ML19320B129
| ML19320B129 | |
| Person / Time | |
|---|---|
| Site: | Hatch  |
| Issue date: | 07/03/1980 |
| From: | Widner W GEORGIA POWER CO. |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| IEB-80-11, TAC-42920, TAC-42921, NUDOCS 8007090339 | |
| Download: ML19320B129 (18) | |
Text
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- a July 3, 1980 GeorgiaPower W. A. '#sdner e s m m, m. --
United States Nuclear Regulatory Commission Office of Inspection ana Enforcement
REFERENCE:
Region II - Suite 3100 RII - JP0 101 Marietta Street, NW 50-321/50-366 Atlanta, Georgia 30303 I&E Bulletin 80-11 ATTENTION: Mr. James P. O'Reilly Gentlemen:
Georgia Power Company hereby submits the enclosed information in re-sponse to Items 1, 2(a), and 3 as required by I&E Bulletin 80-11, " Masonry Wall Design", transmitted in your letter dated May 8,1980.
As you are aware, Item 2(b) does not require any response at this time, but will be addressed in the final report due 180 days from the issue date of the bulletin.
If you have any questions regarding this submittal, please contact my office.
Sincerely yours, (J), C2-,
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W. A. Widner pt, (CAE/mb Enclosure Sworn to and subscribed before e this 3rd day of July, 1980.
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' Notary Pub 1ic Ndary Pubic Georgia, state at LarRe
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My Comanession Dpires Sept 20,1983 xc: Director of the Office of Inspection and Enforcement Director of the Division of Operating Reactors, Office of Nuclear Reactor Regulation #
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N.R.C.
I.E. BULLETIN NO. 80-11 i
I MASONRY WALL DESIGN 4
EDWIN'I. HATCH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-321 AND 50-366 H
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4 TABLE OF CONTENTS PAGE INTRODUCTION 1
RESPONSE TO ACTION ITEM 1.
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RESPONSE TO ACTION ITEM 2 (a).
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RESPONSE TO ACTION ITEM 3 3
- ATTACHMENT 1 4
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ATTACHMENT 2 5-14 i
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ATTACIC4ENT 3 15 I
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INTRODUCTION For Edwin I. Hatch Nuclear Plant - Units 1 and 2 the following responses have been prepared in accordance with the sixty (60) day response requirements of I.E.Bulletin 80-11.
ACTION ITEM 1 Identify all masonry walls in your facility which are in proximity to or have attachments from safety-related piping or equipment such that wall failure could affect a safety-related system.
Describe the systems and equipment, both safety and non-safety-related, associated with these masonry walls.
Include in your review, masonry walls that are intended to resist impact or pressurization loads, such as missiles, pipe whip, pipe break, jet impingement, or tornado, and fire or water barriers, or shield walls.
Equipment to be considered as attachments or in proximity to rhe walls shall include, but is not limited to, pumps, valves, motors, heat exchangers, cabinets, instrumentation and controls.
Plant surveys, if necessary, for areas inaccessible during normal plant operation shall be performed at the earliest opportu..ity.
RESPONSE TO ACTION ITEM 1 A plant walkdown was done to survey all accessible areas of the plant which contain safety-related equipment, and to identify all concrete masonry walls which are in proximity to safety-related equipment or have safety-related equipment attached.
Detailed wall sketches were prepared to show all safety-related and non-safety-related equipment attached to the walls.
In addition, wall penetrations and as-built wall dimensions were verified to facilitate the determination of actual loads on the walls.
No concrete masonry walls are intended to resist impact or pressurization loads such as tornados, missiles, pipe break, pipe whip, or jet impingement.
These walls are all internal walls primarily intended as partition walls and as fire barriers.
The locations of concrete masonry walls in Class I buildings are shown in Figures 12-1-1 through 12-1-6 in Section 12 of the Unit 1 Final Safety Analysis Report (FSAR), and in Figures 3.8-25 through 3.8-38 in Section 3.8 of the Unit 2 FSAR.
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. identifies the structures surveyed and a summary of the survey results. provides a list of safety-related and non-safety-related systems and equipment associated with the walls located in the Unit 1 and 2 Control Building.
The Units 1 and 2 Reactor Buildings contain no walls which pose a danger to safety-related systems or equipment.
ACTION ITEM 2(a)
Establish a prioritized program for the re-evaluation of the masonry walls.
Provide a descripti'on of the program and a detailed schedule for completion of the re-evaluation of the categories in the program.
The completion date of all re-evaluations should not be more than 180 days from the date of this Bulletin.
A higher priority should be placed on the wall re-evaluations considering safety-related piping 2-1/2 inches or greater in diameter, piping with support loads due to thermal expansion greater than 100 pounds, safety-related equipment weighing 100 pounds or greater, the safety significance of the potentially affected systems, the overall loads on the wall, and the opportunity for performing plant surveys and, if necessary, modifications in areas otherwise inaccessible.
The factors described above are meant to provide guidance in determining what loads may significantly affect the masonry wall analyses.
RESPONSE TO ACTION ITEM 2(a)
A prioritized program for re-evaluating the masonry walls is described in Attachment 3.
Although all safety-related systems and equipment are consiceren equally important, the applicable factors described in the bulletin were used as a guide to establish the re-evaluation priorities.
No piping with 71gnificant thermal ex,ansion loads has been identified as being associated with concrete masonry walls.
alls will be re-evaluated according to priority, and all re-evaluations are scheduled to be completed within 180 days from the issue date of the Bulletin.
Priority I walls are scheduled to be re-evaluated by September 15, Priority II walls by September 30, and Priority III walls by October 24, 1980.
Placement of the walls into the priority classifications indicates that 65% of the walls fall. into Priority I, 12% of the walls in Priority II, and 23% of the walls in Priority III.
ACTION ITEM 3 Existing test data or conservative assumptions may be used to justify the re-evaluation acceptance criteria if the criteria are shown to be conservative and applicable for the actual plant conditions. _
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In the absence of appropriate acceptance criterin a confirmatory masonry wall test program is required by the NRC in order to quantify the safety margins inherent in the re-evaluation criteria.
Describe in detail the actions planned and their schedule to justify the re-evaluation criteria used in Item 2.
If a test program is necessary, provide your commitment for
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such a program and a schedule for submittal of a description of-the test program and a schedule for completion of the program.
This test program should address all appropriate loads (seismic, tornado, missile, etc.).
It is expected that the test program will extend beyond the 180 day period allowed for the other Bulletin actions.
Submit the results of the test program upon its completion.
RESPONSE TO ACTION ITEM 3 Plans are to use the original design methods and acceptance criteria described in the Unit 1 and Unit 2 FSAR's for the re-evaluation of the masonry walls.
Concrete masonry wall re-evaluation will be based on working strength design for reinforced concrete masonry structures.
The applicable code for design is American Concrete Institute
" Concrete Masonry Structures-Design and Construction", ACI 531-70.
Loads and loading combinations will be based on those found in Section 12.4.2.3 " Reactor Building and All Other Class I Structures" of the Unit 1 FSAR, and Section 3.8.'4 "Other Seismic Category I Structures" of the Unit 2 FSAR.
The seismic design basis for concrete masonry walls is found in Section 12.3.3.2, " Design of Class I Structures" of the Unit 1 FSAR, and Section 3.7A " Seismic Design" of the Unit 2 FSAR.
The seismic loading on the walls is computed using the floor response spectrum for the floor supporting the walls.
Allowable stresses for the Operating Basis Earthquake (OBE) are the same as those found in ACI 531-70.
The allowable stresses for the Design Basis Earthquele (DBE) are those given in Section 12.6.2 of the Unit 1 FSAR, and Section 3.8.4.5 of the Unit 2 FSAR.
The original analysis of the concrete masonry walls provided a l
minimum factor of safety of 2.5 for OBE forces, and a minimum factor of safety of 1.11 for DBE forces, as described in the i
response to Question 12.2.0.23 in the Unit 1 FSAR.
r There are no plans to institute a masonry wall test program.
Conservatisms in the method of analysis and design described in the response to Question 12.2.0.23 in the Unit 1 FSAR provided adequate factors of safety, and is justification for the acceptance criteria. m
ATTACHMENT 1 CLASS I STRUCTURES SURVEY RESULTS REACTOR BUILDING UNITS 1 AND 2 The reactor building-contains unreinforced concrete masonry walls classified for equipment removal.
These walls are bounded on both sides by structural steel plates supported by a structural steel frame.
The steel frame / plate system will preclude' damage to safety-related equipment in proximity to the wall under all postulated loads.
No safety-related equipment is attached to the walls or steel frame / plate system.
No re-evaluation will be required for these walls.
CONTROL BUILDING The control building contains horizontally and vertically reinforced concrer.e masonry walls used as partition walls and as firewalls.
Reinforced concrete beams and columns are located around door openings, where required. Vertical reinforced concrete columns are. strategically located to reduce concrete masonry wall span lengths in accordance with the original allowable seismic moments and shears.
Safety-related equipment is either attached to or in proximity to 70% of these masonry walls.
DICOEL--GE:: nATOR BUILOI::G The diesel-generator building contains no concrete masonry walls.
RIVER INTAKE STRUCTURE The river intake structure contains no concrete masonry walls.
MAIN STACK The main stack was inaccessible to personnel during the plant walkdown.
The main stack will be surveyed during the next scheduled refueling outage, or sooner if conditions permit.
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ATTACIDfENT 2 SAFETY - RELATED & NOU - SAFETY RELATED
'EOUIPMENT ASSOCIATED WITH MASONRY WALLS The following list describes the Safety - Related & Non - Safety Related mechanical and electrical equipment identified as having components attached to or in proximity to the concrete masonry walls.
C71 Reactor Protection System C61 Primary Containment Isolation System B21C Automatic Depressurization System E51 Reactor Core Isolation Cooling System E41 High Pressure Coolant Injection System Ell Residual Heat Removal System E21 Core Spray System R20M 600V AC Emergency Station Service System R20P 120/240V Vital System
~R20N 120/208V Emergency Stat:.on Service - Essential R42A 125/250V DC Station Batccry & SWGR System R20E 480/277V AC Plant Lighting System R42A 125V DC Emergency Lighting System R42E 24/48V DC Instrumentation Batter _1es R20D
.120/208V AC Instrument System - Norman Station Service P33
. Steam & Condensate Cycle Sampling System Z41B Control Bldg. HVAC System P51 Service Air System
.Z43 C. B. Fire Protection System ESS Division I Raceway System ESS Division II Rac _.<ay System Diesel _A Raceway System Diesel B Raceway System Diesel.C. Raceway System-Z41 Computer Rm HVAC System 4
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PS2 Instrument Air P41 Service Water P42 RECC Water System -
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CONTROL BLDG. EOUIPT LOCATED ON ELEVATION 112 I
ELECTRICAL EOUIP NO
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H21-P272 Cent Bld Sump Pump Cont PNL H21^P204 Steam & Cond Cyc Sample PNL i
H21-P205 Steam &_Cond Cyc Sample PNL H21-P206 Steam & Cond Cyc Sample PNL H21-P207 Steam & Cond Cyc Sample PNL I" -
_. H21-P2f,8 Steam & Cond Cyc Sample PNL' H21-P302 WI. Anal RM HVAC Cent PNL 1
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~ Z41-B006A UT. Anal RM A/C Unit Z41-B006B WT. Anal RM A/C Unit 5
R42-S001B Sta. Batt 1B R42-S001A Sta. Batt lA H21-P241 Air Comp 1A Rly PNL H21-P234 Air Comp. lA Cont PNL H21-P235 Air Comp. 1B Cont PNL.
H21-P236_
Air Comp 1C Cont PNL
- H21-P223 Instr Cont: Rack
'R42-S017B 24/48V RPS Batt 1B' R42-S017A 24/48V RPS.Latt IX R44-S001
-Inverter A Un - Inter PWR Sys.
. H21-P254
-Sump P. & HTR Cont. PNL.
Il21-P253.
Sewage Eject Cont PNL' H21-P219 Turb Bld Instr kack_
H21-P237-'
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CONTROL BLDG. EOUIPT LOCATED ON ELEVATION 112 ELECTRICAL E0_UIP NO
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R24-S030 600V MCC - IF Z41-B007B-Hot Inst B01 A/C
- 241-3007A Hot Inst RM A/C s
2R42-5017A 24/48V RPS Batt 2A
~Un - Int AC PWR Sys H21-P276 Stm & Cond Sample PNL H21-P277 Stm &'Cond. Cyc Refrig Unit f
H21-P300U CAB Cont ?NL (Door Cl)
I H21-P300V CAB Cont PNL (Door C4) 9 H21-P300W CAB Cont PNL (Door Cll8A)
H21-P300X CAB Cont PNL (Door C-118B)
H21-P309 Hot Instr Shop HVAC Cont PNL
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H21-P317'
. Vital AC Batt Shunt PNL 2H21-P219-MS Sjae A&B 3rd Stage-PNL 2P33-P204 Stm & Cond Cycle Sample Ph1 2P33-P205 Stm & Cond Cycle Sample PNL 2P33-P206-Stm & Cond Cycle Sample PNL i-2P33-P207-Stm & Cond Cycle Smaple PNL 2H21-P233' Turb Bld Instr Rack' 2H21-P227A C. B. lnst Rack 12H21-P227B_
C. B. Instr Rack 2H21-P227C C. B. Instr-Rack 2H21-P227D C. l B.MInstr Rack 2H21-P237 ANNUN Logic CAB 2A.
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j CONTROL BLDG. E0.UIPT LOCATED ON ELEVATION 112 ELECTRICAL EOUIP NO 2H21-P254 C. B. Non Rad Sampling PNL 2H21-P285 Sta Batt 2A Shunt PNL 2H21-P285A Batt Fuse Monitor PNL 2H21-P286 Sta Batt 2A Shunt PNL 2H21-P287 Sta Batt 2A Shunt PNL 2H21-P288-Sta Batt'2B Shunt PNL l
2H21-P288A' Batt Fuse Monitor PNL 2H21-P289 Sta Batt-2B Shunt PNL 2H21-P290 Sta. Batt 2B Shunt PNL 2H21-P294 Rad Mon. Batt 2A Shunt PNL 2H21-P295 Rad Mon Batt 23 Shunt PNL 2H21-P317 Vital AC Batt Shunt PNL 2H21-P501D Fire Prot RLY PNL Piping Service Water to RBC'CW Coolers Piping RB'CCW Cooler Suctida and Discharge Fire Protection-Piping HVAC Ductwork._ -
CONTROL BLDG. EOUIPT LOCATED O!! ELEVATIO!! 130 ELECTRICAL EQUIP NO R23-5004-600V SWGR S Transf ID r
H21-P246
-600V SWGR Loc Cent PNL R25-S037 120/208V Essential CAB 1B Rll-SO42 600-120/208V Essent Transf 1C R23-S003 600V SWCR & Transf 1C H21-P245 600V SWGR Loc Cont PNL R25-S036 120/208V Essent CAB 1A l
R11-SO41 600-120/208V Essent Transf 1B H21-P223 Turb Bld Instr Rack R22-S017-125/250V DC SWCR 1B H21-P249 125/250V DC Cent PNL R42-5029 125V DC Batt CHG 1D R42-S030 125V DC Batt CHG 1E R42-S031 125V DC Batt CKG 1F R26-M031C 125V DC T/0 SW R26-M031D 125V DC T/0 SW S11-S007
-Sta Transf 1CD
-R25-S071-480/277V LGT CAB 1A
-R25-SO93 120/208V LGT CAB R25-S080 120/208V LGT CAB R22-S016 125/250V OC SWGR 1A
-H21-P248 125-250V_.SWGR Loc Cont PNL R42-5026'
~125V DC Batt,Chg-1A R42-S027-
~125V DC Batt Chg 1B R42-S028-125V DC Batt Chg 1C
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CONTROL BLDG. EOUIPT LOCATED ON ELEVATION 130 ELECTRICAL EQUIP NO R26-M031A 125-250V T/0 SW R26-M031B 125-250V T/0 SW R25-S069 125V DC Emerg LGT CAB R25-S001 125V DC CAB 1A H11-P630 NSSS MCiUN Logic CAB R42-S051 24V DC Batt Chg 1A
' R42-S057:
- - - R26-M041A 24V DC T/0 SW j
R26-M041B 24V DC T/0 SW R25-S015 24/48V-DC CAB 1A R25-5064 120-208V AC Instr CAB 1B Instr Bus 325-5063 120-208V AC Vital AC CAB 1A R24-S001 600V & 208V MCC - 1A C71-S001B RPS M-G Set 1B 4
C71-S001A RPS M-G Set 1A R42-S054 24V DC Batt Chg 1D R24-S058 24V DC Batt Chg 1CD R26-M041C 24V DC T/0 SW R26-M041D 24V DC T/0 SW R25-6065
.120-208V AC Inst CAB 1B Instr Bus 2C71-S001B RPS M-G Set 2B 2C71-S001A
-RPS M-G Set 2A i
2R42-S051-24V' DC Batt:Chg 2A
- 2R42-5058 24V DC.Batt Chg 2CD
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. CONTROL ELDG. EOUIPT LOCATED ON ELEVATION 130 ELECTRICAL EQUIP NO 2R42-S058 24V DC Batt.Chg 2CD 2R26-M03-24V DC T/0 SW 2R26-M05 24V DC T/0 SW
-2C71-P001 RPS Dist CAB 2R25-S064 120-208V AC Instr CAB 2B Instr Bus 2Hil-P630 RPS ANNUN Log CAB 2B l
2R42-S051 24V DC Batt Chg 2A 2R42-S057 24V DC Batt Chg 2AB 2R42-S052 24V DC Batt Chg 2B
'2R26-M02 24V DC T/0 SW 2R26-M04 24V DC T/0 SW
'24-48V DC CAB 2A 2R25-S064 120-208V AC Instr CAB 2A Instr 5us 2R25-S065
.120-208V AC -Vita 1 AC CAB 2A 2R24-S004 600V & 208V MCC-1D i'
~2R25-S072 480-277V AC Lgt CAB 1B 2R25-S025 120-208V Dist CAB 1E
.2R22-S017 250V DC ' Batt SWCR - 2B l
2R21-P249' 250V DC SWGR 2B Loc' Cont PNL
.2R42-S029 125V DC Batt Chg 2D
'2R42-S030 125V DC Batt Chg 2E 2R42-S031 125V DC Batt Chg 2F
'_ 2R11-SO42 600 120-20SV Essent Transf s..
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s CONTROL BLDG. EQUIPT LOCATED ON ELEVATION 130 ELECTRICAL EOUIP NO _
2R25-S037-120-208" Dist PNL 2S.
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2R25-S002 125V DC Dist CAB 2B 2R11-S041 600 120-20SV Essent Transf 2R25-S036 120-20BV AC Dist PNL'2R 2R25-S001 125V DC Dist CAB 2A 2R25-S069 125V DC Emerg.Lgt CAB 2R25-S071 480-277V AC Lgt PNL 2R25-S080 120-208V AC Lgt PNL 2R22-S016 250V DC SkCR 2A 2H21-P248 250V SWGR 2A Log Cont.PNL 2R42-S026 125V DC Batt Chg 2A 2R42-5027 125V DC Batt Chg 2B 2R42-S028 125V DC Batt Chg 2C 2R23-S004 -
600V SWGR & Transf 2D 2S11-S007 4160-600V Sta Serv Supply Transf 2CD 2R23-S003 600V SWGR & Transf 2C Piping Service Water.to Turbine Oil Reservoir Coolo.rs Piping. Service Water to EHC Coolers Fire Protection Piping
-HVAC Ductuork=
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w CONTROL BLDG. EQUIPT LOCATED ON ELEVATION 147 ELECTRICAL EQUIP NO H21-P301 Computer Rooms HVAC Control PNL Z43-P002A F. P. PWR Dist CAB 1A Z43-P002B F. P. PWR Dist CAB 1B 1
Z43-P004 Electro - Man Pilot CAB Z43-P005 F. Det. Cont PNL 1B HVAC Ductwork Fire Protection Piping 3
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CONTROL BLDG. EQUIPT LOCATED ON ELEVATION 164 ELECTRICAL EQUIP NO R26-M01 600V Throw - Over SW Z43-P006
- 7. Det Cont PNL 1C Z43-P0ll F. Det Cent PNL ID Z43-S001 F. Det Sys PWR Supply Inverter HVAC Ductwork Fire Protection Piping
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-0 ATTACHMENT 3 PRIORITIZED PROGRAM FOR MASONRY WALL l
RE-EVALUATION j
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I PRIORITY I (HIGH PRIORITY) 1.
Walls with attached conduit four inches or larger in diameter.
2.
Walls with attached cable trays.
3.
Walls with attached electrical or instrumentation cabinets or other electrical equipment weighing 100 pounds or more.
4.
Walls with attached mechanical equipment weighing 100 pounds or more.
5.
Walls with attached piping 2-1/2 inches or larger in diameter.
PRIORITY II (MEDIUM PRIORITY) l.
Walls with attached conduit two inches to 3-1/2 inches in diameter.
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Walls with attached piping 1-1/2 inches to 2-1/2 inches i
in diameter.
3.
Walls with attached mechanical or electrical equipment weighing 50 to 100 pounds.
4.
Walls with unusually large numbers of attachments and/
or penetrations.
PRIORITY 111 (LOW PRIORITY) 1.
Walls with attached conduit under two inches in diameter.
2.
Walls with attached piping under 1-1/2 inches in diameter.
3.
Walls with attached mechanical or electrical equipment weighing less than 50 pounds.
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