ML19321B029
| ML19321B029 | |
| Person / Time | |
|---|---|
| Site: | Prairie Island  |
| Issue date: | 07/08/1980 |
| From: | Gilberts D NORTHERN STATES POWER CO. |
| To: | James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| References | |
| IEB-80-11, NUDOCS 8007250077 | |
| Download: ML19321B029 (51) | |
Text
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NSP !
NOMTHERN STATE 5 POWER COMPANY M O N N E A PO L.l S. M I N N E S OTA 55401 July 8, 1980 Mr. James G. Keppler Director, Region III IHis DOCUMEt!T C0tlTAlHS Office of Inspection and Enrorcement POOR QUALITY PAGES --
U. S. Nuclear Regulatory Commission 799 Roosevelt Road '
Glen Ellyn, IL 60137
Dear Mr. Keppler:
PRAIRIE ISIAND NUCLEAR GENERATING PIANT Docket Nov. 50-282 and 50-306 IE Bulletin No. 80-11 In response to IE Bulletin No. 80-11, Items 1, 2a, and 3, the attached report by Fluor Power dated July 2, 1980, is offered. Inaccessible areas will be reported in our 180 day response or subsequent submittals.
Due to transportation problems with receiving the final draft from our con-tractor, this response is submitted one day late. Ken Ridgeway of the Region III Office was informed of this delay on July 7.
Yours truly,
/ W D. E. Gilberts Vice President Power Production cc: Mr. G. Charnoff NRC Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D. C. 20555 At,tachments DEG:nk rqn* f T N 80072500 U g
UNITED STATES NUCLEAR REGULATORY COMMISSION NORTHERN STATES POWER COMPANY ERAIRIE ISLAND NUCLEAR GENERATING PLANT ,
Docket Nos. 50-282 and 50-306 LETTER DATED JULY 8, 1980 RESPONDING TO NRC REQUEST FOR INFORMATION IN IE BULLETIN NO. 80-11 Northern States Power Company, a Minnesota corporation, by this letter dated
- July 8,1980, hereby submits information in response to NRC request for in-formation concerning IE Bulletin No. 80-11.
This request contains no restricted or other defense infomation.
NORTHERN STATES POWER COMPANY By: o ~
D. E. Gilberts Vice President Power Production On this th day of ,19 [ , before me a notary public in and for said County, person gly affeared D. E. Gilberts, Vice President Power Pro-duction, and being first duly sworn acknowledged that he is authorized to execute this document on behalf of Northern States Power Company, that he knows the contents thereof and that to the best of his knowledge, information and belief, the statements made in it are true and that it is not interposed for delay.
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!!ASONRY WALL DESIGN Response to IE Bulletin 80-11
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. PRAIRIE ISLAND NUCLEAR GE.' CRATING PLANT UNITS 1 & 2 i NORTHERN STATES PC'..'ER COMPANY PROJECT 217450-280 JULY 2, 1930 I
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- Resp:nso to' IE Bulletin 80-11 217450-280 Page ii MASONRY WALL CESIGN TABLE OF CONTENTS ,
Item Page List of Tables jjj 1.0 Introduction 1
2.0 Design Philosophy 1 3.0 Type of Construction 2 4.0 Identification of Walls 2 E.0 Priorization of Walls 3 6.0 Re-Evaluation of the Design 4 7.0 Re-Evaluation Acceptance Criteria 4 8.0 Project Plan 12 Attachment 1: System Alphabetic Code Attachment 2: Field Data Sheet ,
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!, - 21-7450-280 l . Page iii MASONRY WALL DESIGN
. . LIST OF TABLES PAGE I
- 1. Allowable stresses in Masonry - Inspected Workmanship 12 1
- 2. Masonry Walls on Floor 695'-0" with Safety Related Equipment and/or piping. 13
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- 3. Masonry Walls on Floor 715'-0" with Safety Related Equipment and/or piping. 14
- 4. Masonry Wall on Floor 735'-0" with Safety Related Equipment and/or piping. 15
- 5. Masonry Halls on Floor 755'-0" with Safety Related Equipment and/or piping. 16 1
- 6. Identification of Equipment and Piping on Safety Related Masonry Walls on Floor Elevation 695'-0" 17
- 7. Identification of Equipment and Piping on Safety Related Masonry Walls on Floor Elevation. 715'-0" 22
- 8. Identification of Equipment and Piping on Safety Related Masonry Walls on F1,oor Elevation 735'-0" 28
- 9. Identification of Equipment and Piping on Safety Related Masonry Walls on Floor Elevation 755'--0" 32
- 10. Priority List of Walls 34
- 11. Priority List of Safety Systems 35 l
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. PRAIRIE ISLAND NUCLEAR GENERATING PLANT UNITS 1 & 2
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NORTHERN STATES P0'.!ER COMPANY MASONRY WALL DESIGN RESPONSE TO BULLETIN 80-11 _
1.0 INTRODUCTIOM 1.1 The report presents Northern States Power Company's sixty day response to NRC's IE Bulletin No. GO-11 for Masonry Wall Design for Prairie Island Nuclear Generating Plants Units 1 and 2.
1.2 Our review of the bulletin and Trojan Nuclear Plant's LER No. 79-15 indicates that the structural integrity of Concrete Masonry Walls is questioned by the Nuclear Regulatory Commission because:
1.2.1 Certain high energy and large diameter (greater than 2-1/2 inches) pipes are supported on the block walls as a routine design pro-cedure without adequate engineering review of the walls.
1.b.2 Use of non-conservative design criteria for the allowable inter-face shear and tensile stre',ses used for Double Wythe Concrcte Masonry Walls.
Problems of interpretation .if masonry wall code.
The difficul-1.2.3 ties in the interpretatjons are attributable to the fact that the design l'oads and the load combinations are factored loads based on ultimate strength method of design whereas the allowable stresses in the code are based on working stress design method.
2.0 DESIGN PHILOSOPHY 2.1 The review of design calculations and final safety analysis report for the Prairie Island Nuclear Generating Plant indicates that the concrete block walls do not fall into the same design philosophy as the design of masonry walls of Trojan Nuclear Plant which instigated the bulletin.
2.2 Concrete masonry walls of Prairie Island Plant were Penetrations, generally however, weredesigned as partition walls or as shield walls.
permitted in the masonry walls for pipes and ducts.
2.3 Attachments of both safety and nonsafety related equipment, ducts, pip-ing, electrical conduits, etc., were permitted only if their weights were insignificant.
2.4 The design of the plant was based on the work allowable design stresses existed.
of Unifonn Guilding Code of 1967.
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Page 2' l 2.5 Concrete masonry walls of the hydrogen room and probably those around the elevator shaft were designed' as shear walls.
l 3.0 TYPE OF C0'lSTP.UCTIO'l . ,
3.7 The construction and materials for concrete masonry walls in the plant were classified as Quality Assurance type I except for walls in the l administration building, service building and around toilet and sundry facilities which were classified as type III.
3.2 Inspection and Quality Assurance records for these walls exist at the plant. They will be reviewed prior to the detailed analysis of the walls.
3.3 The plant has approximately 275 masonry walls. Some of these are single wythe walls and others are double wythe walls. The walls are reinforced vertically and horizontally. In case of double wythe walls of 18", 30",
42" and 48 inches thickness, the two wythes are interconnected with lateral ties per Uniform Building Code,1967.
1 4.0 IDENTIFICATION OF WALLS .
4.1 IE Bulletin 80-11 requires identification of all masonry walls at the plant which are in proxinity to or have attachnents from the safety-related piping or equipment such that the wall failure could affect a safety related system. This phase of work. except for inaccessible walls, is completed, and the walls arp identified in Table 2 through 5.
4.2 The identification procedure consisted of sequen,tial numbering of each masonry wall in the Class I area of the plant. The areas excluded from consideration are the radwaste building, administration 7/8/8
,.. building, security or guard house and chlorine building. The walls in these buildings are not identified as they are not considered safety Class 1 areas. The walls in the reactor building have not been identified because of inaccessibility of the area at this time.
Walls in the reactor building will be identifded when the area becomes accessible, during plant outage.
4.3 The drawings were given to various disciplines (Mechanical engineering, Piping engineering, Electrical and Instrumentation and Control engi-neering Structural engineering)to identify walls with any safety re-lated system as defined in 4.1.
4J4 Field engineering survey of all numbered walls was conducted.
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4.5 The objective of the survey was:
4.5.1 To verify, to the extent possible, that all walls identified as having no safety related e':uipment in the vicinity indeed do not have any safety relataJ equip;;.ent in th2 vicinity.
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i 7/8/80 Revised by NSP
, .o 01-7450-280 Page 3 4.5.2 To recerd and to identify all safety and non-safety related equipment in the vicinity of the safety related walls, and to estimate loads transferred to the walls.
4.6 Two engineering teams were sent for the field survey. Each team con-tained exoerienced staff from the folicwing four engineering disciplines;
- electrical, instrumentation and controls, mechanical and structural engineering. The teams were under supervision of a Professional Engineer.
4.6.1 The project teams were furnished with block wall data forms and architectural drawings per Section 4.2. They were instructed to fill out the forms for each wall and attach photographs of the as-built calls whenever practical. The copy of the form used for the field work is given as Attachment 2.
4.7 The field data of all disciplines were compiled in the office. Systems and equiprent which could not be identified in the field were rechecked from the existing drawings.
4.9 Tables 6 through 9 provide lists of safety and non-s:fety related equip-ment for the walls identified in Tables 2 through 5, respectively. Table 6, for example, identifies equipment and piping for the walls listed in lable 2. In addition, in Tables 6 through 9, piping and equipment which are attached to the walls are distinguished frnm those which are in the vicinity. A priority number is 'also assigned to the walls.
S.O PRIORITIZATION OF WALLS 5.1 A safety evaluation report for all walls identified in Tables 2 through 5 will be transmitted to the Nuclear Regulatory Conmission within 180 days from the date of IE-Bulletin No. 80-11.
5.2 The walls are prioritized in three basic groups based on relative safety classification of equipment. The Following criteria are used for as-signing priorities to the walls.
5.2.1 Priority I Systems required to bring the plar.t to a safe Seeshutdown Table 1.1 or forto main-the sys-tain it in the safe shatdoun condition.
tems included in this group. . ;
5.2.2 Priority II I
- Systems associated with the safety of p; ant personnel in terns of .
radiation, service water, etc. See Table 11 for the system list.
,- I 5.2.3 Priority III All other safety desiqn Class I s. stern are included in this group. See Table 1.1 for the syste" list.
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- 21-7450-280 Pag 2 4 5.2.4 The relative priority of walls in each priority grous will be based on the number of safety systems attached to the walls.
Walls with multiple systems will have higher priority.
5.2. 5 ' The priority of. walls with equal number of safety related sys-tems will be fixed during re-evaluation stage based on the magni-tude of loads attached on the wall. Walls with heav,y loads will be re-evaluated first.
5.3 Table 9 provides the list of walls included in each priority group.
6.0 RE-EVALUATION OF THE DESIGN 6.1 Walls identified in Tables 2 through 5, will be screened in accordance with the following criteria oefore stress analysis of wall is undertaken.
6.1.1 Compare loads recorded on the data sheets with the loads for which the walls were originally designed. If additional loads were not added to the wall, then the wall will be consider ad to be safe and no further analysis will be done.
6.1.2 Loads of electrical conduits,1" and 1-1/2" diameter pipes, HVAC
- ducts, etc., which weigh less than 100 lbs. will not be considered.
6.1.3 The load of ducts and pipes which penetrate through the wall but are not directly supported by the walls will not be considered.
6.1.4 The walls which support edditional new loads in excess of 100 lbs.
or do not me'et construction acceptance criteria presented in Section 7. .
7.0 RE-EVALUATION ACCEPTAT'CE CRITERI A 7.1 Types of ?!asonry Walls Masonry walls shr'1 be classified as follows:
7.1.1 Load bearing walls and non-load bearing walls.
7.1.1.1 Load bearing Walls:
Walls designed to carry loads such as dead and live loads of floor slab in addition to those due to self
- weight and permanent attachments on it.
7.1.1.2 ?!on-load bearing walls:
Walls designed to carry loads due to self weight only.
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. , 21-7,450-280
. Page 5 7.l.2 Single Wythe and Multiple Wythe Walls 7.1.2.1 Single Wythe Walls:
Walls.which are one masonry unit wide.
_ 7.1.2.2 Multiple Mythe Walls: ,
. Walls which are more than one masonry unit wide.
7.1.3 Reinforced Walls and Unreinforced Walls 7.1. 3.1 Reinforced Walls:
Walls which satisfy minimum reinforcement and grouting requirements of 1967 USC code.
7.1.3.2 Unreinforced Walls-I Walls which do not satisfy minimum reinforcement and ,
grouting requirements of 1967 UBC code i 7.2 Quality Assurance 7.2.1 Quality Assurance records of masonry walls will be examined to compare the materials and type of construction in accordance with Sections 7.2.3 and 7.2.4 7.2.2 If tests made during construction indicate lower than specified ;
strength, then the design calc,ulations for the walls will be :
reviewed to check if allowable stresses were adequately reduced. l 7.2.3 Materials !
The following materials were specified for the masonry walls for Prairie Island fluclear Generating Plant.
7.2.3.1 Masonry Units - Lightweight or standard weight evenly textured, hollcu, load-bearing, modular concrete masonry units conforming to ASTM C90-66T Grade U-1.
7.2.3.2 Solid Masonry Units - Solid load-bearing concrete masonry units confonaing to ASTM C145-66T, grade U-l .
7.2.3.3 Horizontal Wall Reinforcing - Dur-o-wall truss or ap-
. proved equal. Deformed longitudinal ner.bers and galvn-
. ized crosstics. Unless otherwise noted on the drawinjs 3/16" longitudinal wires. 69 wire size reinforcing is called for on :he drawings. Reinforcement spacing shall be as per drawings.
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7.2.3.4 Vertical Reinforcement-Deformed reinforcing bars-ASTM-A615-68, grade 40. Lap, when required, 30 diameters.
Size of reinforcement steel and spacing as per drawings.
7.2.3.5 Metal Wall ties - #22 gage corrugated galvanized steel.
7.2.3.6 Mortar - Mortar complying with ASTM C476, type PL, with
_ following composition unless specified otherwise.
Portland Cement - 1 part Lime putty or hydrated lime - 1/4 to 1/2 parts Send 1/4 to 3 times the sum of the volumes of the cement and lime used.
7.2.3.6.1 Lime: ASTM C207, type S hydrated, or quick lime slaked to form lime putty conforming to ASTM C5.
7.2.3.6.2 Portland Cement: ASTM C150, type I, or AST'4 C175, type IA.
, 7.2.3.6.3 Sand: ASTM Cl44 well graded from coarse to fine.
7.2.3.7 Grout - Conforming to ASTM C476-63, fine grout type.
Aggregate conforming to ASTM C404-61, size 1 concrete sand.
7.2.4 Construction Construction specifications will be checked to see if good engi-neering specifications were provided for proper workmanship.
Inspection records will be reviewed to verify that poor workman-ship was not permitted.
7.3 Loads and Load Combinations 7.3.1 Loads 7.3.1.1 Dead Load l l
Dead load consists of the weight of the walls, the permanent loads from the attachments and floor dead loads supported by the walls.
- 7. 3.1. 2 Live Load
- Superimposed floor loads which are based upon the in-tended use of the ficor and the non-permanent loads of attachments.
7.3.1.3 Seismic Loads i
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Page 7 7.3.1.3.1 The floor accelerations and horizontal dis-placements shall be in accordance with the topical report FAB-PS-02 prepared by John A.
Blume and Associates for the Prairie Island
.- Nuclear Plant.
-. 7.3.1.3.2 Damping factor shall be 5% of critical.
- 7.3.1.3.3 To compute inertia loads the acceleration for a wall shall be determined by taking average of accelerations of floors above and below the wall.
7.3.1.3.4 Story Drift Loads shall be computed using the maximum horizontal relative displacement of the wall.
7.3.1.4 Loads due to thermal expansion of the pipes will be in-cluded.
7.3.1.5 Loads due to thernal gradient, wind, operating pressure, accident pressure, pipe rupture, etc., will~be included when applicable.
7.3.2 Load Combinations The following load combinations will be used:
- 1. Dead Load + Live 1.oad
- 2. Dead Load + Live Load + Thennal Expansion Load
- 3. Dead Load + Live Load + Thermal Expansion Load + Operating Basis Earthquake
- 4. 2/3 (Dead Load + Live Lead + Thermal Expansion Load + Design Basis Earthquake)
The load cer.binations will be as per Table B.6-1, Appendix B, of the FSAR when loads cited in Section 7.3.1.4 are involved.
7.4 Analytical tbdeling 7.4.1 The walls will be modeled as beams or plates. The end conditions ~
will be considered as taing fi).ed, simale supports er free'. Gt. . Je
- lines for boundary conditions are given in Section 7.4.2.
I 7.4.2 Boundarv Conditions 7.4.2.1 Fixed: When reinforcement is adequate to resist fixed end morents and shears.
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. 21-7450-280 Page 8 7.4.2.2 Simply Supported: When an edge is connected to a slab, floor or another wall to provide sufficient shear capacity that will prevent relative translation at the joint but will permit end rotation.
Joint between wall and the slab with a compressible material between them does not qualify as simple support.
7.4.2.3 Free: When an edge has no connection with another wall or slab or has a connection not capable of transferring j required amount of shear and/or moment to qualify as a l simple or fixed support. {
7.4.3 Single Wythe Walls 7.4.3.1 Walls will be checked for both in-plane and out of plane loadings. Walls will be checked for its cverall safet/
as well as local integrity at the load attachments.
7.4.3.2 For local behavior, punching shear, pull-out of con: rete block, local bending, shear and compression on the block at load application will be investigated.
7.4.3.3 1.ocal strength evaluation will also take into account modifications due to Bulletin 79-02.
7.4.3.4 Overall behavior of walls will be investigated for all loads including loads from safety as well as non-safety related sys.tems . .
7.4.3.5 Tables and charts may be prepared to establish allowable loads for local and overall behavior'of walls. ,
7.4.4 Multiple Wythe Walls 7.4.4.1 Following additional criteria will be used for Multiple Wythe walls.
7.4.4.2 For local strencth evaluation it will be conservativelv assurred that only or.e wythe shall support the tensile ' loads nonnal to the walls.
7.4.4.3 If one wythe is not sufficient to support the tensile load then composite action (more tnan one wythe acting tog 2:ner) will be considered provided the tensile stresses bet'..22n the wythes do not exceed 25 psi. ,
7.4.4.4 If a value greater than 25 psi is required to satisfy the composite behavior then justification will be given in the form of accepted industry staniiards or test data.
Otherwise, corrective action will be proposed.
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21-7450-280
' Page 9 7,4.4.5 For overall bending of the wall the vertical shear transfer through the morter between wythes will be calculated using fornula VQ/IB.
7.4.4.6 If the snear stress exceeds the allowable shear stress
- then each wythe will be considered separately. The distribution of lateral loads shall be taken in prcpor-tion to the relative stiffness of the wythe.
7.5 Allowable Stresses Allowable stresses for the masonry walls shall be as per Table 1 conforms to ACI 531-79.
7.6 Codes and Documents The evaluation of the masonry walls shall be governed by the 1967 edition of the " Uniform Building Code (UBC) unless otherwise noted in this report or in the final safety analysis report (FSAR) for the Prairie Island Nuclear Plant. ,
7.7 References
'1. Building Code Requirements for concrete masonry structures (ACI 531-79) and commentary (ACI 531R-79); American Concrete Institi te, Detroit Michigan, 48219.
- 12. Topical report JAB-PS-02 for Prairie Island Nuclear Plant:
John A. Blume and Associates, San Francisco, Calif.
J. Dur-o-wall, Technical Bulletins: Dur-o-Wall Inc. Baltimore, Md. 21237.
a4. LER 79-15 & Supplements 1 through 4; Trojan Nutlear Plant, Portland General Electric Company, Portland, OR. 97204.
- 5. General Conditions for contracts a:1d specification for Prairie Island Nuclear Generating Plant; Northern States Power Company, Minneapolis, Minn. 55401.
- 6. Final Safety Analysis Report (FSAR), Prairie Island Nuclear Generating Plant: Northern States Fower Company, Minneapolis, Minn. 55401.
- 7. Uniform Building Code,1967 Edition: International Conference of
- Building Office, Pasadena, Calif. 91101.
8.0 PROJECT PLAN 8.1 The design re-evaluation of all masonry walls identified in Tables 2 throurh 5 shall be cocpleted before .';avamber 3,1930. The walls not listed in the tables because of their inaccessibility will be investi-gated at the earliest opportunity. The block wall design investigation will be accomplish;d in accordance with the following project plan.
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Starting Completion 8.2 Activity Date Date A. Description of Itasonry !!all 7/7/30 7/18/80 B. P.eview QA and Inspection Reports 7/11/80 7/25/80 C. Re-evaluation of Priority I Ualls 7/21/30 8/30/80 D. Field Inspection of Prioi'ity Walls Requirir.g Fadifications 8/ 31/30 9/5/80 E. Re-evaluation of Priority II Walls 8/6/80 9/19/80 F. Field insoection of Priority II and III walls requiring modifica-tions 9/20/80 9/30/30 G. Field ins;ection of Priority II and III walls requiring modifi-10/15/80 cations 10/1/30 H. Re-evaluation Re' cort ~10/16/80 1,0/31/80 8.3 A brief description of work planned in each activity is described in the subsequent sections.
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80.1 Descriction of Masonry Walls In this phase safety related masonry walls will be classified in ac-cordance with their function, type of construction (single or doable wythe walls), reinforcement requirements and Quality Assurance re-quirements. The information in this phase will be obtained from the structural drawings rel, eased for construction of the walls and existing design calculations.
8.3.2 Review of Quality Assurance and Insoection Reports Quality Assurance and inspection records for the masonry walls will be examined and compared with the materials and construction !
methods specified. Discrepancies found will be documented. !
8.3.3 Re-evaluation of Priority I Walls Structpal integrity and margins of safety for the walls in Priority I will be inicstigated in this phase for the loads and load combi-nations proposed in the re-evaluation criteria. Both local and overall behaviors will be considered. Only those walls which are subjccted to loads more than criqinal design loads will be re-viewed. Malls which fail to reet re-evaluation acceptar.ce criteria may be farther scrutinized for the actual values of loads and tne analytical model used for computation of stresses.
Modificatio'r.s either in the form of reduction of loads or strengthening of walls will be proposed for walls found ceficient.
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Page il 8.3.4 Field Inspection of Priority I Walls Requireing Modifications:
A field investigation to verify the practicality of the proposed modifications will be perforr.ed.
8.3.5 Re-evaluation of Priority II Walls Activities involved in this phase are similar to those in Section.
8.3.3.
8.3.6 Re-evaluation of Priority III Walls See Section 8.3.5.
8.3.7 Field Inscection of Priority II and III walls Recuiring Modifications See Section 8.3.4.
8.3.8 Re-evaluation Report A detailed report will be presented for the safety related walls.
The report shall discuss s tuf ts of activities in Sections 8.3.1 through 8.3.7. The repor. . 11 also present a schedule for wall modification.
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Response to IE Bulletin 80-11 217450-280
. Page 12 TABLE 1 -ALLO'!ABLE STRESSES IN PASCNRY-INSPECTED WORK").MSHIP (For Notation and Definitions See ACI 531-79)
Allowable Stress,(psi . U.M. )
Description Related to fin Maxiaum Compressive:
Axial For Masonry Walls F a .225 fm' 1-(h/40t)3.
1000 Axial for Masonry Column Pa (.225 fm' An + 0.65Asf s) x$1-(h/40t)3] lbs.
Flexural Fm 0.33 fm 1200 Bearing ,
0.25 fm 900 On full area Fa On one-third area 0.375 f' 1200 or less Fa Shear No Shear reinforcement Fle ural members vm 1.1 6 50 Shearwalls 0.9/fhi 34 M/VDy y_ 1 vm M/Vdy <1 vm 40 2.0/ fsi l (1.85 - M/Vde)
Reinforcement taking entire shear Flexural members Shear Walls v 3.0 [ -
150 M/Vdy 2.1 y 1.5 /f' 75 M/Vdy <1 y 2.0/ fin 45 (2.67 - M/Vd,' ,
. Tension l
No tension reinforcenent.
1' Tension normal to bed joint:
0.5/mo 25 Hollow units Ft Solid and/ar 40 grouted units Ft 1.0/m o Tension parallel to bed joints in running bond "
50 Holicw units F t I.0/m o l l
Solid and/or 80 grouted units F t
1.5 8 o~ '
Mo< lulus or elasticity 1000fdi 2,500,000 Em 400 f,'n 1,000,000 Modulus of rigidity Ey l -
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9 ,,,gy g g p uvy= M 3 crtvsb Response to IE Bulletin 80-11 217450-280 Page 13 TABLE 2 Masonry Walls on Floor 695'-0" with Safety Related Equipment and/or Piping.
BUILDING PHYSICAL LOCATION OF WALL IDEr(TIFICATIO1 WALL IDENTIFICATION WITH RESPECT TO PLA*;T COLUM" RO'. S
- NO.
. Turbine Building 1 Between Aa and Ab on 9 Turbine Building 2 Between A and B on 9 Turbine Buildi g 3 Between B and C on 9 Turbine Building 4 Between C and 0 on 9 Turbine Building 5 Between 8 and 9 on D Turbine Building 6 Setween 9 and 10 on D Turbine Building 7 Between D and E on 9 Turbine Building 8 Between E and F on 9 Auxiliary Building 12 Between H and G near 6 Auxiliary Building 12A Between G and Ha on 6 Auxiliary Building 13 Between H and G near 6 Auxiliary Building 15 Between H and G near 6 Auxiliary Building 18 Between 7 and 8 on H Auxiliary Building 19 Between 7 and 8 On H -
Auxiliary Building 20 Between 7 and 6 near H Auxiliary Building 21 Between 11 and 12 near H Auxiliary Building 22 Between 10 and 11 near H Auxiliary Building 23 Between 11 and 12 on H Auxiliary Building 24 Between 10 and 11 on H Auxiliary Building 25 Between 10 and 11 on H Auxiliary Building 27 3etween J and K near 13 Auxiliary Building 28 Between J and K near 11 - Auxiliary Building 31 Between 10 and 9 near J Auxiliary Building 32 Between J and K on 8 Auxiliary Building 33 Between J and K near 8 Auxiliary Building 34 Between 7 and 8 near J Auxiliary Building 35 Between J and K on 7 Auxiliary Building 36 Between 5 and 6 on J Auxiliary Building 37 Between 5 and 6 near J Auxiliary Building 38 On K at 9 Auxiliary Buildir.g 39 Between 9 and 10 near K Auxiliary Building 40 Between J and K on 9 Auxiliary Building 45 Between L and M on 7 Auxiliary Building 48 Between L and M on 11 Auxiliary Building 55 Between N and P near 6 Auxiliary Building 59, Between M and N near 7 f
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Response to IE Bulletin 80-11 l 217450-280 1 Page 1:4
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TABLE 3 -
. Masonry Walls on Floor 715'-0" with Safety Related Equipment and/or Fiping WALL IDENTIFICATI0ti PHYSICAL LOCATIO!i 0F WALL BUILDI1G NO. WITH RESPECT TO PLANT COLUMN R0WS '. IDENTIFICATION 23 . Between C and D near 9 Turbine Building 25 Between 9 and 10 near F Turbine Building 26 Between 8 and 9 near F Turbine Building
} 27 Between 8 and 10 near G Auxiliary Building 28 Between G and Ja near 10 Auxiliary Building 29 Between 8 and 10 near Ja Auxiliary Building 30 Between G and Ja near 8 Auxiliary Building 34 Between H and J near 12 Auxiliary Building l 35 Between 11 and 12 near H Auxiliary Building 36 Between 11 and 12 near J Auxiliary Building 37 Between 11 and 12 near J Auxiliary Building 38 Between 11 and 12 near J Auxiliary Building 39 Between 10 and 11 near J Auxiliary Building 43 Between 9 and 10 near K Auxiliary Building 44 Between K and J near 9 Auxiliary Building 45 Between 8 and 9 near K Auxiliary Building 47 Between 7 and 8 near J Auxiliary Building 48 Between 7 and 8 near K Auxiliary Building 51 Between H and J near 7 Auxiliary Building 52 Between 6 and 7 near J Auxiliary Building 53 Between H and J near 6 Auxiliary Building 61 Between G an'd J near 6 Auxiliary Building 66 Between 5 and 6 near H Auxiliary Building 69 Between 4 and 5 near H -
Auxiliary Building 74 Between 3 and 4 near H Auxiliary Building 79 Between 11 and 12 near L Auxiliary Building 79A Between 11 and 12 near L Auxiliary Building 81 Between 10 and 11 near L '
Auxiliary Building 82 Between 8 and 9 near L Auxiliary Building 83 Between 8 and 9 near L Auxiliary Building 85 Between 7 and 8 near L Auxiliary Building 86 Between 7 and 8 near L Auxiliary Building 87 Between 6 and 7 near L Auxiliary Building 87A Between 7 and 8 near L Auxiliary Building 90 Between 7 and 8 near P Auxiliary Building 91 Between 7 and 8 near P Auxiliary Building 92 Between 11 and 10 near il Auxiliary Building 93 Between 11 and 12 near fl Auxiliary Building 94 Between M and N near 11 Auxiliary Building
. 95 Between 11 and 12 near N Auxiliary Building 99 Between 11 and 12 r. ear ti Auxiliary Building 100 Between N and P near lla Auxiliary Building 101 Between 11 and lla near N Auxit iry Building 102 Between 11 and lla near P Auxiliary Building 103 Between N and P near 11 Auxiliary Building 201 Between 1 and 2 near J Auxiliary Building 203 Between G and J near 2 Auxiliary Building
+.
- ~
s Response to IE Bulletin 80-11 217450-280 Page 15 TABLE 4 Masonr.) Walls on Floor 735'-0" with Safety Related Equipment and/or Piping WALL IDENTIFICATION ' PHYSICAL LOCATION OF WALL BUILDING NO. WITH RESPECT TO PLANT COLUMN R0WS IDENTIFICATION l . Between G and H near 13 Auxiliary Building 2 Between G and H near 12 Auxiliary Building 3 Between J and G near 13 Auxiliary Building 4 Between G and H near 12 Auxiliary Building 5 Between H and J near 12 . Auxiliary Building 6 Between 12 and 13 near H Auxiliary Building 7 Between 13 and 14 near H Auxiliary Building 8 Between H and J near 12 Auxiliary Building 10 Between 11 and 12 near J Auxiliary Building 11 Between H and J near 11 Auxiliary Building 13 Between J and K near 11 Auxiliary Building 16 Between N and P near 11 Auxiliary Building 18 Between 10 and 11 near P Auxiliary Building 19 Between 7 and 8 near P Auxiliary Building 19A Between H and P near 7 Auxiliary Building 21 Between J and K near 7 Auxiliary Building 23 Between 6 and 7 near J Auxiliary Building 26 Between H and J r. ear 6 Auxiliary Building 27 Between 6 and 7 near H Auxiliary Building 34 Between G and H near 6 Auxiliary Building 35 Between G ,and H near 5 Auxiliary Building 36 Between G and J near 5 Auxiliary Building 37 Between H and J near 6 Auxiliary Building 38 Between 5 and 6 near H -
Auxiliary Building 39 Between 4 and 5 near H Auxiliary Building m
QW9 e
t FLUOR POWER S3RVICES,lNC.
Response to.IE Bulletin 80-11
~
217450-280
~
TABLE 5 Masonry Walls on Floor 755-0", with Safety Related Equipment and/or Piping WALL IDENTIFICATION PHYSICAL LOCATION BUILDING NO. WITH RESPECT TO FL C T COLUMN R0WS IDENTIFICATION 1 Between G and H on 9 Auxiliary Building 2 Between 9 and 10 on H Auxiliary Building 3 Between 7 and 9 on H Auxiliary Building
- 9 I e
l l
O e
S J
._ = - - - -- __. ._ _
Response to IE Bullein 80-11 FLUCR POWER S~ERVICES.INC. 217450-280
. TABLE 6 Page 12 IDENTIFICATION OF EQUIPMENT AND PIPING ON SAFETY RELATED MAS 0::P.Y WALLS ON FLOOR ELEVATI0t 695'-0"
! SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM WALL SUPPORTED' PROXIMITY SUPPORTED PR0XIMITY NO. ON WALL TO WALL ON WALL TO WALL PRIORITY l B-Train-EB (1) (6) Tray or III Pull Box Conduit Pene.
2-1/2" Pipe- -
I.P.
Bus Duct -
6 - Conduits -
GRO Bar - '
12" Line - FP PP, CP 2-Pipes I 3 A-Train - ZT
- 6-Items B-Train - ZT SWGR -
- 16 Items 18" Line - CL' 2" Pipe - CP 2-1/2" Line - I 4 A-Train - UE III Unit 1&2 5 A-Train - UE III B-Train - UE '
Unit 1 6 A-Train - UE III B-Train - UE ,
Unit 2 7 B-Train - UE Units 1&2
. Duct - III
~
8 Distr. Pnl-EX B-Train - UE : Test. Cab SA, ZE III A'-Train - UE ' Contr. Box Panel Box-EX Fan - ZE Filter - SA 3 - 2'2" Pipes-SA 2-2" Pipes ~E Pump -
Air Comp. - SA
- SEE FIELD I: ATA Sih.ET FOR IDE:;iiFICATla';
(1) FOR DESCitIPTION OF SYSTEtt ALPilABETIC CODES SEE ATTACHMENT 1.
.. t FLUOR POWER SERVICES,lNC. ' . ,
TABL5 6- (Cont'd. ) Response to IE Bulletin 80-1.
IDENTIFICATI0!! 0F EQUIP"ENT At:0 PIPIllG 217450-280
'UN SAFETY RELATED MASONRY llALLS Ott Page 8 FLOOR ELEVATIO!! 695'-0" Page - 2 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM SUPPORTED PROXIMITY SUPPORTED PROXIMITY WALL _.
PRIORITY ON WALL TO WALL ON WALL TO WALL NO. -
8 3 Lines - SA 1 Line - CL 2 Lines - UE PI 11114-CL PI 11117-SA
. PI 11202-SA PI ll435-SA PI 11436-SA PI 11487-SA PI 11488-SA PI 11555-SA PI 16028-UE PI 16246-SA PI 16253-SA
(' PI 16461-SA III 12 A-Train Switch-AC Pull Box !
3-Transf. - UEl.
FX; ZE, ZH DC, AC 12A RH, CC, .
1" Pipe-RCCH Cmpt. Coolin'g 2-4" Pipes- Lines - CCH I RHRH 4" Pipe FP DCS 18251 - CC Air Junction Cox
- SA 2h" Pipe-ZH :.
13 10" Pipe - CCH 2Y' Line-CHR .
I 8" Pipe - FP 6" Pipe-CW I
15 Pull Box - MCC Bus & B-VC, DC Train !
RH.VC.RD,CC, EB 2-Trays 1AG RH,VC CC,ZE, DC,RD 6" Pipe - FP
^
- 45" Tubing-CC l
l
, p __ _
TABLF 6 - (Cont'd.) 'e Rasponse to IE Bulletin 80-11 IDENTIFICATION OF EQUIPf1ErlT Af;D PIPING 217450-280
.DN SAFETY RELATED MASONRY WALLS ON Page 19 FLOOR ELEVATION 695'-0" Page - 3 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM SUPPOP.TED PROXI4ITY SUPP'ORTED PR0XIMITY WALL ,
PRIO11TY ON WilLL TO WALL ON WALL TO WALL NO. !
II 18 Box 1195-VC Splice Box & !
B-Train Cond. !
-ZE VC #13 Meter .
I&C Manifolds with 3 Mount-ing Plates Fan-ZE A-Train Splice . P8 1196-VC .I -
19 '
Box - ZE,VC I .II.
20 Y Pipe-ZE Pull Box-ZE . ,
Control-VC Box - VC Duct 9x9 III (2) Fan, 21 Conduit Box ,
III 22 Box 2480 Phone - CU B-Train Box-VC Chargin9 Li9h t - EL Pull Box-VC I 23 2AVB ZE Pump - VC ' Pump Meter 2AVB ZE 9"x9" Duct .
-VC t Chrg. Pump-VC RA Speaker-CU Pull Box-VC I 24 2HVA ZE Pump Motor 2HVA ZE I
25 2HVB ZE Chrg. Pump-VC , PA Speaker-CU Pull Box - VC ,I .
RHVB ZE l Pump "a'.or 9x9 Duct Duct - ZE 3-Mounting il 's
- . for ISC PI's I
w wsns.=nvrus-7=--
TABLE 6 - (Cont'd.) Response to IE Bulletin 80-l' IDENTIFICATION OF EQUIP!*ErlT AND PIPING 21-7450-280 ON SAFETY RELATED l',A50f;RY WALLS 0:1 Page 20 ;
FLOOR ELEVATION 695'-0" j Page - 4 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM PROXIMITY SUPPOR'ED PROXIMITY WALL SUPPORTED - MIORITY TO WALL ON WALL TO WALL NO. ! ON WALL A-Train - CL Vent Supp. I 28 3/4"O Line
-ZE VLV
~
31 Box - CC B-Train - RD PI ll349-AS .I DPT 23096-CC I 32 A-Train - Analyzer -
RD & GC A-Train - ZE FT-23087-CC Equipment
33 1" Line-CCH Box - ZX (2) I 34 2-Pull Boxes H02
-ZX Filter - RH 18412 - WL 18413 - WL '
24073 - WL i 4 Boxes - ZX I 35 Box 1268 - CL RB Sca. - CL 3 1"3 Tubing
& Junction Box HVA-93 HVA-1 C51107 f 1
I 36 '9-Conduits-CS i I I 37 Snubber- RHH Pull Box - SI i SI Line PI 11259 - SI Nitrogen Line-NG III 38 .~ F71 Line - UM i 2-Brackets &
N , 3/4 Line 1 - B'i S U? ?-::G l 2 PI ll295-!;G l
CU 31232-:n
'SEE FIELD DATA SitCEI FCil ICZ'iTIFICATIGri
)
1 wo
+
{
t IFICA 1 F EQUIPf*ErtT AND PIPING o IE Bulletin 80-11 21 8
. ON' SAFETY RELATED LSONRY WALLS Ott Page 21
. FLOOR ELEVATION 695'-0" Page - 5 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM WALL SUPPCRTED PR0XIMITY SUPP09.TED PROXIMITY NO. _ ON WALL TO WALL _0_N WALL TO WALL ' PRIORITY 39 B-Train & Tray I HT,WG,WL.C0 CT,FX,CC, CP,CU .
Tray -VC .
4" Line - CC 4" Duct - UM 40 Box, A-Train 2(A-Trains) Box - HT
- UE 2-4" CC Lines 1-4" SS I .
1-3" SS 45 Duct 18x18 2-Boxes -
Aux.Sidg. Vent i Equipment (Special) 6-Items
- II CU 31789-WL CU 31790-WL 48 3" Waste Gas A&B Train Cond. N2 line - NG N2 Line - NG I Lines (2)-WG Tray-VC MP,WL' 3 Relief Line HT,EB Brackets Tray - MS CL, .
CU,WG ,FU, .
CP,WL,RD DC Tray-AC ,CU , RD 55 B-Train Cond. Conduits - EL 10x8 Air Duct SB Fil ter To Containment 6-l" Lines-WG I 59 Filter 9x9 Duct (2)
& Regulator Diesel Gen Exh'
-ZD,5Y Fire Protec.
Line - FP I A-Train & Box
-ZD B* Train - ZD -
"SEE FIELD DATA SHEET FOR ILCTIFICATI0tl
,g _ . _
awnxam-xs
. 3 . TABLE 7 Page 22 IDENTIFICATION OF EQUIPMENT AND PIPING ON SAFETY RELATED PASONRY WALLS ON FLOOR ELEVATION 715'-0" SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM WAL-L SUPPORTED PROXIMITY PROXIM'ITY NO .- ON WALL TO WALL l ON SUPPORTED WALL TO WALL PRIORITY 23 B-Train CND(2) Numerous .,
III
-UE Security CNDs Bus Duct -
Vent Duct -
\" Copper Tube 25 Tray-AF, CC, Trays-CW, RM Ltg. Supp CND-Normal I MS, ZR CO, CU i Tes t PNL-CA Tray-EB, DC Trays-AT, EA ' 2 - Duc ts -
MT, HD, CW, CL RH Chilled Water ' 2-Thermostat- Valve .
-t System - ZH j ZH 26 Tray-EB, DC A-Train, 3-CND' Test Cab-ACB Bus Duct- I Disc. SW -EB Tray-DC, AT, . Pull Box RPA5 FW, CD, RC & : Tray-CU, CL, 2 - Duct -
Test PNL - EA (6) B-Train i SA, CW, F0, FP 2 - Pipes -
'2 Normal GND Chilled Water ! (2) Thermo- Valves System - ZH stats - ZH , C\ 31757 CV-31758 27 Pull Box - CU I to -
30 NOTE: Relay room walls safety related, outside walls' computer room non-safety related. .
27 Yes Yes to Relay Room 30 NOTE: ALL systems in the plant that are controlled or monitore'd from control room run thru this rocm.
34 PNL 2111 Heat Trace-VC Note: East Wall Inaccessible I (Boric Acid
. System)
B-Train
- Equip. (See Field Data She'et)j (8-Items) ;
(1) FOR DESCRIPTION OF SYSTEM ALPHABETIC CODES SEE ATTACHMENT 1.
W
, 6
- TABLE 7 - (Cont'd. )
IDENTIFICATION OF EQUIPMErlT AfiD PIPI!;G ON & Response to IE Bulletin 80-11
' SAFETY RELATED MASONRY WALLS ON 217450-280
. FLOOR ELEVATION 715'-0" Page 23 Page 2 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM WALL SUPPORTED PROXIMITY SUPPORTED PR0XIMITY NO: ON WALL TO WALL ON WALL TO WALL PRIORITY 35 Panel'-NI Trays-AC, II, Duct - AC III NI -
Pull Box -
NOTE: Inaccessible "A" train on south wall.
36 Vent Control Control Valve I PNL-HC, DPI(2)
NOTE: Inaccessible "A" train on north wall.
37 Inaccessible "A" train on south wall. III 38 Inaccessible "A" train on east wall. III 39 2 "A" Train 1" Pipe I CND - AC Test Panel-VC, SM, SF, Nitrogen Lines .
1" Pipe ,.
43 HT (4-Item.s) Boric Acid Trays-VC, HT Pumps-HT, -
Tubing-HC I 44 Chem. Vol. 2" Lines- I Control Line-
- VC -
45 4"-Line- Duct- U;: Pull Box
- Equip II UM .
5 Itens Boron Panel .
47 "A" Train #122 Monitor III
- UE Tank Pump Discharge Lines-R"U, RM, )
' ~
3" Line- L"1 ~ .
3" Line-i3 1
- TABLE 7 - (Cont'd.) Response to IE Bulletin 80-11 i
IDENTIFICATION OF EQ'JIPMENT AND PIPING ON )
SAFETY RELATED MASONRY WALLS ON 217450-280 <
FLOOR ELEVATION 715'-0" Paga 24 i Page 3 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM PR0XIMITY SUPPORTED PROXIf+1TY WAli. SUPPORTED PRIORITY NO .~ ON WALL TO WALL ON WALL TO WALL 48 Panel-IP, SI Sound Phone-CU" I ZR, ZG, WL , MS - -
ZT HT, H2 0, Lines 2" Line -NG 51 Inaccessible - Safety related equipment inside. yyy Elec.PNL-HC 2-Lines- UM lb" Pipe I 52 Tray - UE 1" Pipe - SS
' Tubing to Air Junction
, Panel-HC Box - HC 53 Pull Box-VC Instr. Sta-VC I i
(Numerous Instr.)
- Equip, NOTE: West wall inaccessible.
6-1 tems l
I 54 Inaccessible - High radiation, locked door. III i
66
- Equip Duct-ZD
- Equip III (5-Items) (6-Items) .
II 69 Exhaust Fan-ZL Control Panel-Ter. Box -
Contr. Sta.-
Ter. Box-ZC
'Contr. Sta.-
TB-A1064-PP Water Heater I 74 Tray-EG,EB,0C Tray-CA EG,0C, Pull' Box- -
ZG,
- See Field Data Sheet e
e
' TABLE 7 - (Cont'd.)
, IDENTIFICATI0Il 0F EQUIP.ENT AND PIPING Response to IE Bulletin' 80-11 Os SAFETY RELATED '.ASZRY WALLS ON 217450-280
'. FLOOR ELEVATION 715'-0" Pag 2 25 Page 4 SAFETY RELATED SYSTEM- NON-SAFETY RELATED SYSTEM WALL- SUPPORTED PROXIMITY SUPPORTED PROXIMITY NO. ~ ON WALL TO WALL ON WALL TO WALL PRIORITY 79 2"-Line-SI A&B Train 2"-Line
- Equip '
I CND (34) 4-Items Trays (3) with ;
20 systems 79A 2-Lines-S'4 B-Train-DC !
^
Distr. PNL
- 4-Items (Mech)j -
Valve Handle-VC l I 81 82 Valve Handle-VC I 83 Valve Handle-VC I 85 Chemical Vol 3-Val ves-WL I
~
Pipes-1" & 2"- .
- - VC 86 Pipe-VC Normal CND I Drain Line-87 Distr. Panel- Numerous A & B , III WG, PS, Train CND.
4-Reg. & Filter PS(2) l on Valve-S'4 l
- . WG(2)-SM 10 Cond (Unknown) 2-Boxes-SM 20 Cond B-Train ~
4 Cond A-Train
- Tray (10 systems)
~
. - UE -
87A ,
B-Train Distr. Panel- 10-CND I
. 2-Boxes-SM VC, ZN, WL, RP,;1
- *5 Items SM, ZA, ZS, ZP,! -
.- SB, WG, MS, CA,
' ' FW .
- Equip (Mech) 7 Items l
~
- See field Data Sheet ! '
i
-.;-- l
- TABLE 7 - (Cont'd.) ,
R sponse to IE Bulletin 80-11
. !DENTIFICATION OF ECUIP"ENT AND PIPING ON SAFETY RELATED MASONRY WALLS ON 217450-280 FLOOR ELEVATION 715'-0" Page 26 Page 5 SAFETY RELATED SYS' TEM NON-SAFETY RELATED SYSTEM WAtl SUPPORTED PROXIMITY SUPPORTED PROXIMITY NO. ON WALL TO WALL TO WALL PRIORITY l ON WALL i
90 Tray-CU, MS, AC Pull Box-CU Tray-EL, HS DC, HT, WL, CP i ~
CP 1 8" Line-SF i 8" Line-CC 2-Pipes 4" Line- UM ,
91 1" Pipe-CC ' Recept-EL Tray-EL,HS I CP 8" Pipe-CC l Pull Box-CU 8" Pipe-SF Emerg. Light Tray-CP, CU WL, DC, AC, HT 4" Pipe-lb" Pipe-DE
- 1h" Pipe-92 Compressor-WG 3-Condui t III B-Train - UE ,
InsteCU 93 Pull Box-WG Pull Box d'G WG(3) WG Lines III 94 Pull Box-WG -
6-Pull Box-WG I CV-31963-WG 95 Press Transf- Conduit-EL 3- Condui ts III WG Air Supply
. Station 99 4-CNP- WG CV 31454, 55, III
& 56 3-CND . UE 100 A-Train-WG Compressor WG '
WG(DPI & FE) . .
Limit Swtch-WG "B" Train Cond.
. Control Valves *
& Instrut.-UE 101 .
Compres so r-WG 3-CND UE III
~
Control Valve
& Instrs.
. g
-n G- en -
TAB 1E / - (Con 8'd.)
IDENTIFICATION OF. EQUIPMENT AND PIPING Response to IE Bulletin 80-
.ON SAFETY RELATEd MASONRY WALLS ON 217450-280
FLOOR ELEVATION 715'-0" Page 27 Page 6 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM WALL SUPPORTED PROXIMITY SUPPORTED PR0x!MITY NO. ON WALL TO WALL ON WALL TO WALL PRIORITY 102 Compressor-WG Telephore-CU III Pull Box-WG Control Valves '
& Instr.
103 Compressor-WG Horn-CU 4-CND-EL, III i CO, MS "A" Train Cond 4-CND-Spares 2-CND-WG 201 Term. Box- Panel-EL III .
ZG 203 B-Train-DC, ZG Pull Box-ZG Fire Line-FP III Trays-SBM-L4 Ltg. Pull 2-Ducts-SBM-T3 Box-A-Train CND- ! . . e' DC , ZG , CU , ZT ,' -
AC,PC,EL,MPl E
o O
e l
e e
O
.~
e S
e 4
e SWW W
, 4 e -
o . 2575i0-280 TABLE 8
- Page 26 IDENTIFICATION OF EQUIPf-iENT AND PIPING ON SAFET RELATED MAS 0ilRY WALLS O'l FLOOR ELEVATION 735'-0" 3AFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM WALL
~
SUPPORTED PROXIMITY SUPPORTED PROXIMITY NO. ON WALL TO WALL Off WALL TO WALL' PRIORITY 1 A-Train Conduit 2-4" Cond. NIS-N' Pull Box - CU I Conduit - RP (l) Cond. Train A-EG Bus 210 SWGR ,
A Train - .
AF,HC,MS,NI,RC, RD,RH,SI,VC,ZK, ZS 2-2" Insulated Blue - ZW 3/4" CU Line-VLV 2 Gus 210 Control 2-4" Cond. flIS-NI GRD Bar - GC I Sta. - ZH Bus 210 SWGR Pull Box - ZH A-Train - AF,HC MS ,NI , RC , RD, RH ,
SI,VC,2K,ZS NIS Cond's.-NI 3-4" Pipe Sup- 4-4" Pipe Pen Duct ports 4" SS Pipe-AFD RHRH '
1 " CU Tubing II 3 B-Train Cond. Tray Cond.-DC,RP, Card RDR-SU .
(EB) Bus 220 B-Train Phone Box - CU B-Train Cond. S'.lG R- AF ,H C . MS , fil , Conduits-CU (ZH) RC,RD,RH,SI,VC,2K, A-Train Cond. ZS 3/4" CU Line-CD 3/*" CU Tubg.-CD ,
15" CU Tubing-CD l Chiller - ZH 4 Tray - RH,EB, Bus 220 SWGR I ZH,HC B-Train Tray - DC.RP AF,HC,MS,NI,RC, RD,RH,SI,VC,ZK, ZS 2-2" Pipe Blue -
RHRH 4"xS" Exhaust Duct from Instr. Lab ,
(1) FOR D;SCRIPil0:10.7 StS!EP ALPilAutT!C CODES SEE ATTACH::Ei.T 1.
\fUGELI.TituSWMMcNJR16 TABLE 8- (Cont'd.)
/ Response to IE Bulletin 80-11 IDENTIFIC'. TIC:t 0F EQUIP"ENT "%D PIPING Oil 217450-280 SAFETY RELATED MASONRY WALLS ON Page 29 FLOOR ELEVATION 735'-0" Page - 2 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM SUPPORTED PROXIMITY SUPPORTED PROXIMITY WALL TO WALL ON WALL TO WALL, PRIORITY NO. - ON WALL Tray - RH Cond's.-EB,ZH I 5
Tray - EB,ZH,HC Feed Water Flow Inst. Devices DPT 23027823028 4" SS-AFD 6 Pull Box-ZH MCC ELA - AF.CC, Comm. Pull Box I B-Train - EB EB ,MS ,PS ,RH ,SI ,VC l A-Train - UE 2-3" SS Pipes-FW B-Train - UE 3-6" SS Pipes-FW, MS Exhaust Duct frcm Instr. Lab 7 Pull Box - ZC NIS Cond's.-NI Pull Box - CU. Misc. Cond's. III HVAC Pnl. - ZC Pull Box - EL 14" Copper Tub- lk" CU Tubing-CD 1" Pipe Res-ing - CP traint 8 Pull Box-NI FW , Ltg. Panel 11 Pull Box-HI,FW 2 for B-Train 1 for A-Train PB&3 Transf.'
Feed Water Flow DPT 23027,23028 10 Instrument-FW II Instrument-FW l 4" SS 2-RMSH DPI 23026,2302S DPI 11409,
-FW 11369
-FW l III 11 NIS Cond. - UE HVAC - ZE Recept - El 2!3 " Pipe A-Train - VE III 13 -NIS Cond.- UE B-T. rain & NIS Channel W* 9 k _ t
- TAELE 8 - (Cont'd.)
IDENTIFICATI0!l 0F EQUIPMEilT Afl0 PIPING Ofi Response to IE Bulletin 80-11 i SAFETY RELATED 11AS0 lRY WALLS Ofi 217450-280 FLOOR ELEVATI0tl 735'-0" Page 30 Page - 3 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM WALL SUPPORTED PR0itMITY~ SUPPORTED PR0XIMITY NO. ,
ON WALL TO WALL ON WALL TO WALL. PRIORl_Q
~
18 ,
10" Pipe - FP 6" Pipe-?l2 I 19 8" SS Pipe-VM III 19A 8" Pipe Riser III
- UM 21 Tray -MS,FW,C0 1" Air Line II 23 MTR - FW Tray - CO,MS,FW II MTR - FW 23022-FW 11339 23021-FW 26 VLV-N' Pnl. - EL I :
Pal. - EL
. Pnl. - EL Transf.& Pull Box 3"84" Pipe-FP DPT 23023-FM '
DPT 11368 - <
1 DPT 23024-FW '
DPI-Magnehelic 27 Wall No. 26 . l
- EL,NI I 34 Bus 110 SWGR-ZH Bus 110 SWGR I A-Train - AF,HC, MS ,fil , RC , RD,RH ,
4" Pipe - AFD 3-4" Blue P.pe-CW 6" Blue Pipe-CW 3/4" CU Line-CD l 35 Pnl. & A-Train - A-Train Cond.-ZH Recept. - EL I I MS B-Train Cond.-MS l
, NIS Cond's.-NI Bus 110 SWGR-AF H C ,!'S ,fil , ZS , RC ,
RD,RH,SI,VC,ZK A-Train Relay Cab
-EB Misc. Reack - MS 6" Pipe - FP 4" Pipe - FS W.
TABLE 8- (Cont'd.) .
IDENTIFICATION OF EQL'IP::ENT AND PIPING ON SAFE'TY RELATED MASON 3Y L' ALLS ON Response To IE Bulletin 80-I:
. FLOOR ELEVATION 73S'-0" 217450-280 Page - 4 Page 31 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM WALL SUPPORTED PR0XIMITY SUPPORTED PROXIMITY NO. ON WALL
, _ TO WALL ON WALL TO WALL PRIORITY 36 ~ B-Train - EA.VC Tray - DC,MS,RP Recept. - EL I 3 Cond's. B ~ B-Train - FG Card - SU Traia-ZV Bus 120 SWGR T8 - PS -AF ,HC ,fis , NI , ZS ,
Stm. Exclu. Aux ZK,RC,RD,RH,SI Relay Cab - fG &VC Rack 126 B-Train
-ZV 4" Pipe - CD 2-3" Pipes 3/4" CU Pipe - CD Steam Exclusion Metering Cab 121 Aux Bldg.
70050-ZD 37 B-Trains-ZH B-Train Cond. Pull Box Tray-DC,ZJ,ZN Bus 120-AF,HC, I
& ZH Cond's.-CU FtS , ZS ,RC , RD , RH ,
Tray-EB,ZA,2C,ZH SI,VC & ZK 15" Copper Tub- 6" Pipe - FP ing - ZH 4" Pipe
& Hisc. Devices-FP Chiller Unit
B-Train - EA EB PS,CL,AF MS,FW PB & Speaker HVAC Pull Box-ZH lb" CU Pipe - CW 4" SS Pipe Floor Drain 39 A-Train Cond's. ; Pull Box III NI$ Cond's.-NI '
480V Disc.
SW-EB 230V Disc.
SW-EB i Sound Pwr. &
Phone Box-CU
. HVAC Cont. Pnl.
, . -ZW 6-2" Lines - CV Chiller Unit 3/4" Pipe-N 6" Pipe - SA 2
1" CU Tubing-CD l
l l
e-.=
ht- -- - - - - -
t
- TABLE 9 6 32 L IDENTIFICATION OF EQUIPMENT AND PIPING ON SAFETY RELATED PAS 0!:RY WALLS ON FLOOR ELEVATION 755'-0"
NON-SAFETY RELATED SYSTEM SAFETY RELATED SYSTEM T SUPPORTED PROXIMITY SUPPORTED PR0XI81TY WALL PRIORITY ON WALL TO WALL ON WALL TO WALL NO. ,
B-Train Cond's-ZN(1) Trays - ZN, MS, Pull Box - ZH Cond's - ZH I l
TB-ZA, ZH Pull Box - ZN ,
A-Train 3 Cond's-ZN 2-lh" Pipes Horizontal Pipe 4" Pipe - RHR' Duct Supp.-CD Support - RHRH 2-4" Pipe -
1" Pipe - DE Duct for Control Room Vent -
3"&4" Pipe- UM 4" Chiller Bypass SV 33703 - ZN CV 31838 - ZH Air Supply SV 33712 - ZN CD 34143 - ZN SV 33320 - ZN CD 34182 - ZN SV 33821 - ZN SV 33808 - ZH SV 33704 - ZN SV 33713 - ZN CV 31837 - ZH SV 3.3807 - ZH ,
TB - ZV Trays - ZV,ZN, Pull Box - CU I 2
Pull Box - ZV ZA,ZH,ZJ,EB, Unit Htr.-ZD .
Cont.Pnl.-ZV HC MS A&B Train Cables
-ZJ TB - ZH Pull Box - ZH Cont.Pnl.-ZN 2-Chilled Wtr. 3/4" Htg. Lines Supports 4" Chillcd Wtr. 3 Line 3" Fire Prot.
Line - FP 1" SS Line - ZH SV 37020.- IN Air Duct-ZN Filter Pnl.-ZN SV.37014 - IN Air Duct-ZN Manom-ZN l
(1) FO?. CZSCRIFi10M OF SYSTEM ALP;iABETIC CODES SEE ATTACH:-:ENT 1.
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IDENTIFICATI0ft OF EQUIPMEflT ATID PIPING ON Response to IE Bulletin 80-11 SAFETY RELATED MA50f!RY WALLS ON 217450-280 FLOOR ELEVATION 755'-0" Page 33 Paga - 2 SAFETY RELATED SYSTEM NON-SAFETY RELATED SYSTEM WALL SUPPORTED PROXIMITY SUPPORTED PROXIMITY NO. _._ON WALL TO WALL ON WALL TO WALL PRIORITY 3 Panel - Zft . PB - ZN Pull Box - CU PB Station- ZN A&B Train Cond's HVAC PB Station Pull Box - ZH Panel - ZJ ZD I PB - ZJ 4" Pipe-RHRH 4" SS Pipe- 3/4" Pipe-fig Horizontal-RHR Strut.
3-3" Lines - FP Inst.Pnl . 57014 Inst.Pnl. 57015 O
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' R:sponse to IE Bulletin 80-11 217450-280 Page 34 TABLE 10 PRIORITY LIST OF WALLS PRIORITY t'. UMBER WALL fiU"BER FLOOR ELEVATION I 2, 3, 12A, 13, 15, 18, 19, 20, 695'-0" 23, 24, 25, 27, 28, 31, 32, 34, 35, 36, 37, 39, 40, 48, 55, 59 II 45 III 1, 4, 5, 6, 7, 6, 12, 21, 22, 38 I 25, 26, 27, 28, 29, 30, 34, 36, 39, 715'-0" 43, 44, 48, 52, 53, 74, 79, 79A, 81,
- 82, 83, 85, 86, 87A, 90, 91 .
94 II 69 e III 23, 35, 37, 38, 45, 47, 51, 54, 66, 87, 92, 93, 99, 100, 101, 102, 103, 201, 203 I 1, 2, 3, 4, 5, 6, 18, 26, 27, 34, 35, 36, 37, 38 , 735'-0" II 8, 10, 21, 23 t
III 7, 11, 13, 19, 19A, 39 j I 1,2,3 755 ',- 0 "
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. Page 35 TABLE 10 PRIORTIY LIST OF SAFETY SYSTEMS SYSTEM ALPHABETIC PRIORITY . SYSTEM NAME CODE I CONTAINMENT SPRAY CAUSTIC ADDITION CA COMPONENT C00LI:iG CC
~
COOLING WATER AND SAFEGUARDS SCREEfl WASH CL FIRE PROTECTIC:; A::D SCREEri '! ASH FP CONTAINMENT HYDROGEN C0ilTROL , HC REACTOR CCCLA:.T RC RESIDUAL MEAT REMOVAL RH SAFETY INJECTION SI CHEMICAL VOLUME AilD CONTROL VC AUXILIARY BUILDING SPECIAL VENTILATION ZA EQUIPMEtlT HEAT REMOVAL ZE CHILLED WATER SAFEGUARDS ZH
~11 FEEDWATER FW CONTAlf' merit AIR HAflDLING . 'ZC HOT CHEMICAL LAB AND SA"PLE ROOM VE!!TILATI0tl IJ CONTROL, RELAY & COMPUTER ROCitS VEl;TILATION & AIR C0ti-DITIONIrlG ZN PUMP HOUSE COOLING AND SERVICE WATER ZX III AUXILIARY FEED'.:ATER AF HEAT TRACI ;3 HT REACTOR PRESSURIZER PS STEAM GENERATOR BLOWDOWN SB UN-IDEi!TIFIED ELECTRICAL SYSTEM UE
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UN-IDEtiTIFIED MECHAtllCAL SYSTEM UM GAS WASTE DISPOSAL WG DIESEL GE::EO.ATOR ROOM C00LI::G ZG BATTERY C00.': SPECIAL VEl:TILATI0il ZK SHIELD GUILDP;G VE.*lTILAT!G:t ZS j C0flTAl. l5::T l' .ERVICE PU'.GE A!!D SPENT FUEL POOL 1 SPECIAL VE:!T!LATI0ri ZV l j
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Response to IE Bulletin 80 '
217450-280
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- Reproduced fron Project Administrative *'anual, for
< Prairie Island fluclear Generating Plant, Follow-on
- 217450,Section V-5.7 d
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Page 1 PROJECT ADMINISTRATION f* .':UAL Section V-5.7
- NORTHERN STATES POWER CCMPANY Revision No.
FOLLOW-0N PROJECTS 21-7450 Effective Date 4/1/79 l
SUBJECT:
5.0 PROJECT ADMINISTRATION (CCNTINUED) ,
5.7 PROJECT SYSTEMS LIST - (PRAIRIE ISLAND ONLY) 5.7.1 Definitions In accordance with the requirements of the Project Management Department Procedures Guide, a project system list was developed for the original Prairie Isla. Project 21-6197 and mcdified for the Follow-On projects 21-7450. The system list begins on page 7 and contains:
5.7.1.1 Column one - the system name.
5.7.1.2 Column two - the system alphabetic code; a unique com-bination of two or three letters which may be used at in place of the system name.
5.7.1.3 Column three - a list of the responsible disciplines for the system as follows:
Code Discipline A Engineering Support Services E Electrical -
I Instrumental & Control M Mechanical N Nuclear S Structure' .
If more than one code letter is listed, the code letters will be separated by a slash (/). The first listed code letter has the lead responsibility.
5.7.1.4 Column four - the Quality Assurance (QA) Type are amplified in Appendix B of the FSAR. In addition, the Asstrance Type for piping is further defined in Specification
- Piaa3tha IC6, (piping, fabrication, and erecticn) for the
. on.ginal Prairie Island Prcject. Any deviation from the definitions will be established on a project basis with e the approval of the Project Manager.
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Section l FOLLOW-ON PROJECTS 21-7450 V-5.7 2 i i t
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5.0 PROJECT ADMINISTRATION (CONTINUED)
QA Type I ,
Those items for which the Quality Assurance Program must assure the highest feasible degree of quality standards consistent with the importance of the safety function to be performed. This category includes, in accordance with NRC Design Criterion No. 1 specified in 10 CFR 50, those items of the plant which are essential to the prevention of accidents which could affect the public health and safety by the release of sucstantial quantities of radioactivity or are required in the mitigation of the consequences of sucn accidents.
QA Type II . i The items for which the Quality Assurance Program must engender a highly confidence level that the item will perform satisfactorily. This category includes those iters wnose failure would not direct-ly affect the health and safety of the public but the failure of which could cause severe economic loss or cause the plant to experience an extended R
outage. .
QA Type III , ,
Those items for which there is no compelling need of a Quality Assurance Program beyond that required to obtain good workmanship in manufacture and construction.
This category includes all other items not included in Types I and II.
l
! 5.7.1.5 Column five - the design class description The definitions of design class are amplified in Appendix j B of the FSAR:
Class I
- Those structures and cc ponento including instruments R and controls whose failure might cause or increase Et ,the severity of a loss-of-coolant accident or result j g_
in an uncontrolled release of substantial
- amounts
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- A substantial amount of radioactivity is defined as that amount of U radioactive m.iterial which would preduce radiation levels at the h site boundary in excess or L; of levels speciried in 10 CFR 100. i O
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SUBJECT:
5.0 PROJECT ADMINISTRATION (CONTINUED) of radicactivity. Also those structures and components vital to safe shutdown and isolation of the reactor are included.
Class II Those structures and corrponents which are important to reactor cperation b.t not essential to safe shutdown and isolation of the reactor and whose failure could not result in the release of subetan-tial amounts of radioactivity.
' Class III Those structures and co penents which are not directly related to reactor operation or containment.
Class I* Structures The design of Class I* Structures is similar to the design of Class I structure for seismic only as detailed in paragraph 8.6.3 (a) (i) of the Prairie Island FSAR.
In all other, respects the design of Class I* Struc-tures is identifcal to the design of Class III Structures as detailed in paragraph B.6.3 (e) of the i Prairies Island FSAR.
5.7.2 Modifications to the Existino Plant Systems.
Quality assurance type and design classification can be deter- '
mined by referring to the existing plant dccuments such as flow diagrams, line list, or the FSAR as well as the following table. i 5.7.3 Additions of New Plant Svste s ,
For new systecs which are added to the existing plant, the most current regulatory guices and criteria must be u:ed.
Since it is desirable to maintain the original norenclature
. and definiticns used for the casign and construction of Prairie
$ Island, the quality assurance and design classification require-D ments must be ccmpared to the definitions stated previously.
D
- A substantial iceunt of radioactivity is defined as tnat a. cunt of T radioactive- eaterial which would precace radiation levels at the O site boundary in excess of G of levels specified in 10 CFR 100.
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SUBJECT:
- 5. 0 PROJECT ADf4INISTRATION (CONTINUED)
PRAIRIE ISLA'O NUCLEAR PLANT - LNITS 1 & 2' Colum.n (1) (2) (3) (4) (5)
System Quality Alph. Resp. Level Design System Name Code Discip. Descrip. Class MECHANICAL s'tSTE"5 LIST Auxiliary Feedwater AF M/I I I Air Removal AR M/I III III Bleed Steam BL M/I II III Containment Spray Cuastic Addition CA M/I I I Component Cooling CC M/I I I Condensate CD M/I II III Chemical Feed (Turbine Cycle) CF M/I III III CO p CG M/I III III Cooling Water & Safeguards Screen Wash CL M/I I I Containment Spray CS M/I I I External Circulating Water CT M/I III III Circulating Water CW 'M/I III III Condensate Polisher CP M/S/I/F III III Deepwell, Potable Water Supply, Water Treatment and Concensate flakeup DE M/I II III Fuel Handling FH M/I I I l Fuel and Diesel Oil F0 M/I I I '
Fire Protection and Screen Wash FP M/I II III J Feedwater FW M/I II III Gland Seals GS M/I III III Containecnt Hydrogen Control HC M/I I I
- Heater Drains HD M/I II III Hydrogen (Pricary and Generator) HG M/I III III
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e Plant Boiler and Plant Hot Water Heatirg HS M/I III III Heat Tracing HT N/E/I I I Heater Vents HV M/I II III h
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SUBJECT:
5.0 PROJECT ADMINISTRATION (CONTINUED)
_ PRAIRIE ISLff0 NUCLFAR PLANT - UNITS 1 & 2 -
Column (1) (2) (3) (4) (5)
System Quality Alph. Resp. Level Design System Name Code Discip. Descrip. Class Leveltrol, Alarm and Gage Glass Piping (no Syste.ms-Valves appear in several systems) LA M/I II. III Miscellaneous Drains and Vents MD M/I II III Miscellane:us Plant utilities (Machine Shop, Lab, Doors, etc.) MP M/I III III Mair , Auxi .iary Steam and Steam Dump MS M/I II III Nitrogen NG M/I III III Cranes / Hoists PC S I Elevators PE 15 l Plant Plumbing . , PP M l Reactor Pressurizer PS M/I I I Reactor Coolant RC *M/I I I Residual Heat Removal RH M/I I I Reactor Water flake-Up RH M/I II III Station and Instrument Air SA M/I II III l
Steam Generator Blowdown (To and incluaing Flash Tank) SB M/I III III Spent Fuel Pcol Cooling / Refueling Water Cleanup SF M/I III III Safety Injection SI M/I I I Reactor Hot Sampling SM M/I III III Turbine Cold Sarpling SS M/I III III Turbine - Generator TB E/M/I III III Ccndenser Tube Cleaning TC M III III
.R Turbine Buildir,g Traps and Drains TD M II III
- t Turbine Oil Purification TO M/I III III II T
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PRAIRIE ISLA'O NUCLEAR PLANT - UNITS 1 & 2' Column (1) (2) (3) (4) (5)
System Quality Alph. Resp. Level Design System Name Code Discip. Descrio. Class Chemical Voltme ar.d Control VC M/l I 1 Boron Recycle Charging /Letc0.sn/5eal WE' Chemical Control / Purification Gas Waste Disposal WG M/I I I Liquid Waste Disposal and Steam WL M/I III III Generator Bloadown Treatment Eeactor Bldg. S..ps and Drains Auxiliary Bldg. Sumps and Drains Solid Waste Disposal WS M/I III III I
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5.0 PROJECT ADMINISTRATION (CONTINUED)
! PRAIRIE ISLAND NUCLEAR PLANT - UNITS 1 & 2 l
Column (1) (2) (3) (4) (5)
System Quality Alph. Resp. Level Design System Na e Code Discip. Descrip. Class VENTILATION SYSTE'15 LIST Auxiliary Building Specici Ventilation ZA M/I I I Administration Buildir.g Air Conditioning ZB M/I III III Containment Air Handling ZC M/I .
Containment Fan Coil I I Containment Dome Recircalation I I Containment Internal Cleanup . III III Control Rod Drive Mechanism Cooling II III II III Ring Girder Cooling III Reactor Gap Cooling III Neutron Detector Cooling II III III Refueling Ventilation III Auxiliary Building Normal Ventilation 20 M/I III III Equipment Heat Removal ZE M/I I I Spent Fuel Pool Normal Ventilation ZF M/I III III Diesel Generator Room Cooling ZG h/I I I Chilled Water Safeguards ZH M/I I I Hot Chemical Lab & Sample Room Ventilation ZJ M/I III III Battery Room Special Ventilation ZK M/I I I Local Ventilation Exhausts ZL M/I III III Cold Chem Lab A-C and Ventilation ZM M/I III III Control, Relay and Computer Rooms Ventilation and Air Conditioning ZN M/I I I Filter Room and Solid Waste Handling Ventilation Z0 M/I III III Containment Purge ZP M/I III III Screen House Heating and Ventilation ZR M/I III III Shield Building Ventilation ZS M/I I I R Turbine Building Ventilation ZT M/I III III 2R Containrent In-Service Purge & Spent I I Fuel Pool Special Ventilation ZV M/I Di Labs Service Area A-C System ZW M/I III III ZX M/I I I T Pump House Cooling & Service Wat.2r o Rad Was:e Building Ventilation System ZZ M/I III III 3
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5.0 PROJECT ADMINISTRATION (CONTINUED)
PRAIRIE ISLAND NUCLEAR PLANT - UNITS 1 & 2>
Column (1) (2) (3) (4) (5)
System Quality Alph. Resp. ' Level Design System Name Code Discip. Descrip. Class Radiation Monitoring RD E/I III III Reactor Control RE E/I III III Reactor Protection RP E/I III III External Circulating Water Substation ST E/M III III -
Plant Substation SY E/si III III Yard Lighting YL E- III III o
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6 = FOR STRU;TURAL DEPT USE ONLY - WALL CONSTR N= NORTH. $=50VTH. E= EAST. W. WEST H = HOLL0m' CORES 4= CHOOSE ONE. WALL IS FOR G = GROUTED SOLID CORES ENCLOSURE FOR STAIR. ETC. GR = GROUTED SOLID W/RE-BAR STL REINF.
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