ML19291D043
| ML19291D043 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 11/28/1960 |
| From: | Kirk R US ATOMIC ENERGY COMMISSION (AEC) |
| To: | Furcolo F MASSACHUSETTS, COMMONWEALTH OF |
| References | |
| NUDOCS 8011240026 | |
| Download: ML19291D043 (1) | |
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-SEPTEysER 23 360 MEMORANDUM FOR: Steven A. Yarga. Chief Operating Reactors Branch fi, CL Thocas A. Ippolito, Chief Operating Reactors Branch F2, DL Robert A. Clart, Chief Operating Reactors Brunen f3, DL Robert W. Reid, Chief Operating Reacters Srsnch #4, DL Dennis M. Crutchfield, Chief Jperating Reactors Branch 75, OL James R. Mtiler, Chief Standardization and Special Projects Branch, DL FROM:
Charles M. Trammell Pnsfect Manager Operating Reactors Branch f3, DL SIEJECT:
MASONRY WALL DESIST - IE BULLETIM 80-11 On May 8,1990, the Office of Inspection and Enforcament issued IE Bulletin 80-11, " Masonry Wall Design" to anst power reactor facilities.
A copy of this bulletta is attached.
MRR has agreed to assist I&E to evaluating iteensee's responses to this bulletin.
Licensee's responses are being sent by 11E to the Structuraf Engineering Branch, Mvision of Engineering, where they are under review now.
TAC sheets have been prepared he all plants that received the bulletin (except Mr TMI-2) and are attached fbr your reference and use. The individual SEE reviewerr are identified on the TAC sheets. If these TAC sheets duplicate any others which yee may have written, pt' ease cancel the old and use the attached TAC sheets.
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Multiple Addressees Responsibilities for this review effort are:
I&E overall scheduling, coordination with licer. sees, and field-related implementation tasks.
MRR (SES) evaluation of Ticenses submittals and related technical ecuments, determination of masonry wall design adequacy, and resoltttion of non-conforming design itess.
Key Personnel:
I1E Coordinator: Hoerd Wong SG Coordinator: It. C. Leu DOL Coordinator: Charles Trusself ggginal Signed Bt Charles M. Trammell, Project Manager Operating Reactors Branch f3 Division of Licensing Attachments : -
1.
IE Balletin 80-11 2
TAC Sheets cc: w/o attachments:
H. Wong K. C. Leu T. Novak F. Schauer E. Jordan R. Tedesco D. Eissthut D. Jong K. Herring E. Lainas C. Tremne11 DISTRIBUTION Central Files GPSt3 Reading File P..treutzer omCr I
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DATE NRC FORM 313 i -76) r*RCM 3240 t u.S. GOV ERNMENT PRINTING CmCE: 1979-289 369 9
IE Bulletin No. 80-11 May 8, 1980 Page 2 of 4 Action to be taken by all power reactor facilities with an Operating License (except Trojan, Sequcyah Unit 1, North Anna Unit 2, and Salem Unit 2):
1.
Identify all masenry walls in your facility which are in proximity to or have attachments from safety related piping er equipment such that wall failure could affect a safety related system.
Describa the systems and equipment, both safety and non-safety-related, asscciated with these masonry walls.
Include in your review, masonry walls that are intended to resist impact or presseri:ation loads, such as missiles, pipe wnip, pipe break, jet impingement, or tornado, and fire or water barriers, or shield walls.
Equipment to be considered as attachments or in proximity to the walls shall i1clude, but is not limited to, pumps, valves, motors, heat exchangers, cacle trays, cable / enduit, HVAC cuctwork, and electrical cabinets, instrumentation and controis.
Plant surveys, if necessary, for areas inaccessible during nerinal plant Operation shall be performed at the earliest opportunity.
2.
Previce a re evaluati n of the desicn adecuacy of the walls icentified in Item I atove to determine whether the masonry walls will perform theia intended functicn under all postulated Icats and lead ccabinations.
In tnis regard, the NRC encourages tne fermation of an Owners' group to estaDlish both a;;repriate re-evaluation criteria anc where necessary, a later confirmatory masonry test program t0 puantify the safety margins estaclished by the re evaluation criteria (this is discussed furtne i n Item 3 below).
Establish a prioritized program for the re evaluation of the masonry a.
walls.
Provide a description of :ne ;rogram anc a cetaile: s:nedule for completion of tne re evaluatier for the categcries in the program.
The t0=oietion date of all re-evaluations snc:.id not be =0re inan 150 davs from the date of this Bulletin.
A hi:ner crioritv should be placed on :ne -all re-evalusti:n censicering safety-related piping 2-1/2 in:nes or greater in ciameter, pipin; witn se Dort 1 cads due to thermal ex ansi n greater tnan 100 pouncs, safety-related ecuipment weigni ng 100 pcunts or greater, the safety significance of the potentially af f ected systems, the overall icacs en :ne wall, and.ne ep;crtunity for :erforming clant surveys anc, if necessary, mo tirications in areas otnerwise ir.accessi le.
The factors describe: atove are meant to provide guidance in cetermining what 10:ds may significantly af fe:; the masonry wall analyses.
c.
Submit a written report c On :om:letion of the re evaluation program.
The resc-t snall inclu:e ne folic.,ing information.
(i) Describe, in cetail, tne f unction Of the mascnry walls, the configuratier.s of tnese walls, ine type an: strengths of tne materials of.nich they are con:tructed (mortar, grout, concrete anc steel), anc the reinforcement details (ncri:cntai siecl, vertical steel, and masonry ties f r multiple -ytne
IE Eulletin No. 80-11 May 8, 1980 Page 3 of 4 constructioni.
A wythe is nsidered to be (as defined by ACI Standard 531-1979) "each centinuous vertical section of a wsil, one masonry unit or greuted space in thickness and 2 in. minimum in thickness."
(ii) Describe the constructica practices employed in the construction
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of these walls and, in particular, their adecuacy in preventing significant voics or other weaknesses in any mortar, grout, or concrete fill.
(iii) The re-evaluation report shculd include detailed justification for +he criteria used.
References to existing coces or test dat. 1ey be used if acplicable f or the plant conditions.
The re-evaluation should specifi;; ally accress the following:
(a) All postulated leacs anc load combina' ions should be t
evaluated acainst the 0rresponding re-evaluatior.
acceptance criteria.
The re-evaluation should consider the 'l02:5 frem safety anc non-safety-related attachments.
differential floor cisplacement and thermal effects (or detailed justi'itation that these can be considered self limiting and cannet incute crittle f ailures), and tne effe s of any *ctential crackin; unter dynamic loacs.
Descri:e in cetail the methods usec 10 at: cunt for these factors in the re-evaluation anc the adequacy of the acceptance criteria f or Detn in plane and Out-of-clane loads.
(b) The me:nanism for load transfer into the masonry walls an: postulated failure moces snculd be revie-ed.
For multiple wythe walls in wni:n :cm;csite Denavior is relied u;cn, describe One metnocs anc accettance criteria used to assure that these sils will Dehave as compcsite walls, esce:ially with regard to shaar and tension transfer at the wytne inter # aces.
'a'itn regard to Tccal loadings such as Diping and e ui::ent su;;;rt reactions, the acceptance criteria snculc assure that the loacs are acecuately trans-ferred into the wall, su n that any assumoticns regarting tne behavier Of tne walls are a:;repriate.
Incluce the potential for block cuilout and tne necessity for tensile stress transfer tnroutn bend at the wythe interfaces.
1.
Existing test data er :cnservative assum:tions may Oe usec to justify the re-evaluation acceptance criteria if the :riteria are snown to be conser-vativt and an;iicacie for tne a cal :iant ::ncitions.
In the aosence Of appropriate attestance criteria a confirmatory masenry wall test program is recuired by the NRC in crcer tc guantify the safety mrP; ins inherent in the re-evaluatice criteria.
Des rite in cetail the actions planned and their schedule te justify the re-evaluation criteria used in Item 2.
If a test program is necessary, previce ycur termitment f or such a program and a senecule for su mittal Of a descri:tien Of tne test pregram and a senecule for completien of the Oregram.
Inis test Oregram snould a: ress all
IE Bulletin No. 80-11 May 8, 1980,
Page 4 of 4 appropriate loads (seismic, tornado, missile, etc.).
It is expected that the test program will extend beyond the ISO day period allowed for the other Eulletin actions.
Submit the results of the test program upon its completion.
4.
Submit the information requested in Items 1, 2a, and 3 withia 60 days of the date of this B.:lletin.
Within 180 days of the date of this Bulletin submit the information requested in Item 20.
If in the c:
se of the re-evaluation, the operability of any safety related system is in je pardy, the licensee is expected to meet the applicaole tecnnical specifications action statement.
This information is requested uncer the provisions of 10 CFR 50.54(f).
Accordingly, ycu are requested to provice within the time period specified in Item 4, written statements of the above information, signed under cath er affirmation.
Reports should be submitted to the Director of the appropriate NRC Regional Of fice and a copy should be forwardec to tne NR: Office of Inspection anc Enforcement. Division of Reactor Operations Inspection, Washington, D.C. 20555.
The reportin; recuirements of this Bulletin ce not precluce nor substitute for the applicacle requirecents to report as set forth in the reculations and license.
If you receire adcitienal informatic. regarding this matter, please contact the Directcr of the accropriate NR; Regional Of fice.
Accreved by GAC, E180255 (EUO72); clearance excites 7/31/SO.
Approval was civen uncer a Oianket cle ince specifically for identified generic preolems.
Attachment:
IE Infcrmation Notice Nc. 79-25
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