 0.0 14.7 14.7 14.7 14.7 14.7 14.7 14.7 14.1 14.7 0.01 14.7 14.7 14.7~ 14.7 14.7 15.2 14.7 14.7 14.7 0.02 14.7 14.7 14.7 14.7 14.7 15.8 14.7 14.7 14.7 ,
0.03 14.7 14.8 14.7 14.7 14.7 16.2 14.7 14.7 14.7 0.04 14,7 14.8 14.7 14.7 14.7 16.4 14.7 14.7 14.8 0.05 14.7 14.9 14.7 14.7 14.8 16.4 14.1 14.7 15.0 i 0.06 14.7 15.0 14.7 14.7 14.8 16.3 14.7 14.7 15.0 O.07 14.7 15.1 14.7 14.7 14.8 16.0 14.7 14.7 15.1 O.08 14.7 15.2 14.7 14.7 14.9 15.6 14.7 14.7 15.2 I 0.09 14.7 15.3 14.7 14.8 15.0 15.3 14.7 14.7 15.3 0.10 14.7 15.4 14.7 14.8 15.1 15.0 14.7 14.7 15.4 1 0.11 14.8 15.5 14.7 14.8 15.2 14.8 14.7 14.7 15.4 0.12 14.8 15.5 14.7 14.8 15.3 14.6 14.7 14.7 15.4 0.13 14.8 15.4 14.1 14.8 15.4 14.6 14.7 14.7 15.4 0.14 14.8 15.3 14.7 14.8 15.4 14.6 14.1 14.7 15.3 , 0.15 14.8 15.3 14.1 14.8 15.5 14.7 14.7 14.7 15.3 O.16 14.9 15.2 14.7 14.9 15.5 14.8 14.7 14.7 15.2 0.17 14.9 15.1 14.7 14.9 15.5 14.9 14.8 14.8 15.1 0.18 14.9 () 0.19 0.20 14.9 14.9 15.1 15.0 15.0 14.7 14.7 14.7 14.9 14.9 14.9 15.5 15.5 15.4 15.0 15.0 15.1 14.8 14.8 14.8 14.8 14.8 14.8 15.0 15.0 15.0 0.22 15.0 15.1 14.8 15.0 15.3 15.1 14.8 14.8 15.1 0.24 15.0 15.1 14.8 15.0 15.1 15.1 14.8 14.8 15.1 0.26 1S.1 15.1 14.8 15.1 15.0 15.1 14.8 14.8 15.2 0.28 15.1 15.1 14.8 15.1 14.9 15.1 14.8 14.8 15.2 0.30 15.1 15.0 14.8 15.2 14.8 15.0 14.8 14.9 15.2
; 0.32 15.2 15.0 14.8 15.2 14.8 14.9 14.8 14.9 15.1 0.34 15.2 14.9 14.8 15.2 14.8 14.8 14.8 14.9 15.0 ,
0.36 15.2 14.9 14.9 15.2 14.8 14.1 14.9 14.9 14.9 l 0.38 15.2 14.8 15.0 15.2 14.9 14.6 14.9 14.9 14.8 0.40 15.2 14.8 15.0 15.2 14.9 14.7 14.9 14.9 14,4 i 0.42 15.2 14.8 15.0 15.2 14.9 14.7 14.9 15.0 14.8 0.44 15.1 14.8 15.0 15.2 14.9 14.8 15.0 15.0 14.9 0.46 15.1 14.9 15.0 15.2 14.9 14.8 15.0 15.0 15.0 0.48 15.1 14.9 15.0 15.2 14.9 14.8 15.1 15.0 15.0 0.3 15.1 15.0 15.0 15.1 14.9 14.9 15.1 15.1 15.0 3 0.6 15.0 15.0 15.0 15.0 15.0 14.8 15.1 15.1 14.9 i 0.7 14.9 14.8 14.9 14.9 14.8 14.7 15.0 14.9 14.8 0.8 14.7 14.1 14.8 14.7 14.7 14.5 14.8 14.8 14.7 0.9 14.6 14.6 14.7 14.1 14.6 14.4 14.7 14.7 14.6 1.0 14.5 14.5 14.6 14.5 14.5 14.4 14.6 14.6 14.5 2.0 14.8 14.8 14.8 14.8 14.8 14.7 14.8 14.8 14.8 5.0 14.7 14.7 14.1 14.7 14.7 14.6 14.7 14.7 14.7 s 10.0 14.7 14.1 14.7 14.1 14.7 14.6 14.7 14.7 14.7 O Amendment 5 l , (August 1988) ! l ]
hl TABLE 8C-10 TEMPERATURE RESPONSE OF TURBINE BUILDINO COMPARTHENTS hl TO A MAIN STEAM LINE BHEAK AT 100 PEHCENT POWEH Timo Compartment Number (seconds) 1 3 5 7 8 9 11 17 18 19 0.0 104 104 104 104 104 104 104 104 104 104 0.45 109 132 - 105 109 106 269 106 106 108 0.5 108 135 107 105 108 107 218 106 106 109 5.0 110 269 140 103 105 138 314 105 105 119 30.0 111 253 230 97 113 218 296 103 103 195 55.0 113 243 222 94 132 266 294 101 101 271 80.0 118 268 252 93 143 273 319 99 99 297 85.0 119 279 - 93 144 273 326 98 99 304 90.0 120 289 - 92 142 273 327 98 99 308 95.0 120 294 - 92 140 273 318 98 98 310 105.0 121 292 286 92 139 275 314 97 98 308 130.0 122 299 291 92 130 281 320 97 97 280 155.0 123 306 285 92 127 287 320 96 97 251 180.0 123 299 279 92 124 295 320 96 97 248 200.0 124 295 286 92 120 301 320 96 97 228 220.0 124 291 - 92 118 304 316 96 97 221 250.0 126 283 275 92 116 297 299 96 97 206 300.0 128 265 260 92 120 268 272 96 97 188 350.0 132 251 248 94 131 255 257 100 100 139 400.0 136 241 238 96 135 244 250 105 104 134 450.0 139 235 232 98 137 236 246 108 107 136 500.0 142 232 229 100 137 232 244 110 109 131 550.0 144 232 229 101 139 232 243 112 111 138 600.0 146 233 230 103 140 232 244 114 112 139 625.0 147 23 - 103 140 229 217 114 112 140 635.0 147 220 - 103 140 225 212 114 112 140 650.0 147 214 214 102 140 219 205 114 112 140 700.0 148 199 198 100 138 203 183 113 111 139 Amendment 5 (August 1988)
j 1 4 3 TABLE 8C -; WORST-CASE TEMPERATURE RF SPONSE OF TURBINE BUILDINC -! COMPARTMENTS TO PARTIAL AREA MAIN STEAM LINE BREAK AT 100 PERCENT POWER 4 r
- f f !
l 8 Compartment Time Temperaturo ,s ; 2-No. -(Seconds) ('F) 10 . t i 1 i 1 100 198 l 5 320 304 f 7 495 145 ; j 8 520 185 ; j 9 310 306 7 1 11 395 469 17 490 162 i j 18 499 144 j' 19 110 218 !
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_ . - - - . . - _ _ . - _ _ - . _ . . . - - - . - . - ~ . . . . . . - -._ . . - - -._-_ - ___ --.. - - 1 O 07/26/83 O O PORTLAND GENERAL ELECTRIC EQ COMPONENTS IN TURBINE B*JILDING TABLE SC-12 SHEET 1 0F 7 ' PLANT SAFETY ROOM VOLUME ELEVATION-ID_NUNSCR_ MANUFACTURER MODEL NUMBER FUNCTILM NUMBER kUMBER (FEET) A 1 AC POWER DISTR 107 20 69 ATB 701 GE NO NAMEPLATE ELEC CONN 91 16 45 ATB 702 GE 2648965 ELEC CONN 91 16 45 ATR 703 GE 264B965 CLEC CONN C160 14 45 ATR 704 GE 2648 % 5 ELEC CONN C160 14 45 ATR 705 GE EB ELEC CONN 107 20 69 ATR 706 GE EB ELEC CONN 107 20 69 ATR 711 GE 264B%5 ELEC CONN 113 1 93 5 1 AC POWER DISTR 107 20 69 9 3 AC POWER DISTR 107- 20 69 R 21 AC POW.R DISTR 107 20 69 E 23 AC POWER DISTR 107 20 69 3 25 AC POWER DISTR 107 20 69 GTB 701 NO NAMEPLATE ELEC CONN 90 15 45 l l CTB 703 WOODWARD 8271-179 ELEC CONN 90 15 45 BTB 704 TB FIELD FABRICATED DIODE IRC 40HF100 ELEC CONN /ISLN 98 15 45' BTB 706 GE EB-5 ELEC CONN 90 15- 45 DT3 711 GE EB-5 ELEC CONN 113 1 93- , C 101 CONTROL 85 18- 45 C 102 CONTROL 86 17 45 C 160 A INDICATION & CONTROL C160 14 45 C 160 B INDICATION & CONTROL C160 14. 45 SN s 0&
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$* EQ COMPUNENTS IN TURBINE BUILDING TABLE 8C-12 SHEET 2 0F 7 PLANT SAFETY ROOM VOLUME ELEVATION ID NUMBER MANUFACTURER MODEL NUMBER FUNCTION NUMBER NUMBER (FEET)
FT 510 BARTON 384 REACTOR TRIP 103 11 63 FT 511 BARTON 384 REACTOR TRIP 103 11 63 FT 520 BARTON 384 REACTOR TRIP 103 11 68 FT 521 BARTON 384 REACTOR TRIP 103 11 68 FT 530 BARTON 384 REACTOR TRIP 103 11 63 FT 531 BARTON 384 REACTOR TRIP 103 11 63 FT 540 BARTON 384 REACTOR TRIP 103 11 63 FT 541 BARTON 384 REACTOR TRIP 103 11 63 G 101 NO NAMEPLATE 4.16KV POWER SUPPLY 85 18 45 G 102 FIELD VALVE 85 18 45 G 103 GE 275X630C377 NEUTRAL GND RESISTOR 85 18 45 G 201 NO NAMEPLATE 4.16KV POWER SUPPLY 86 17 45 G 202 FIELD VALVE 86 17 45 G 203 GE 275X630C377 NEUTRAL GND RESISTOR 86 17 45 LS 4905 A BARTON 286A CONTROL 85 18 45 LS 4905 B BARTON 288A CONTROL 86 17 45 LS 4909 A BARTON 288A CONTROL 90 15 45 LS 4909 B BARTON 288A CONTROL 90 15 45 LS 4911 A BARTON 288A CONTROL ALARM 85 18 45 LS 4911 B BARTON 288A CONTROL ALARM 86 17 45 LS 5201 C ROCHESTER ET-1214 SEE NOTES , 90 15 45 LS 5265 ROCHESTER ET-1214 SEE NOTES 90 15 45 MD 3045 A LIMITORQUE SMB-00-10 BACK UP FDW SOURCE 91 16 47 O O O
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% ,I \j 'tj 07/26/88 PORTLAND GENERAL ELECTRIC EQ COMPONENTS IN TURBINE BUILDING TABLE 8C-12 SHEET 3 0F 7 PLANT SAFETY ROOM VOLUME ELEVATION ID NUMBER MANUFACTURER MODEL NUMBER FUNCTION NUMBER NUMBER (FEET)
MO 3045 B LIMITORQUE SMB-00-!O BACK UP FDW SOURCE 90 15 47 MO 3060 B LIMITORQUE SMB-000 LOW COOLING WATER 90 15 45 MO 3071 LIMITORQUE SMB-000 THROTTLE VALVE 91 16 45 MO 3170 LIMITORQUE SMB-000 CONTROL VALVE 91 16 45 MO 4903 A LIMITORQUE SMB-000 FUEL TRANSFER 85 18 45 MO 4903 B LIMITORQUE SMB-000 FUEL TRANSFER 86 17 45 MO 4907 A LIMITORQUE SMB-000 FUEL TRANSFER 90 15 45 MO 4907 B LIMITORQUE SMB-000 FUEL TRANSFER 90 - 15 45 MP 168 BALDOR 27384-11925 PUMP MOTOR 90 15 45 MV 163 A hT.S11NGHOUSE TBDP ROOM COOLING 107 20 69 MV 163 B WESTINGHOUSE TBDP ROOM COOLING 107 20 69 MV 163 C WESTINGHOUSE TBDP ROOM COOLING 107 20 69 MV 164 hT.STINGHOUSE TBDP ROOM COOLING 107 20 69 MVC 131 A RELIANCE TYPE P ROOM AIR EXHAUST 85 18 45 MVC 131 B RELIANCE TYPE P ROOM AIR EXHAUST 85 18 45 MVC 132 A RELIANCE TYPE P ROOM AIR EXHAUST 86 17 45 MVC 132 B RELIANCE TYPE P ROOM AIR EXHAUST 86 17 45 MVC 161 RELIANCE TYPE P ROOM AIR SUPPLY 85 18 45 MVC 162 RELIANCE TYPE P ROOM AIR SUPPLY 86 17 45 MVC 166 RELIANCE TYPE P ROOM AIR SUPPLY 91 16 45 MVC 167 RELIANCE TYPE P ROOM AIR EXHAUST 87 9 45 MVC 168 RELIANCE TYPE P ROOM AIR EXHAUST 89 14 45 5N =R ; 5&
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$ TABLE 8C-12 SHEET 4 0F 7 PLANT SAFETY ROOM VOLUME ELEVATION ID NUMBER MARUFACTURER MODEL NUMBER FUNCTION NUMBER NUMBER (FEET)
PS 3072 C ROCHESTOR ET 1215 TRIP TURBINE PUMP 89 14 45 PS 3072 D ROCHESTOR ET 1215 TRIP DIESEL PUMP 90 15 45 PS 3073 X MERCOID CONTROL DA33-804 OPERATOR SPEED INCR 90 15 45 PT 505 ROSEMOUNT 1153GD8 FDW ISOLATION 87 9 48 PT 506 ROSEMOUNT 1153GD8 FDW ISOLATION 87 9 50 PT 514 ROSEMOUNT 1153GD9 SI/PAM 103 11 63 PT 516 ROSEMOUNT 1153GD9 SI/PAM 103 11 63 PT 524 ROSEMOUNT 1153GD9 SI/PAM 103 11 63 PT 526 ROSEMOUNT 1153GD9 SI/PAM 103 11 63 PT 534 ROSEMOUNT 1153GD9 SI/PAM 103 11 63 PT 536 ROSEMOUNT 1153GD9 SI/PAM 103 11 63 PT 544 ROSEMOUNT 1153GD9 SI/PAM 103 11 63 PT 546 ROSEMOUNT 1153GD9 SI/PAM 103 11 63 PT 2210 FISCHER & PORTER 50EP1041BCSB PAM 103 11 66 PT 2230 FISCdER & PORTER 50EP1041BCSB PAM 103 11 66 PT 2250 FISCHER & PORTER 50EP1041BCSB PAM 103 11 68 PT 2270 FISCHER & PORTER 50EP1041BCSB PAM 103 11 66 PT 3072 A FISHER /PORTEk 55PD1111A LOW PRESS TRIP 91 16 45 PT 3072 B FISHER / PORTER SSPD1111A4A LOW PRESS TRIP 90 15 45 o PT 3083 A BARTON 393 CONTROL PUMP SPEED 91 16 45 PT 3083 B BARTON 393 CONTROL PUMP SPEED 91 16 45 PY 3072 A FISHER / PORTER 50EK1000 SIGNAL ISOLATION 89 14 45 PY 3072 B FISHER / PORTER 50EK1000 SICNAL ISOLATION 90 15 45 s O O O
O 07/26/88 O O PORTLAND GENERAL ELECTRIC EQ COMPONENTS IN TURBINE BUILDING TABLE 8C-12 SHEET 5 0F 7 PLANT SAFETY ROOM VOLUME ELEVATION ID NUMBER MANUFACTURER MODEL NUMBER FUNCTION NUMBER NUMBER (FEET) O 71 SAB-NIFE (30) H410-2 AFW DIESEL BATTERY 90 15 45 0 73 AFW DIESEL CONTROL 90 15 45 0 80 SAB-NIFE SCBF100-24-25 FLOAT BTRY CHARGE 90 15 45 0 318 A WESTINGHOUSE N/A POWER SUPPLY 107 20 69 QK 107 B DIESEL AITTO START C160 14 45 QMP 168 SPEED INCREASER 90 15 45 RT 10400 POWERS SERIES 90 MODEL SS SEE NOTES 86 17 45 RT 10401 POWL?S SERIES 90 MODEL SS SEE NOTES 85 18 45 SV 510 A ASCO LB8300C58RU FDW ISOLATION 113 1 107 SV 510 B ASCO LB8300C58RU FDW ISOLATION 113 1 107 SV 5*.0 A ASCO LB8300C58 FDW ISOLATION 113 1 107 SV 520 B ASCO LB8300C58RU FDW ISOLATION 113 1 107 SV 530 A ASCO LB8300C58RU FDW ISOLATION 113 1 107 SV 530 B ASCO LB8300C58RU FDW ISOLATION 113 1 107 SV 540 A ASCO LB8300C58RU FDW ISOLATION 113 1 107 SV 540 B ASCO LB8300C58RU FDW ISOLATION 113 1 107 SV 2993 A1 ASCO WP8300C61RU FDW BYPASS ISOLATION 113 1 103 SV 2993 A2 ASCO WP8300C61RU FDW BYPASS ISOLATION 113 1 103 SV 2993 B1 ASCO WP8300C61RU FDW BYPASS ISOLATION 113 1 103 SV 2993 B2 ASCO WP8300C61RU FDW BYPASS ISOLATION 113 1 103 SV 2993 C1 ASCO WP8300C61RU FDW BYPASS ISOLATION 113 1 103 SV 2993 C2 ASCO WP8300C61RU CONTROL VALVE 113 1 103 OR Rd n
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mv PORTLAND GENERAL ELECTRIC EQ COMPONENTS IN TURBINE BUILDING l 3 TABLE 8C-12 SI'EET 6 0F 7 PLANT SAFETY ROOM VOLUME ELEVATION ID NUMBER MANUFACTURER MODEL NUMBER FUNCTION NUMBER NUMBER (FEET) l SV 2993 D1 ASCO WP8300C61RU CONTROL VALVE 113 1 103 l l SV 2993 D2 ASCO WP8300C61RU CONTROL VALVE 113 1 103 SV 3712 A ASCO NP8321ASE COOLING WATER 85 18 45 SV 3712 B ASCO NP8321ASE COOLING WATER 86 17 45 j SV 3714 ASCO NP8321ASE SC I/II 86 17 45 i SV 3725 ASCO NF8321ASE SC I/II 85 18 45 UCDA 1 PYROTRONICS N/A SEE NOTES 86 17 45 X 11 VOLTAGE REDUCTION 107 20 69 X 13 VOLTAGE REDUCTION 107 20 69 X 40 HEVI-DUTY HSIF7.5A (1 PHASE) VOLTAGE RDCN CH A 107 20 69 ZS 510 NAMCO D2400XR2 FDW ISOLATION 113 1 107 ZS 520 NAMCO D2400XR2 FDW ISOLATION 113 1 107 ZS 530 NAMCO D2400XR2 FDW ISOLATION 113 1 107 ZS 540 NAMCO D2400X FDW ISOLATION 113 1 107 ZS 2993 A SA TYPE 304 FDW BYPASS ISOLATION 113 1 103 ZS 2993 B SA TYPE 304 FDW BYPASS ISOLATION 113 1 103 ZS 2993 C SA TYPE 304 FDW BYPASS ISOLATION 113 1 103 ZS 2993 D SA TYPE 304 FDW BYPASS ISOLATION 113 1 103 ZS 3071 A NAMCO D2400XR2 AFW INLET VALVE 91 16 45 ZS 3071 B NAMCO D2400XR2 AFW INLET VALVE 91 16 45 ZS 3712 A NAMCO D2400X INDICATION 85 18 45 ZS 3712 B NAMCO D2400X2SR INDICATION 86 17 45 ZS 3714 NAMCO D2400X2SR ISOLATION SEAL IN 86 17 45 I O O O
-.m -_.____m _ _ _ _ _ _ - . . . . . .__ . _ =___ _ _ _ . . ._ _ _ _.____ _ ____ _ -._ __ .. .. _ . ___ ._ _ _ _ . _ .
7 -_ t 07/26/83 PORTLAND GENERAL ELECTRIC EQ COMPONENTS IN TURBINE BUILDING
- TABLE SC-12 SHEET 7 0F ? I i PIANT SAFETY ROOM VOLUME ELEVATION j ID NUMBER MANUFACTURER MODEL NUMBER FUNCTION NUMBER NUMBER fFEET) j ZS 3725 NANCO D2400X ISOLATION SEAL IN 85 18 45 1
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Portland General Electric Nucioar DMsion MEMORANDUM TO: Document Control, Desk. USNRC TDW-661-88 FROM: T. D. Walt \ DATE: August 31, 1988 SUBJECT Transmittal of PGE Topical Repo_r_t_ Enclosed is your copy of Amendment 5 to PGZ-1025, "Environmental Qualification Program Manual". Please acknowledge receipt by completeing the lower portion of this trans-mittal and returning it to the location given below.
"
- TDV/ mew Enclosure ACKNOWLEDGEMENT PGE-1025 Environmental Qualification Program Manual Amendment 5 I hereby acknowledge receipt of Controlled Copy Number (s) 52-62 of the subject document.
3 Signature of Copy Holder Date
** Return to: Mary E. Wagner NSRD SB-Bridge Portland General Electric 121 S. W. Salmon Street
( pg(,I Portland OR 97204 1 i ll l
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