ML20134G595
| ML20134G595 | |
| Person / Time | |
|---|---|
| Site: | Perry, 05000000 |
| Issue date: | 10/21/1980 |
| From: | Kacer W CLEVELAND ELECTRIC ILLUMINATING CO. |
| To: | Julie Hughes NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| Shared Package | |
| ML20132C675 | List:
|
| References | |
| FOIA-85-264, FOIA-85-265 NUDOCS 8508270032 | |
| Download: ML20134G595 (25) | |
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THE CLEVELAND ELECTRIC ILLUL.N ATING COMPANY ILLUMINATING BLDG. e PUBLIC SoUARE e CLEVELAND, OHIO 44101 m TELEPHONE (2.., 623-1350 e Mall ADDRESS:
P. O. BOX 5000 Serving The Best Location in the Nation October 21, 1980 Mr. Jack llughes Site Resident Inspector, Region III U. S. Nuclear Regulatory Commission 10 Center Road Perry, OH 44081
Dear Jack:
As requested, I am sending you a copy of our Deviation Analysis Report 035, with attachments, which concerns the Ruskin Manufacturing Company type N1BD23 fire dampers.
If you have further questions, please contact either Mr, Mike Brown (extension 202) or Mr. Gary Leidich (extension 538).
Sincerely, h
W. J. Kacer General Supervising Engineer Construction Quality Section ksz Attachments cc:
B. L. Barkley M. A. Brown G. R. Leidich 404.101,73
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8008270032 850802 PDR FOIA MCDEVIT85-264 PDR N
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. PERRY N U]i E A R PO WER PLAhT DEVIATION Ak ALYSIS REPORT ITEM LOCATION QUANTITY Ruskin Fire Dampers Perry Nuclear Power Plant 85 ORIGINATOR W M g[h ORGAlilZATION M. A. Brown DATE
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Construction Quality d
Engineering 8/8/80 RESPONSIBLE ORGANIZATION SPECIFICATION REFERENCE DOCUMENTS Rur: kin Manufacturing Company SP-49/91 See Attached DESCRIPTION OF DEVIATION Fire Dampers furnished by Ruskin Manufacturing Company are being failure of the brackets as explained on attached Ruskin lettermodified because of SP-49/91.
Regulatory Commission.This problem has been reported by Ruskin under 10CFR21 ear
SUMMARY
ANALYSIS The fire dampers in question are non-nuclear safety in all system affected safety related system drawings will be revised to indicate thi s.
The s.
Manufacturing Company and verified by Robert Irsay CoAl uskin such time that dampers are accessible.The remaining six (6) dampers
- o. at Irsay Co. after completion of modification.Ruskin will be notified, by Robert
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- 54. Ait M mt: d *I % d # 2 O d N -ID
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SIGUIFICANT DEFICIENCY YES
_X.
NO REPORTABLE DEFECT YES
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ENGINEERING QUALITY ASSURANCE RALYSIS BY C
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OTHER 7A/-J/ -
kl, Iok/ro ew-so NAME/DATE NA :',/DATE 8
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[b OP3RdEfl Gilbert / Commonwealth August 12, 1980 to:
J. S. Holton from:
K. R. Pech, subject: Safety Related System Diagrams with Fire Dampers It has been pointed out to us by the resident NRC inspector that while our philosophy is to consider all fire dampers as non-safety, there is no indication on the system diagrams of the safety related systems to this effect.
We committed to have a note added to the affected diagrams to identify the fact that the fire dampers are an exception to the safety related classification of the system. As we discussed on the phone the re-vised drawings should be on site by September 1.
Please proceed with the required revisions.
The drawings to be changed are as follows:
DWG, No.
SYSTEM DESIGNATION D-912-60s 1M15 D-912-609 M23 & M24 D-912-610 Mas & M26 D-912-617 M40 D-912-622 1M36 D-912-623 M28 D-%2-605 2M15 D-962-622 2M36 Please call John Cichello or..myself if you have any questions on this.
i K. R. Pech cc:
P. B. Gudikunst J. P. Cichello
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-CLEAR POWER PLANT PROJECT ORGANIZATION THE CLEVELAND ELECTRIC ILLUMINATING COMPANY SEP 251980 Ano reiseR enoiserRs. m e.
MEMORANDUM PNPP COS ru-o Rev.sas PAGCHQ.~
B. L. Barkley !
vo W. J. Kacer ROOM Wll5 FROM oATE Sept. 24, 1980 PHONE 212 ROOM W220 sue. sect DAR 01 Ruskin Fire Dampers This information is provided to backup the DAR on Ruskin Fire Dampers SP-49/91, dated August 8, 1980.
The DAR (based on a Huskin 10CFR21 report to NRC) is not a significant deficiency since the fire dampers are not safety related. Here is the explanation of why the Fire Dampers in a safety related duct (or non-safety duct) are not safety related.
1.
The fire damper's function is to maintain the integrity of the fire vall it is installed in.p As such, it is considered to be part of the fire protectionosystem and to have the came non-safety related classification.
2.
While the fire dampers are classified as non-safety related, they are required to be seismically qualified when they are to be installed in a nuclear safety related ductwork system.
Proper documentation is available concerning the seismic qualification of fire dampers for the Perry Project.
(In a seismic event they do not det;rade the performance of the ductvork system.g l.t., %ey ruak open.) @
GAI has added a note as requested, to each nuclear safety related system diagram to eldify that the fire dampers are non-safety related and seismic category I.
This vill remove the concern that the drawings indicate that the dampers are safety related. The spec clearly states they are non-safety.
BLB/jac cc:
H. W. Dieckmann J. D. Grier P. B. Gudikunst K. R. Pech S. W. Reid E. J. Turk NDS File 9
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- 2 An investigation has been performed to determine the effect of the failure of a fire damper to close properly,on the ability to safely shutdown the reactor plants and to minimize radioactive releases to the environment.
The investigation consisted of a review of fire damper locations throughout the plant and the fire analysis for the related areas as described in the Fire Protection Evaluation Report.
The areas where a fire damper failure would result in the potential for a fire to affect redundant systems or equipment are detailed below along with an analysis of the significance of each.
I.
HPCS Battery Room (620'-6" Control Complex)
Ventilation for this area is provided by two (2) ducts off of the main duct that supplies DTV 1 and DTV P MCC Arcan.
Air is relieved through wall openings in the walls to DIV 1 and DIV 2 MCC Areas.
Separation of the fire dampers is at least 13 feet in this area and a fire loading of 21,130 BTU /sq. ft. (less than 30 minute fire) indicate that a fire could not traverse the duct to damage the other Division.
Thus a safe shutdown of the reactor plants is not impaired.
II.
Division 1/ Division 2BatteryRooms(638'-6"controlcomplex)
Battery rooms for Division 1 and Division 2 have exhaust via fire dampered openings in the wall to a common corridor. The Fire Protection Evaluation Report indicates there are no combustibles in the corridor, hence no fire loading.
III.
Vertical Cable Chase (638'-6" control complex)
Air supply ducting to the computer room is obtained via two (2) ducts originating from a common duct which penetrates the fire wall between divisionalized cable chases.
Postulating a fire damper failure, the physical separation of the tray of divisions 1 and 2 is such that the ability to safely shutdown the reactor plants is maintained.
IV.
Control Room (654'-6" control Room)
The common plenums (3 places) serving both Units 1 and 2 contain fire dampers on the Unit 1 side and the Unit 2 side.
The entire ventilation system is seismically supported.
In the instance of fire damper failure, the arrangement is such that a fire in one control room will not spread through the duct in one control room through the failed fire damper and through the duct in the other control room.
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V.
HVAc Area (679'-6" control complex)
Physical separation of redundant equipment of at least 30 feet and a fire loading of 15,500 BTU /sq. ft. (less than 15 minute fire) indicate that a fire damper failure does not allow t;he fire to travel to the redundant equipnent and does to not effect the ability to safely shutdown the reactor plants.
VI.
Plenum Area (693'-2" control complex)
Although the plenum area is common to Unit 1 and Unit 2, the physical separation of the supply ducts for the redundant electrical divisions and components is such that in the case of a fire, and fire damper failure, the fire will not travel through the duct to another divisional area and the ability to safely shutdown the reactor plants is maintained.
The fire dampers, in all cases, are seismically qualified and are supported fromeitheraseismicallyconstructedwall/floororaseismicallysupported duct system.
Additionally, the redundant areas are also separated by physical distanceand/orseismicsafetyclassductwork.
The analysis of the above areas indicate that the ability to safely shutdown the reactor plants is not impaired.
Therefore, the deviation described on the DAR is not considered reportable as a significant deficiency.
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l SQL #786 giflME THE ROBERT IRSAY COMPANY July 21, 1980 Site Organization.
Perry Nuclear Power Plant 10 Center Road P.erry, Ohio 44081
' Attention: Mr. H. Dieckmann Cleveland Electric Illuminating Co.
Perry Nuclear Power Plant HVAC Contract No. P-1527-V Modification of Vertical Spring Closure, N1BD23 Fire Dampers Gentlemen:
The purpose of this letter is to inform you of the events which transpired after The Robert Irsay Company was notified of a necessary modification of dampers previously procured by Irsay. Of eighty-five (85) dampers, seventy-nine (79) complete.
Please find enclosed three (3) letters from Ruskin Manu-facturing Company to The Robert Irsay Company, dated January 21, 1980, April 4, 1980 and May 22, 1980.
The sequence of these letters should reveal our current status with the modification.
.You will be notified by letter upon completion and acceptance of the modification, i
Should you have any questions regarding the above, please contact the undersigned.
RECEIVED Very truly yours, JUL 221980 THE ROBERT I AY COMPANYc,uomm suomunma fW i
i Richard G. Hughes Field Coordinator RGH:eb Encl.
cc: T. E. O'Connell i
D. Willman
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S/0 Doc. Center, Mike Brown, Joe Carey HEATING e VENTILATING e AIR CONDITIONING
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P.O. BOX 205. PERRY, OH. 44081 PERRY NUCLEAR POWER STATION (216) 259 5 CHICAGO, IL. TOLEDO, OH. JACKSON, MS. OENVER, CO.
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, ROSKIN Manufacturing Company s
yl,'e,i;,,u,,,,,,,e4ngo Phone 816 7617476 e airhandling specialts.os
.,.2 TWX 910 777 7041 TELEX 42 4102 Factories: Parsons and Great Bend, Kansas Representativos in all Major Citics
. January 21, 1980 Mr., Richard Reineck The Robert Irsay Company
' P. O. Box 205 Perry, Ohio 44081
Reference:
PERRY NUCLEAR STATION P.O.# FO-707-46-0
Subject:
Ruskin's Vertical Spring Close 1BD Fire Dampers Vertical IBD type Fire Dampers with spring closure built by Ruskin after June 1979, have upring brackets installed with two rivets through the bottom of the frame and a tackweld holding the top of the bracket to the blade guide.
Previous to this date, brackets had not been tackwc3ded to the binde guide, iddition of the tackweld came about af ter noting that repeated clouings of the blado package during air test at our laboratory p
caused some bending in the brackets.
Fastening of the bracket to the blade
-\\
guide was to provide extra support for the bracket; however, it also alters the shape of the spring holding slot.
This was discovered recently when we recieved a report from one job site of some springs coming out of brackets while, the damper were being cycled.
The engineering firm for this job has advised Ruskin that this problem is reportable under 10CFR part 21.
Ruskin'has reported it accordingly.
Ruskin, with the help and' cooperation'of the engineering firm for the project where this problem was discovered, has come up with a simpic method for climinating this problem.
It consists of placing a #6 screw using a washer, star lockwasher and hex nut t;hrough the narrow portion of the spring slot (see drawing 5398 attached). This fix was successfully tested on a " worst case" damper at our laboratory, af ter duplicating'the spring slipping problem.
I Ruskin can furnish certified hardware for field installation where possible, and will help, with alternatives it field installation seems impractical.
It should be noted that this situation does not alter the ability of Ruskin's fire dampers to survive a scismic event and remain intact and operable.
Ilowever, it can possibly affect the complete closure of the damper and should be corrected.
CONTROL DAMPERS FIRE DAMPERS BACKDRAFT DAMPERS LOUVERG
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Ruckin'c, Vortical Spring Clega IBD Fire Dampers p
January 21, 1980 Page 2 Thank you for your cooperation in this matter.
I;
- Sincerely, RUSKIN IANUPAC11JRING COMPANY
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Thomas D.11111 Executive Vice President and General Manager TDil:csh
Enclosure:
Drawing 5398:
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' ~ RUSKIN Manufacturing Company 8,*n',iew,u;, sour;saoao l
e Phone 816 7617476 e airhandling specialtics TWX 910 777 7041 TELEX 42 4102 Factories: Parsons and Great' Bend, Kansas Representatives in all Major Cities May 22, 1980 The Robert Irsay Company P. O. Box 205 Perry, OH 44081 RECEIVED Attention:
Mr. Richard'Hughes JUL 221980 Subj ec t :
Modification of Vertical Fire Damperd
- gsgygg Enclosed you will find a copy of Field Rework Plan.
Please locate these dampers in the list and let us know what do we have to have in order to get to the plant and do the modifi-cation.
Ruskin Service Contact is Mr. Earnie Reed.
You can contact him and make the arrangement for these modifications.
If there are any questions please contact me.
RUSKIN MANUFACTURING COMPANY Yf d
Hossein A. Novin Proj ect Manager HAN:skh j.-,.
CONTROL DAMPERS o
FIRE DAMPERS o BACKDRAFT DAMPERS o LOUVERS'
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i FIELD REWORK PLAN
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Customer:
Name The Robert Irsay Company Address P. O. Box 205 Perry, OH 44081 Individuals to Conract Phone
'. Richard llughes
' 216-259-5799
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Proj ect - Information :
Job Name Perry Nuclear Power Station
.< Contract /P.O. # ' F0-707-46-0 Customei-Identification #
Ruskin # 0038 3.
Equipment to Which This Plan Applies,:
Vertical Fire Dampers (see Attachment 2) 4.
Supplier:.
'Name:
Ruskin Manufacturing Company Address:
Box 129 Grandview, Missouri 64030 TWX:
910 777 7041 Telephone:
816-761-7476 Telex:
42.4192
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Project Manager:
Hossein A.
Novin Nature of Problem / Scope of Work:
See Attachment 1
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N ELD:;(EWORK PLAll cas 4
//0038 FO-707-46-0 6
Documents Required to Accomplish Work:
Perry Nuclear Ruskin Dwg./ Document No.
Cus tomer Document No.
5566 5567 4311 7.
Repair Material Certification Required:
Yes X
No 8
Special Site Services / Equipment to be Provided Ruskin by the Site Constructor:
9,'Ruskin Service
Contact:
Earnie Reed (816) 761-7476
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Site Contacts:
Richarcl Hughes
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11 Remarks /Special Instructions:
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Attachment No. 1 l
FIELD REWORK PLAN i.a.
NATURE OF PROBLEM 5.a.1 It was observed that the negator springs of type NIBD23 vertical fire dampers can slip out of their spring slots if the bracket is bent or deformed, thereby preventing full closure of the damper.
5.a.2 It was observed that the damper curtain did not always close completely on dampers 9" high and less.
5.b.
SCOPE OF WORK 5.b.1 Problem a.1 is considered to be generic to all type NIBD23 vertical fire dampers furnished to nuclear plants since June 1979.
5.b.2 Problem a.2 is considered to be generic to all small vertical fire dmapers furnished 9" high and less.
5.a.
DAMPERS REQUIRING REWORK 5.c.1 The type NIBD23 vertical fire dampers requiring rework are listed on Attachment 2 to this work plan.
5.d.
WORK TO BE PERFORMED 5.d.1 Ruskin shall remove number six (6) screw, washer and hex nut from each type NIBD23 vertical fire damper listed on to this work plan if previously(replacing installed.
Ruskin shall furnish and install new clamps
- 6 screws) per Drawing No. 5566.
5,d,2 Ruskin shall furnish and install a " snap-in-strip" on cach type NIBD23 small (9" high & less) vertical fire i
damper identified by an asterisk on Attachment 2 to this work plan ~per Drawing No.
5567.
5.d.3 Ruskin shall verify the removal of the original number six (6) screw if previously installed, and the installation of a new clamp in each spring slot in each type NIBD23 vertical fire damper listed on Attachment 2 to this work plan.
In addition, new " snap-in-strip" shall be attached to each small (9" high & less) vertical fire damper iden-tified by an asterisk on Attachment 2 to this work plan.
After verification of clamp installation on all vertical fire dampers, and verification of.new "sna
. installation on all small (9" high & less)p-in-strip" vertical fire dampers, Ruskin will operationally test vertical fire damper by releasing the blade package by hand.
If a dampuc does not close properly by hand, it will be retested by m-
' ink c imni n ti n-f e condition.
The
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i Page 2 hand release will be attempted first since it allows for a greater margin of safety for verifying proper closure due to a less uniform release of the blades.
'Ruskin must be afforded necessary access to perform this work.
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16 x 14 1x1 p9~ h-77 p{$h 10-IB-308
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ED-RB-318 16 x 14 10-IB-401
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'gFD-IB-402 14 x 16.W 1x1
-RB-601 16'x 14 1 x 1,$ d [ D. h 1 x 1 / [ / I/ h FD-IB-141 29 x 17 FD-IB-142
, 29 x 17 1x 1 gj [ h 10-IB-143 27 x 37 1x2,fp pj2;((
FD-IB-247 22 x 10 -v' -
1 x l-IB-248 22 x 10 1x1 J/
FD-IB-347
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ecrry Nuclear FD-707-46-0 VERrICAL FIRE D,WPER LIST
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'FD-CC-307 30 x 36' 1 x 2' g $k,
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FD-CC-409 18 x 10 1 x 1 /X h
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FD-CC-410 36 x 34 7
FD-CC-415 18 x 10 l'x 1 //' [//[.
' ink.gp;- /4h FD-CC-416 36 x 34 -
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FD-CC-421 18 x 10 1x1 FD-CC-422 36 x 34"
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j FD-CC-427 18 x 10 1x 1
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^ CC-428 36 x 34.
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FD-CC-451 18 x 10
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1D-RB-104 16 x 14
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Identification Size y
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Ccaments FD-CC-305-12 x 10 1x1 g FD-CC-306 11 x 11 1x1ge fdh FD-CC-308 12 x 10 1 x 1 f<'
FD-CC-712A 48 x 48 2 x 2 g/'
.I-ylm>0cias.ta he r uv we gavrior FD-CC-712B' 48 x 48 2 x 2,sg
, J.,. ;.:.,., i r,. i n.,,,, - c's ! r-) e}c FD-CC-452 18 x 10 1x1 g [/)),[; '
FD-CC-454 18 x 10
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-FD-CC-456 18 x 10 1x1 c-g [g FD-CC-458 18 x'10 1x1 ef-gf FD-CC-719 24 x 24 1 x 1 ' g f t,y k.'
ss-CC-720 24 x 24 1x1 en.
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FD-CC-311 12 x 10 1x1',T(
FD-CC-312 11 x 11'
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FD-CC-314 11 x 11 1x1 ff ' f'#/[
FD-CC-315 10'x6;tb 1x1 g F
FD-CC-316 11 x 11 1x1
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FD-CC-412 18 x 14 1x1 <T lu-CC-413 29 x 17 1 x 1 /X
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- 0038 VERTICAL FIRE B'MER UST FO-707-46-0 Perry Nuclear m
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, W,..M FD-CC-424 18 x 14 1x1 l'x 1 g eg g FD-CC-425 29 x 17 '
FD-CC-426
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'18 x 14 1 x 1,pr g.f,7j{h FD-CC-431 29 x 17 1x1 E-CC-432 9'x7$'
1 x 1 g gyj/.h g [E//h FD-CC-705A
' 56 x 48 2x2 g [Qf*'
' _FD-CC-70'5B 28 x 48
'1x2 FD-CC-706A 56 x 48 2x2
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' 'ROSKINManuf:cturing Company Bo RUSKIN,.i,n.nana,,.ci,w.,
ac;;, sat.l,%L9s an ew, Missouri 64030 TELEX 42 4192 Factories: Parsons and Great Bend, Kansas Representatives in all Major Cities CERTIFICATION OF CONFORMANCE Purchase Order Number:
FO-707-46-0 Project Name:
Perry Nuclear Power Station Customer Name:
The Robert Irsay Company We hereby certify that all material supplied under this certification (Fuse Links, S-llooks, and Spring Bracket Clips, etc.) are in strict accordance with the drawings and specifications covered under the above purchase order requirements.
Evidence to this effect is on file and subj ect to examination at our facility.
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.a 9tobert Van Becelacro.
E ' 3 D - S' E Date Vice President, Engineering
. V, $1Mw Y /%ww Ho~ssein'A. Novin
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CONTROL DAMPERS FIRE DAMPERS BACKDRAFT DAMPERS LOUVERS
yawu l0-707-46-0 clear CERTIFICATE OF CDNi:0RMANCE I ccrtify that the identified work was performed correctly and meets the re-quirements of this plan.
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bv'i. n t!',bt'Y/ :/ b..$u/,. lb$':. As-la4 7
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.. b..r a f /,.' D. A.. A r N.,e.,.t., bi6n$ + $....<.Iw...v.M '?dJQe,u.3 J
f k u n.,iDsb k Gh,..'y<S ).i n..D.:<-lZ, 8...).:../.A 18
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I certify that the reworked equipment meets all the requirements of the Purchase Order for the original equipment, including warranty.
If the original equipacnt is environmentally and/or scismically qualified, the modification perfonned utilizing this plan does not alter the qualification of the identified equipnent.
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n 3SignatureofSupplierRepresentative RUSKIN MANUFACTURING COMPANY Company
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.nn )%.g Title
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/-/-),s/
.Date 00.4 M S:
See comments on' Attachment #2. Also IB 401. 402. 247. 248. 347 cant.ot be done at this time. Will be done by Irsay 'later Land we will be
, notified by letter as we will do when dampers are accessible.
Item
- CC723 to bc repaired and'Q.C. will check and notify Ruskin by letter.
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r cRUSKINManufacturing Company Box 129 acanay,c,, u;ssourss4020 f%
3 Phono 816 7617476 s air handling specialtics TWX 910 777 7041 h
TELEX 42 4102 Factorics: Parsons. Groat Bond and Paola, Kansas; Anaheirn, California; and Mindon, Louisiana April 4. 1980
.e..,
Robert Irsay Company '
7 P. O. Box 205
,,, Perry, Ohio 44081 A c t.en tion: Mike Szabo
, y,' '.
Refcrence: PERRY NUCLEAR STATION RECEIVED P.O.0 F0-707-46-0 106 Units JUL 221900 NM7aY,Id
'~*
Subject:
Vortical Spring Closure NIBD23 Fire Dampers In our notice to you dated January 21, 1980, we addressed a problem relating to Ruskin's vertical, spring close, NIBD23 Fire Dampers and a fix or correction was suggested which consisted of fastening a #6 cerew in the narrow portion of the slot in the spring brackets.
Although it appears that this method should have uliminated the problem, an engineering firm has indicated to us that some of the screws worked loose during shipment.
This raises the possibility that the use of
,?fll*'.., i,";;,. any activity relative to the installation of this fix.
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screws as a fix is questionabic. We therefore request that you stop
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Ruskin has now developed an alternate fix consisting of a small metal clamp which attaches to the spring bracket and provides a positive stop for the spring (see drawing 5564).
A second prob 1cm has also been brought to'our attention.
If the blade package'in vertical units less than 9" high is shifted such that the
.?
Icading edge of the bottom blade rests higher than the trailing educ, the blades may. jam when released.
Ruskin has developed a snap-in' strip which when installed will hold the bottom blade in the proper orientation and insure c'omplete and consistant closure (see drawing. 5565).
Wh t
CONTROL DAMPERS FIRE DAMPdRS BACKDRAFT DAMPERS LOUVERS e
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April 4 1980' D
..h Page 2.
1 h
Ruskin recognizes that under the terms of its contract with you it is obligated to remedy deficiencies.
Under the assumption that the problems
'I
are deficiencies or non-conformances (Ruskin has reported both these c, ',
inatters to the NRC in accordance with the requirements of 10 CFR part 21)
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Ruskin stands ready to perform the necessary work at the job site itself.
Ruskin desires to make certain that the deficiencies or non-conformances
,d,2'..*i..,,...... are remedied.
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Ruskin will in' the near future contact you so that an appointment will
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.be set for Ruskin's personnel to appear to the job site to perform the corrections referred to.
In the meantime, Ruskin suggests that installation A./ ",..
JW,i;t;.f*,'. of the NIBD23 Pire Dampers not already installed be dulo r Y*
ed until Ruskin's a.,..;.;hw...
. personnel have had the opportuni,ty to make the.correcrlons. '
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Thank you for your cooperation.
Sincerely, v:?;
5.D. *.
RUSKIN UFACTURING COMPANY s
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Thomas D.11111 Executivo Vice President and General Manager TDil:csh p.;,o.h,..
Enclosures '. Drawings 5564
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