ML20129B634
| ML20129B634 | |
| Person / Time | |
|---|---|
| Site: | Palo Verde, Clinton, 05000000 |
| Issue date: | 04/22/1985 |
| From: | Felton J NRC OFFICE OF ADMINISTRATION (ADM) |
| To: | Mcdevitt J KIRKPATRICK & LOCKHART |
| References | |
| FOIA-85-166, FOIA-85-181 NUDOCS 8507150550 | |
| Download: ML20129B634 (2) | |
Text
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- p* *%q#g UNITED STATES Rh l 8 o NUCLEAR REGULATORY COMMISSION ;
3 E WASHINGTON, D. C. 20655 J
% ,,,,, # APR 2 21985 Jerry S. McDevitt, Esquire Kirkpatrick and Lockhart IN RESPONSE REFER 1500 Oliver Building TO F01A-85-166 Pittsburgh, PA 15222 AND F01A-85-181
Dear Mr. McDevitt:
This letter completes our response to your March 8 and 15,1985, letters in which you requested, pursuant to the Freedom of Information Act (FOIA),
specified documents regarding an alleged deficiency with certain model 272 grilles furnished by Titus Products for installation at the Palo Verde and Clinton nuclear power plants.
Since our April 9, 1985, response to these requests, our staff has identified additional records responsive to these requests. We are placing copies of these records, identified on enclosed Appendix B, in the NRC Public Document Room (PDP.) located at 1717 H Street, NW, Washington, DC 20555. The records will be filed in PDR folder F01A-85-166/F01A-85-181 under your name.
Sincerely, 1 a - . *_m_ .
J. M. Fe ton, Director Division of Rules and Records Office of Administration s
Enclosure:
As stated 4
s 8507150550 850422 hEV -166 PDR
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Appendix B to FOIA-85-166 and F01A-85-181
/ TEM NO.
NO. DATE PAGES DESCRIPTION 1.
,.11-6-84 4 Ltr.from Ruskin Manufacturing Company to NRC (I&E) re: Part 21 (fire, dampers failure to close under normal duct pressure)
. , 2. 3-29-85 4 Ltr from WPPSS to NRC Region V subj: 10 CFR 50.55(e) Titus Model 7
272 Trille Tension Wire (D/N #58)
- 3. 8/27/84 1 Morning Report - Region V .- Fire dampers were found to close inconsistently...
- 4. 8/28/84 4 Morning Report - Region V -
- 5. 9/22/84 1 Outstanding item - Palo Verde Unit 1
- 6. 9/19/84 3 Ltr from APS to NRC Region V subj: Interim Report - DER 84-56 A 50.55(e) Potential.ly Reportable Deficiency Relating to Fire Dampers Close Inconsistently
- 8. 11/16/84 el Ltr from ANPP to NRC Region V subj: Time Extension for Report -
- 9. 11/28/84 1 Ltr f rom ANPP to NRC Region V subj: Time Extension for Report - ,
- 10. 12/8/84 5 Ltr from ANPP to NRC Region V subj: Final Report - DER 84-56 11 3/22/85 18 Ltr from NRC Region V to APPS subj: NRC Inspection of Palo Verde Units 1, 2 and 3 12, 3/11/85 1 Record of telephonic Part 21 report.
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In accordanie with the requirements of 10 CFR part 21. Ruskin Manufacturing My ;
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- located at 3900 Dr. Greaves Road Grandview, Missourt 64030, is herewithy
. reporting that we have discovered a deffelency with equipment furnished by Ruskin
, .Mariufacturing Company for Nuclear power Plant application ,
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' 'On ' August 7,,1984 Ruskin received a letter from The tialdinger Corporation '
addressing seven (7) fire dampers failure to close under normal duct pressure at
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10n August 13. 1984 .Ruskin. visited the jobsite to inspect dampers. The results of.. .
L the : inspection revealed damper condition to exhibit bent blades, bent'b_ lade. ., ; ~;
r tracks, rusPand itnc rich paint em7springs. - C.. & .,a '
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y0n ' August 20D1984 ;after Engine. ~ing' review _of i_
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' ."As"a. resalt foOth'is~ review Ruskin~ recommended that the blade packages',be"replacedC &>
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^~ On October 30 '1984 Ruskin was notified.' by The lealding'er Corporation, that'the
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? new blade packages had been installed and tested. The. fir's dampers with th Cnewly-( ^
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- (Riikin Engineering immediately began'to evaluate the probles to detere1pe the w f .,
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' E cause of the; dampers fallsre to close under air flow. Results of this evaluation-
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accurately. depict' actual;1nsta led conditions,
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- may not result in proper performance as tested to AMCA., Ruskin.'en Moveshar 2 ; -
I' m.nd 51984, performed air . flow tests in accordance with AMCA 500 with damper .
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~ ounted on face of tunnel as well'as with damper mounted in ductwork. The results - [
, ['..ef this test; indicated that face , mounted damper.would close 'at much higher static ~ !
pressure than the damper which was' installed in'doctworkd '
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". all field' installed conditions, and relationship between face mounted damper and .
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damper installed in ductwork cannot be accurately calculated. Ruskin recomer.ds - -
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^[' ;, flow conditions' be tested to verify proper operation. This condition affects on s
g.. interlocking, blade fire dampers Model IBD-21,:IBD-23 and NIBD-23 supplied with 5
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'yc Ruskin is currently- researching methods to modify fire dampers to ensure closu..re. *
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> d p ;).f ..fl this e} - letter identifies the affected jobsites by location y' y a V .s A;^ttachment:1- to~ , .. ..
and the
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~ ~-n 4 :In closing, please find enclosed a copy of the letter describing the situation " J g contained in. this letter, which will be sent to each affected site. ' - '
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Thank you for your cooperation. - -
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- Fire Damper Closure Under Air Flow); , .,
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'IBD-23 NIB 023 - - ,
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ti, Mair.. flow conditionsf.to our attention that 'some fire dampers wili. not close.under,. f i
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$lmay not accurately has det depict reined actual. that field our installed Aes'tconditions. methods utilized for' closure Tunder
% as recommended by AMCA 500, were tested per figure 5.5, face mounted on theRuskin .L fire dam
? ^ tunnel. - Ruskin has c'tscovered that when dampers are tested per figure 5.3.y. - ,
M* mounted in ductwork, that the performance of the damper under atr flaw is ? . %,
. , substantially reduced. Additionally, since Undomriters Laboratories do not' m require despers to be tested under air flow conditions, this discovery will:in me?
, This ondition'affects only these dampers supplied with closure f,'p spring
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'5H closure' springs, which require cle'sure under air flew condittees, be tested.te- T'. ' y '
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?'. Ruskin Manufacturing Company has notified.the Nucle % ar Regulatory Commission ofc 's' this situation in'.accordance with the requirements of 10,CFR part 21.
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Washington Public Power Supply System, Box 1223 Elma, Washington 98541 (206)482 4428 - - - March 29, 1985 G03-85-167 Docket No. 50-508 U. S. Nuclear Regulatory Commission, Region V Office of Inspection and Enforcement 1450 Maria Lane, Suite 260 Walnut Creek,-California 94596-5368 Attention: Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects
Subject:
NUCLEAR PROJECT NO. 3 10 CFR 50.55(e) DEFICIENCY TITUS MODEL 272 GRILLE TENSION WIRES (D/N#58) , On March 11, 1985, the Supply System notified your office of a potential 10 CFR 50.55(e) deficiency concerning the subject condition. A subsequent Engineering / Licensing evaluation has determined that' if the deficiencies remained uncorrected they could have affected adversely the safety of operations of the plant. Therefore, the subject condition is reportable in accordance with the provisions of 10 CFR 50.55 (e)'. Attached is a Supply System approved Interim Report. The report provides a description of the deficiency. -analysis of safety -implications and corrective actions taken/ planned. A Final Report will be prepared as soon as information on the nature of the rework and a schedule is received from the Vendor (Titus). I Cy t*th > I t en u t1 h l
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g, . Should you have any questions or desire further information, please contact me directly. O M.N h A. D pKohler-
. (760) g WNP-3 Program Director DRC/cae Attachment cc: Mr. J.'A. Adams, NESCO.
Mr. D. Smithpeter, BPA Mr. W. L. Bryan, Washington Water Power Company Mr. R. V. Myers,~Puget Sound Power & Light Company Mr. W. L. Weislogel, Pacific Power & Light acompany. Mr. B. D. Withers, Portland General Electric Company Mr. J. R. Lewis, Bonneville Power Administration-Ebasco, Elma Docket Control Desk - U. S. NRC l Y l
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WASHINGTON. NUCLEAR PROJECT N0. 3 (DOCKET 50-508) 10 CFR 50.55 (e) DEFICIENCY INTERIM REPORT TITUS MODEL 272 GRILLE TENSION WIRES (D/N#58) DESCRIPTION OF DEFICIENCY Grilles are used to direct air flow exiting from the conditioned air -
- supply ducts to spaces requiring ventilation.
Titus Model 272 Grilles are used in the following safety-related HVAC systems'in WNP-3: Control Room HVAC Electric Equipment Areas HVAC Battery Room HVAC RAB Main. Ventilation System Diesel Fuel Oil HVAC Diesel Generator HVAC Fuel Handling Building HVAC The Vendor, Titus Products, has identified the following deficiency in their Model 272 Grilles. If the blades are closed, some of the -tension wires used for adjustment of blade position will not remain in place (i.e., they will fall off the grilles). The Vendor (Titus) has stated that this deficiency would prevent the HVAC systems on which the grilles are used from functioning as-designed, since it would cause the grille blades to remain' shut, thereby preventing air flow. One design objective of these ventilation systems is to supply fresh uncontaminated air to various areas of the plant. ANALYSIS OF SAFETY IMPLICATIONS The problems with these grilles,' if left uncorrected, could reasonably- be postulated to adversely affect the safety of.the plant, since the result would be to prevent' conditioned air flow to critical areas of the plant.. This would adversely affect efforts to mitigate or prevent release .of off-site radiation. This deficiency, therefore, is considered reportable under.the criteria of 10 CFR 50.55(e). D e -- -%- -- ,
CORRECTIVE ACTIONS
- Titus _ has stated that they have conducted tests and have determined that the necessary rework would consist of replacing the existing tension wires and' adding retention clips. It is anticipated that this work will be done in'the Vendor's shop.
At the present time, the safety-related Titus Model 272 Grilles are_ not yet installed, and are located in the WNP-3 Warehouse. It is not known, at this' time, when Titus will accept these Model 272 Grilles back at their plant for - rework. Titus Products has been purchased by another interest. Since the new -owners 'are not responsible for this deficiency, the rework requires a commercial agreement between the parties -involved. The date for completion of_ the commercial agreement has not been established, and the schedule for rework is, therefore.-indefinite. A Final Report will be prepared as soon as information on the exact nature of the rework and a schedule is received from Titus. 8 6 h ee P n
. . , , :. 2 EECEl'e'Eb F:.oc Arizona Public Service Company 54 SfP 24 -Plf (: op September 19gy ,
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- <- r ANPP-30569-TD5 U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, CA 94596-5368 Attention: Mr. T. W. Bishop, Director Division of Resident Reactor Projects and Engineering Programs n-ww - - . . - - , ,
Subject:
k,ateria Report ,,iDER ' 84-56; A 50.55(e) Potentially Reportable Deficiency Relating To Fire Dampers Close Inconsistently. File: 84-019-026; D.4.33.2 Ref erence: Telephone Conversation between J. Ball and T. Bradish on August 22, 1984
Dear Sir:
The NRC was notified of a potentially reportable deficiency in the referenced telephone conversation. At that time, it was estimated that a determination of reportability would be made within thirty (30) days. Due to the extensive ' investigation and evaluation required, an Interim Report is attached. It is now expected that this information will be finalized by October 31, 1984, at which time a complete report will be submitted. Very truly yours, h E. E. Van B runt, J r.
. APS Vice President Nuclear Production ANPP Project Director EEVn/TRn/nj Attac1 ment l
cc: See Page Two
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. INTERIM REPORT - DER 84-56 POTENTIAL REPORTABLE DEFICIENCY ARIZONA PUBLIC SERVICE COMPANY ( APS)
PVNGS UNIT 1
. ... . s,-
I. Potential Problem SFR 1HJ-153 identified that fire dampers were found to close inconsistently. NCRs SM-4579 and -4580 identified dampers HJB-Mll, HJN-M102, HJB-M08, HJB-M15, HJN-M60, HJN-M61, HJN-M62, and HJN-M107 as not closing fully under normal operating flow during the CO2 and Halon System pre-op testing. II. Problem Resolution Plan Bechtel Engineering is currently studying this problem to determine reportability and the technical justification .for corrective action. New fire damper blades are being installed for additional testing. The test results are scheduled to be complete by September 24, 1984. In addition, The Waldinger Corporation has been requested to provide Bechtel Engineering with information regarding the cause, resolution, and corrective action regarding this i deficient./. Response to this request is forecast for September 26, 1984 III. Projected Completion of Corrective Ac' tion and Submittal of the Final Report-l The complete evaluation and final report are forecast to be completed by October 31,-1984. f D
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4 Mr. T. W. Bishop - DI!R 84 Page Two
. .n . .w cc: : Richard DeYoung, -Director Office of Inspection and Enforcement -
U. S. Nuclear Regulatory Commission Washington, D. C. 20555' T. G. Woods, Jr. _ D. B. Rarner W. E. Ide D. B. Fasnacht A. C. Rogers L. A. Souza
'D. E. Fowler T. D. Shriver j
C. N. Russo l J. Vorees - . J. R. Bynum J. M. Allen { J. A. Brand l i A. C. Gehr -l W. J. Stubblefield' W. G.'Binghas
~R. L. Patterson R. W. Welcher-
'H. D. Poster
;D. R. Hawkinson LJ E. Vorderbrueggen R. P.- Zimmerman S. R. Frost-L. Clyde M. Woods T. J. Bloom 4-Records Center Institute of Nuclear Power Operations 1100 circle 75 Parkway, Suite 1500 ,.
Atlanta, GA 30339 [ 1 i:
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OUTSTANDING ITEM r.-- LICENSEE REPORT Docket Number ' '4
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Item Number
- Was the report submitted.on time?
OI Type Followup Resp. g l e-/' - f ; - 1 1, . _ - - n M--it,-een t ain-a El--informa e ion required by 10 CFR 50.737 - Event Date Report Date d I 2 2 MM D D E' t/. C 9 - 2 # -- R // ~
/ -Is followup action necessary?
Y Yi M M. D.D Y Y Descriptive Title l Mo . < 'c' > a ) ,,. , .. r <
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" Comments:
This report was reviewed in -accordance with. Region V Instruction No. 0402 and IE Inspection Procedure No. 90712. Required actions, if any, have been initiated, h YW)*... ;{r . is.b s %
<tn Proj e'et - or Cognizant Inspector Cognizant Section Ch1M -
- For numbered licensee reports enter 4-digit Tollovup Responsibility 01 Type Codes report number followed by report category on.1 revision number. 0 - Operations Projects 0 - 10 CFR 50.55(e) Report Report cateRories are R - Operations Resident R - LER or Other Licensee Report C = 10 CFR 50.55(c) Report c - Construction Projects ,
I. - 1.tcensee Event Report (1.ER) F - Construction Resident , P - Part 21 Report E - F.ngineering E - Environmental Occurrence M - Radiological Safety X - Spects1 Report 5 - Safeguards / Physical Security Y - Other P - Emergency Preparedness . F. sample 01 Number: 84-03-1,1 Tor reports not numbered by licensee, enter ADP Entry by on / /
- event date or use 01 number system controlled by Project Inspector RV Form 111 (4/84)
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.0ATEa..AUGuaT. 24, 1984..
8tAIDNAL_ ACTION _ - -*" 8""""******
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0 PLANT VENT - AT 4 11 A.M..ON AUGUSTJ6.19 es. C TERMINAT1^k >
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EACIPIC.SAS.ANO FROM SENIOR ELECTRIC COMPANY
. __. TELEfjiQht C ALL REAIDENT.1NaPECIA8 SURVE!LLANCE 0F RELE ASE FUNCTION FOR TME CONT AINM130PER ASLE._THIs ACTIVITIES E GAS ON ONE OF THE _ *(T
_QIA9LO C ant 91L 1 ) =*
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04 50=2T5 hAS DETEPMINED.TO At.IMOPERAeLE SECAUSE THE OT 4ADIA110N MnNITDR_ MAS tt F ARED. AkD.IN ACCORDANCE WITH DEEkEA512rn ae
*I ON AUGUST 23, 1984 CQRTAINMENL Pnaar D-~ 6:00 P.M. w!TM THIS 816NAL * ! '.
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. ~UNDEAmAY..ERAM 1964 WNILE 1011LA.!i ONTHE .AUCONTAINMENT _ _=i 44 P.M. ON AUGUST 2A. t FUNCTIDM WAS.Ih0EERam't 4 MER* EFFLUE
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- -- a; PURSt.3YSTEM ISOLATIOM.WAS NO FOLLOWUP A _ . ~ RELEASE PER peOF stif R4010ACT
- THE LICLNatt NAS MAQF .
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g_0URING_MALON.A D CO2.jYSTE43NE?0P_TESTINS,_f1RE=__CONSI C=~ .
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. JgLEPH_0NE . C ALL _ SAMPER$ NERE FOUND TO CLOSE INTHE aan pas et ama t ED C AuSE _Of_ IMit It IMGMANL
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- PWN6fT _CONIAINmtNT.380 LATHE LICENSEE variawup pra WILL senz PROW 1 0t_4R 108T!AL_CE8.tige racesTHAT Thty
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- ,,_,AR120NA PUsLIC #40m LICENott WITH SHARP METAL EOGES OF TME FIRE STOITTEN REPORf IN_30. Days.Jr
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OPERATO __AT THE JOS 8!TE h! _
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FRON.t!CENsEE _ LuPRICATro NITN sun.ALL St MERE VES Sue 8E00tNTLY LusRICATE - ON'4/37/84 _ NttULA EP t Luer! CANT (C4=
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.._,, (CPC) AUMILIARY TRIP g.ggg _ .__ *
- OPERATING AT 180 PENCENT POWEN WHEN A (LF a n -NTR OSLE M *'
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= DEDUCTION.T0 50 PERCENT fDuCR. C0kDEh8ER.2AcumLPADSLE"! "'
" CAUSED A TURe!NE TRIP AT 5:25 PDT TER WHICH TNE CPC
- h" AU1!LIARY TRIP OCCURRED. THE AU11 ARV TRIP.!S NOT.A *
= TECHNICAL SPECIFICATTON REQUIREMEN AT LOW PowFR LEVELS
- AND THE LICENSEE._IS PURSUING ELIMjNATION OF.TME. TRIP.5ELO" y "!
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=0RNING REPORT = REGION V .
. ...__.__...._.. - DATE l._. AUGUST. 28. 1984._._.. .. .. . ,
PACILITT._ ___NOT!PICATION._ . ITEM. 0R. EVENT.._. _ _ _ _ _ _ . - _ - _ _ _ *E8!ONAL_ ACTION
- l PACIFIC.GA1 AND TELEPHONE. CALL AT .4 11__A.M._0N_ AUGUST _24 1984e_HNILE_PERFARMINn rattagup__ggg_gg_3ggs =
ELECTRIC COMPANY FROM SENIOR SURVEILLANCE ACTIVITIES ON ONE OF THE TWO PLANT VENT = P* ___DIA8LO. CANTON _1 RE8!0ENT. INSPECTOR ___. WOSLE 848 PA0!ATION MONITORS THE AUTOMATIC.. TERMINATION = D3 50=275 0F RELEASE FUNCTION POR THE CONTAINMENT PURGE SYSTEM =
= WAS. DETERMINED _TO SE. INOPERABLE. THIS. FUNCTION.WA8 =
- INOPERABLE BECAUSE THE OTHER PLANT WENT NORLE GAS *
" RADI ALIOM_ MONITOR MA8_ CLEARED _ ANQ_DEENERG12En AT *
"* 4100 P.M. ON AUGUST 23e 19R4 IN ACCORDANCE WITH =
- PROC E DURE 8_ A ND _TML_ A S SOC I A TED_ C O NT A !NMEN T_PURGF *'
= SYSTEM ISOLATION SISNAL WAS GE8ET. WITH THIS O!GNAL = = RESEf t_THE MIGH_RADI ATION _ SIGNAL. FPOM TME DTHER = =
- RA0!ATION MONITOR WOULD NOT cat:SE A CONTAINMENT PURGE
- 4
=
8.18 TEM _180LA.TlDMa_ _.A_1DMIAINPENT_RilRGE M AD _SEEN =
=
UNGERwAY F#0M 10: 13 A.M. ON AUGUST 22, 1984 THROUSN =
=
12:4 4_P,M .. _0N AUGUST. 24._L984._kMILE_TFL CONIAIMMEMT; = '
= PURGE SYSTEM ISOLATION FUNCTION WAS INOPERABLE. THEPE = = NA8_N0_PELEASE_0P_RA0!0 ACTIVE _EFFLUEN!L_Y!A lN!4_ PATHWAY. =
THE LICENSEE MAS MADE A PRESS RELEA8g. = '
= = ARIZONA PUSLIC TELEPHONE CALL OURING MALON AND CO2 SYSTEM PRE =0P TESTING, FIRE. FOLLOWUP PER MC 2512 = =
SERVICE CO. FROM LICENSEE GANPER8_WERE FOUNO To.CLOSE..!NCONSISTENTI_0R_NOL_f_ULLY_uMDE8 '
- -~~P V kS S l ' ~ ~ ~ ~ ON 8/22/84 N08 MAL OPERATING PLOW. THE CAUSE OF THIS IS THOUGHT TO * = 03 58 524 BE AN IMPROPERLY 8! ZED SPRING._THE HALON_ SYSTEM _It_USED = = =
IN THE CONTROL R004 . THE CO2 SYSTEM IS USED FOR CLASS 1 = SWIICMG(AR_AND_8ATTERI_ROQMS. =
= = THE LICENSEE WILL PROVIDE A WRITTEN REPORT IN 30 DAYS !F =
THE ITEM IS DETERMINED _TD_8E. REPORTABLE.._(D(A e4=56J - =
= A%IZONA PUBLIC TELEPHONE CALL SERV!CE~CO. DURIN8_ PERFORMANCE _0F_ PRE =0P PROCEDURE _9tPElR001sVALfE FOLLDMUP_EER_2512 = = PR0" L!tENSEE RDAuv23 FAILED TO MEET ACCEPTANCE CRITERIA 0F CLOSING IN = . PVZ68 1 ON 8/22/84 10 SECONOS = V ALVE_CLO.8E D._IN_11_SE.CONDS_2_T_ME_V ALVE 18 A = - -- 04 58=srs CONTAINMENT ISOLATION VALVE IN THE R&DWASTE DRAIN. - - THE_ LICENSEE WILL PROVIDE _A WRITTEN REPOR.T IN 30_DAT8_IF
- THE ! TEM 18 OETERMINED TO BE REPORTARLE. (OER 88 57) =
.- AUTTOMK PUSEYE TE[fPH0k E~CAEL THE FIRE STOPS A80VE THE M0fo# CONTROL CENTER (MCC) FOLLOWUP PER 2512 - SEGVICE CO. FROM LICENSEE CURICLE8_HAVE_SEEN_! NOTAL (ED_JN_SUCH A PANNER THAT_THEY = . -- PVWCS 2 DN'87/22/64 - b4 MAGE CASLE INSULATION. THE CASLES ARE IN CONTACT =
D. N _5 0-52_9 _ _ _ _ _ _ . . _ _ _ _ _ . - -. ~h!TM SHARP METAL EDGES OF THE FIRE STOPS. = THE LICENSEE WILL PROVIDE A WRITTEN REPORT IN 30 DAYS IF
- THE ITEM IS DETERMINED TD,8E.REPORTA9LE. (DER _84=59) =
ARITONA PU8LIC TELEPHONE CALL .A 70T AL _OF_50 LIMITORQUE V ALVE _0PER ATOR8_hERE. !NITI ALLY Pat t 0Mup pep _M1_251a =-
-"- SERVICE"Co. FROM llcER$EE LURRICATED WITN suw=50 EP TYPE LuSRICANT (LI=Ps RASE). = . PVWG8 2 ON 8/27/R4 ALL 50 WERE SURSEguENTLY LUBRICATED AT THE JOB SITE WITM = - -- 03 5 0 -5 2 9 -- ~'- ~ ' - ' ~
- NERULA EP=t'LU4RICANT (CA=COMPLEr RASEi. THE TWO BASES =
=
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CAN NOT PE MINED THEREFORE THE ASILITY 07 TME VALVES. = TO OPERATE IS INDETERMINANT. IN AD0!?!ON, SUN =50 EP *
~~' LURRICANT IS NOT SUALIFIED FOR USE INSIDE. CONTAINMENT. -
TEN OF THE 50 VALVES ARE LOCATED INSIDE CONTAINNENT.
- THE LICENSEE WILL PRnVIDE_A WRITTEN REPORT IN 30 DATS_!E _...__.._
=
THE ITF4 !$ PETERMINED TO'6E RFPORTA9LE. (nER R4=60) *
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. 80UTMER4 L = 0Z%! A TELE 7HO%E CALL THE UNIT EXPERIENCED A' TOR T;!P FROM APPIOMINATELY FOLLO!UP PER MC 2515 > '
= EDISON _CO>cNY FPON SENIO1. . . .. .10. PERCENT P02ER DN AUGu.a 26e1984.AT et16.PDT FROM A
- SONOS 2 RE810ENT INSPECTOR CORE PROTECTION CALCULATOR (CFC) AUMILIARY TRIP '
_DN 58= H1. . 0N.8/27/84 _ _.. .. (AMIAL SHAPE.INDEM TRIP)..THE. UNIT HAD PREVIOUSLY.8EEN OPERATING 47 100 PERCENT POWER WHEN A LOAD CENTER PROSLEM ' 3
- ___ . CAUSE0 LOSS.0F A FEED. WATER. PUMP OIL PUMP.AT 5820.PDL FERCING_A
- REDUCTION TO 50 PERCENT power. CONDEN8FR VACUUM PROBLEMS CAUSED..A.TURDINE. TRIP.AI 5125.PDT M TER_WMICH THE_CPr AUu!LIARY TRIP OCCURRES. THE AUNILIARY TRIP 18 NOT A a
_ . . _ . . ._ _ TECHNICAL 8PECIFICATION. REQUIREMENT..AT LOW. POWER.LEVFt#
- AND THE LICENSEE IS PUR8u!NG ELIMINATION OF THE TRIP PELOW *
- 20 PERCENT POWER.. RESIDENT..!NSPECTORS AREJOLLOWINE TMF "
POST TRIP REVIEW.
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- ' ' l'.fu Arizona Nuclear Power Project si ;p, _3' . !
p.o Boxs2034 . PHOENIX. ARIZONA 85072-2034 ' l
^
October 30, 1984 ANPP-31007-TDS/TRB U. S. Nuclear Regulatory Commission Region V Creekside Oaks Office Park 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. T. W. Bishop; Director Division of Reactor Safety and Projects f iency Relating To Fire Dampers Close Inconsistently. File: 84-019-026; D.4.33.2
Reference:
(A) Telephone conversation between J. Ball and T. Bradish on August 22, 1984 (B) ANPP-30569, dated September 19, 1984 (Interim Report)
Dear Sir:
The NRC was notified of a potentially reportable deficiency in Reference (A), and an Interim Report was transmitted by Reference (B). At that time, it was estimated that a Final Report would be available by October 31, 1984 Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by November 16,1984, at which time a complete report will be submitted. There is no new information or change ~ to the Interim Report at this time. Very truly yours,
. , ~
Gn
~
-(, CA1A E. E. Van Brunt, Jr.
APS Vice President Euclear Production ANPP Project Director EEVB/IRB/nj cc: See Page Two A vll I I,I &v-o-Mnu Ip. 'l-
ms Arizona Nuclear Power Project P.O. box $2034 e PHOENIX, ARl2ONA 85072 2034 , , ii),' l , M e p ,7 November 16, 1984 TGl0l.1* .t . .. ANPP-31162-TDS/TRB U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 Attention: Mr. D. F. Kirsch
Subject:
- ITime Extensios For Report'- DER ~84456 "
~
~
. A 50.55(e) Potentially' Reportable' Deficiency Relating To Pire Dampers Close Inconsistently.
File:. 84-019-026; D.4.33.2 1
Reference:
(A) Telephone conversation between J. Ball and T. Bradish on ' August 22, 1984 (B) ANPP-30509, dated September 19, 1984 (Interim Report) (C) ANPP-31007, dated October 30, 1984 (Time Extension)
Dear Sir:
The NRC was notified of a potentially reportable deficiency in i Reference (A), an Interim Report was transmitted by Reference (B), and a Time Extension was requested by Reference (C). At that time, it was estimated that a Pinal Report would be available by November 16, 1984 Due to the extensive inve's tigation and evaluation required, it is now expected that this information will be finalized by November 29, 1984, at which time a complete report will be submitted. There is no new information or change to the Interim Report at this time. f Very truly.yours,
. OJLA_ A l E. E. Van Brunt, Jr.
APS Vice President Nuclear Production ANPP Project Director EEVB/TRB/nj cc: See Page Two I 94//2 m / th/h W V/e yi vvvv' f 19 %. l f
V/NOUML
' ' CI I .' ;, ,
Arizona Nuclear Power Project ..
. P.O. box 52034 e PHOENIX, ARI2oNA 85072-2034 1
~h ,f l . 9 November 28,'1984 Ufd .
ANPP-31253-TDS/TRB U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, California- 94596-5368 Attention: Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects
Subject:
O lie 2E de Al $.EsrJeppyrJ; W $ M Q A 50.55(e) Potentially Reportable Deficiency Relating To Fire l 4 Dampers Close Inconsistently. File: 84-019-026; D.4.33.2
Reference:
A) Telephone Conversation between J. Ball and T. Bradish on August 22, 1984 B) ANPP-30569, dated September 19, 1984.(Interim Report) C) ANPP-31007, dated October 30, 1984 (Time Extension) D) ANPP-31162, dated November 16, 1984 (Time Extension)
Dear Sir:
The NRC was notified of a potentially reportable deficiency in Reference (A), an Interim Report was transmitted by Reference (B), and Time Extensions were requested by References (C) and (D). At.that time, it was estimated that a Final Report would be available by November 29, 1984. Due to the extensive investigation and evaluation required, it is now expected that this information will be finalized by December 12,1984, at which time a complete report will be submitted. There is no new information or change to the Interim Report at this time. Very truly yours, w k E. E. Van Brunt, Jr.
- APS Vice President Nuclear Production ANPP Project Director EEVB/TRB/nj cc: See Page Two l
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Arizona Nuclear Power Project i5 f p ,,,,, e.o. sox s2ou . phoenix, Am2ONA 850M-20M " ' December 8, 1984 f+- , ANPP-31384-TDS/TRB I U. S. Nuclear Regulatory Commission Region V 1450 Maria Lane - Suite 210 Walnut Creek, California 94596-5368 i Attention: Mr. D. F. Kirsch, Acting Director Division of Reactor Safety and Projects
Subject:
Final Report - DER 84-56 A 50.55(e) Reportable Condition Relating To Fire Dampers Close Inconsistently.
-File: 84-019-026; D.4.33.2
Reference:
A) Telephone Conversation between J. Ball and T. Bradish on August 22, 1984 B) ANPP-30569, dated September 19,1984 (Interim Report) C) ANPP-31007, dated October 30,1984 (Time Extension) D) ANPP-31162, dated November 16, 1984 (Time Extension) E) ANPP-31253, dated November 28, 1984 (Time. Extension)
Dear Sir:
Attached is our final written report of the Reportable Deficiency under 10CFR50.55(e) referenced above.
. Very Truly Yours,
\
CLLA- ntL E.E. Van Brunt, Jr. APS Vice President Nuclear Production ANPP Project Director EEVB/RB/nj Attachment ec: ' See Page Two OL;11 'i f) M A < eo
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l Mr. D. F. ' Kirsch DER-84-56 Page Two-cc:- . Richard DeYoung,' Director Office of Inspection and Enforcement U. S. Nuclear. Regulatory Commission Washington,~ D. C. ' 20555. T. G. Woods, Jr. D. B. Karner W. E. Ide D. B. Fasnacht A. C. Rogers L. A. Souza D. E. Fowler
-T..D. Shriver C. N. Russo B. S. Kaplan J. R. Bynum J. M. Allen A. C. Gehr
'W. J. Stubblefield W. G. Bingham R. L.'Patterson R. W. Welcher ,
H. D. Foster D. R. Hawkinson-R. P. Zimmerman L. Clyde-M. Matt-T. J. Bloom-D. N. Stover J. D. Houchen J. E. Kirby. D. Canady Records Center - Institute of Nuclear Power Operations 1100 Circle 75 Parkway, Sui _te 1500 l Atlanta, GA 30339-r J
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.4 FINAL REPORT - DER 84-56 DEFICIENCY EVALUATION.50.55(e)
ARIZONA PUBLIC SERVICE COMPANY (APS) PVNGS UNITS 1, 2, 3 I.- _ Description of Deficiency l'
-In the presence of a fire, and under normal operating ' air flow conditions, all fire dampers must close in order to insure the
!- integrity of fire rated walls in which fire dampers 'are located. The i , closure of dampers.is accomplished via the melting of a fusible link - on the damper in. the presence of a fire.' Some dampers close~on the l i ' detection of -smoke from the incipient stages of a fire after the fire control (ETL) onpanel transaits a signal which melts an electrothermal link t- the damper. SFR 1HJ-153 and NCRs SM-4579 and SM-4580 document the various dampers to close fully under normal operating air flow conditions. All dampers closed' fully under "no flow" conditions. These dampers' are macufactured by Ruskin Manufacturing Company an supplied by The Waldinger Corporation ~ (7WC). ! Evaluation L The dampers that failed to close are Ruskin Model N1BD23 Though the . differ, the. prise difference between dampers is the position. dampers, 'and those mounted in' a wall'are defined as dampers. . The primary difference in. operation of the' two types of , dampers is that the vertical dampers are spring loaded andeclosur [ gravity assisted, while the -horizontal dampers do not have the . is l gravity assist due to the installation position of the dampers . 1 A. Vertical Dampers 4 j i HJB-M08, during testing. Mll, MIS and HJN-M102 as having fa , All vertical ~ dampers were later retested (in the presence of TWC and Ruskin representatives)' and it was determined i-that in all cases, except for damper HJB-M11, the ETL conduits . were interfering with the closing of the damper. The root cause a E
+
of this ' condition . appears to be in the conduit design of the-ETLs. , ' After the link melts, the conduit " holds up" the ETL so- l i
. that the ETL interferes with the closing of the damper.For -
- August-24,'1984).
kinked and required replacement '(Ref.' letter F-1 ,
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. FinM. Report :
D5t 84-56 ' -
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, L.Page Two B. l Horizontal Dampers'
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Since the' vertical despers are mounted'in the wall, gravity ; 4
+
assists their closing.' The closing of the horizontal dampers is not-assir,ted in this way. The same negator springs are used in both types of daspers.. This spring is sufficient to close the f gravity assisted vertical dampers, but not the horizontal . l dampers. Further testing of the horizontal d' aspers in Ruskin's facility has shown that use of:n stronger negator spring.and a 1-modified locking mechanism will cause dampers to close during , a design flow conditions. The results'of_these tests are documented in'Ruskin Test Report,' Bechtel'Iag no. j 13-10407-MM598-3018.. A complete list of affected horizontal dampers 'is supplied as Attachment.1. . f j The root cause of this condition'is that the springs;in these b dampers were not designed _to close in horizontal. duct mounted installations under air flow conditions. >
; II. Analysis of Safety Implications "
'I i l i The failure of the fire dampers which are installed in ductwork to j- fully close when required will derate the fire rating,of the fire , i l rated wall or floor in which tihey are located.- ' This may lead to a l; violaton of separation criteria' where two-trains of a system are I separated by a fire rated wall in which a damper is_ located. i Therefore, this condition'is evaluated as reportable under 10CFR50.55(e); since, if this condition were to remain uncorrected, l it could pose a substantial safety hazard.- I, _ s Ruskin has already reported this' condition underl10CFR Part 21. 4 Therefore, required.- determination of 10CFR-Part 21 reportability is not
).
j III.. Corre~ctive Action A. Vertical.Despers.
+
- ~
Fire damper HJB-M11 has been reworked so that.it now closes.under design flow conditions. ) . Thishas been accomplished by replacing the kinked negator' spring (via Startup Work Authorization number - [ 24939). This damper. and all other . vertical fire dampers will-l have their ETL conduits removed so that.th'e dampers will close j under design flow conditions. This work wil1~be accomplished'via
-Design Change Package (DCP) 10M, 2SM, 3CM-FP-131. Unit 1 will be L
completed prior.to entry into Mode 6. Unita 2 and 3 will be- !' - completed prior to issuance of an ' operating-license. I I pr, -w, ,-fa.-- +- - , , - . ,==r s- * * ,we- ,ir-+=*+ ee---ee-i-e,=-+---s-e,eevis.+w-e o--=v
Final Report DER 84-56 Page Three B. Horizontal Dampers All horizontal fire dampers will have new negator springs and -
. modified locking mechanisms installed in order to insure that the dampers will close during design flow conditior.s. In addition, horizontal fire dampers with ETLa will also have their conduits removed. The changes will be accomplished in each unit under DCPs 10M, 2SM, 3CM-HA-040; HF-021; HJ-042; HR-007; HT-017. The scheduled completion dates are the same as those listed above.
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I p, 4 NUCLEAR REGULATORY COMMISSION
- l i ;; namon v f
1* . 8, g 1450 MARIA LANE,sulTE 210
% * . . . * ,d VWALNUT CREEK, CALIFORNIA 94806
[ MAR 221985
.. Docket Nos. 50-528, 50 529 and 50-530^
Arizona Public Service Company P. O. Box 21666 Phoenix, Arizona 85036 Attention: Mr. E. E. Van Brunt Jr. Vice President, Nuclear Production Gentlemen:
Subject:
NRC Inspection of Palo Verde Units 1, 2, and 3. This refers to the inspection conducted by Messrs. G. H. Hernandez and J. R. Ball of this office during the period December 1, 1984 - January 31, 1985, of activities authorized by KRC License Number NPF-34 and Construction Permit Numbers CPPR 142 and 143, and to the discussion of their findings with you and members of your staff at the conclusion of the inspection. Based on the results of this inspection, it appears that one of your activities was not conducted in full compliance with NRC requirements, as set forth in the Notice of Violation, enclosed herewith as Appendix A. This violation concerns an apparent failure of the HVAC contractor to comply with welding requirements as specified by approved drawing documents. The apparent failure of the welds to comply with procedural and code requirements brings into question whether sufficient contractor management and oversight controls existed at the HVAC contractor during the period the components were fabricated. Please provide your response to the Notice of Violation, including any additional steps or corrective action that you have ; taken to assure that HVAC contractor welding inspectors were properly 1 qualified, and to assure that other components fabricated during this period complied with design requirements. Your response to this Notice is to be submitted in accordance with the l provisions of 10 CFR 2.201 as stated in Appendix A, Notice of Violation. ;
\
In accordance with 10 CFR 2.790(a), a copy of this letter and the enclosure ' will be placed in the NRC Public Document Room. The responses directed by this' letter and the accompanying Notice are not subject to the clearance procedures of the Office of Managescat and Budget as required by the Paperwork Reduction Act of 1980, PL 96-511. 57- Q\d,I,I(lY! i y g4Of,L ____2 E_ _ -
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. Arizona Public Service Company 3 Should you have any questions concerning this inspection, we will be pleased to discuss them with you.
- ff -Sincerely,
; p Acting Director
~~
D.F. Kirsch,j Division of Reactor Safety and Projects
Enclosure:
A. Appendix A, Notice of Violation B. Inspection Report Nos: 50-528/85-01 50-529/85-01 50-530/85-01 cc w/ enclosure: J. R. Bynum, APS S. R. Frost, APS T. D. Shriver, APS W. E. Ide, /JS C. N. Russo, APS J. Morrison L. Bernabei, GAP A. C. Gehr, Esq. Snell & Wilmer bec: RSB/ Document Control Desk (RIDS) Resident Inspector Mr. Martin RV andtbdh M Mb GH as aller AChaffee AJol son DKirsch 3 /85 3/ry/85 3f)/85 3//f /85 3/p /85 3/t1 /85
-(.) ') .. , APPENDIX A N0fiCE OF VIOLATION Arizona Public Service Company ,' Docket Nos. 50-528 and 50-529 e g,P. O. Box 21666 .
NRC License No. PM-34 and a y?hoenix, Arizona,85036 Construction Permit No. 142
. x -
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'As a result of the inspection conducted on December 1, 1984 - January 31, 1985, and in accordance with NRC Enforcement Policy, 10 CFR Part 2, Appendix C, the following violation was identified:
1 10 CFR 50, Appendir'B, Criterion.V as implemented Ly Section 17 of the l FSAR, states in part that, " Activities affecting quality shall be prescribed by documented instructions, procedures or drawings... and shall be accomplished in accordance with these instructions, procedures or drawings." CTI-Nuclear Drawing No.10407-M721B-582-4, Section 11.1, Sketch No. 31254, Revision K, calls out (in Detail No. 5) full penetration welds on stiffener connections located on the Control Room Essential Air Handling Units, and, in Section No. AA, calls for full penetration welds on the plate to plate welds of the same units. Contrary to the above,'the stiffener connections on the Air Handling Units for Units Nos. I and 2, did not have full penetration welds, as required. Additionally, prtions of the required full penetration plate-to plate welds on Air Handling Unit No. 2-M-HJA-F04 (Unit No. 2) were not fully welded in some areas. The plate-to plate welds on 2-M-HJA-F04 were not fully welded for a total of 6 inches on the top north side and 4 inches or. the top south side of the unit. All welding identified above was inspected and accepted by Quality Control Inspectors of the Waldinger Corporation (TWC) for Unit No.1, on October 12, 1982, and for Unit No. 2, on or before October 3, 1979. This is a Severity Level IV Violation (Supplement II). *- Pursuant to the provisions of 10 CFR 2.201,' Arizona Public Service Cotpany, [ is hereby required to submit to this office within thirty days of the date of this Notice, a written statement of explanation in reply, including: (1) the corrective steps which have been taken and the results achieved: (2) corrective steps which will be taken to avoid further items of noncompliance; and (3) the date when full compliance vill be achieved. Consideration may be given to extending your response time for .3ood cause shown. - gj t%R 221985 Dated LVF. Miller,- CEidi Reactor Projects Section No. 2
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,, U. S. NUCLEAR REGULATORY COMMISSION 12GION V
' Report Nos: 50-528/85-01,50-529/85-01,50-530/85-01 I Docket Nos: 50-528, 50-529, 50-530 - <
~~
7I.icense No: NPF-34
',A i
donstructionPermitNos: CPPR-142 and 143 Licensee: Arizona Public Service Company P. O. Box 21666 Phoenix, AZ. 85036
' Facility Name: Palo Verde Nuclear Generating Station Units 1,2,3 i _ Inspection Conducted: Dec 1, 84 - January 31, 1985 Inspectors: ,rh b/kh Date Signed G. BG erna }elyr Resident Inspector j f I rn J. YI Ball, ReMoent Inspector J< /6([
Date Signed l i Approved By: Y/VY L.U. Miller,(phief Date Signed ' Reactor Projects Section No. 2 Summary: Inspection from December 1,1984 - January 31, 1985 (Report Nos. 50-528/85-01, 50-529/85-01, and 50-530/85-01) l Areas Inspected: A routine, onsite inspection by the Construction Resident Inspectors of activities related to the following: Unit One: Review and close out of licensee-issued Deficiency Evaluation Reports (DERs), NRC open items (Notice of Violation 50-528/84-38-04, Notice of Deviation 50-529/84-08-04, and Unresolved Item 50-529/84-08-03),NRC Information Notice 84-30, and an allegation related to Unit 1 Reactor Vessel studs. Unit Two: Examination of the Reactor Vessel installation and concrete, and g containment steel liner records.
.; Unit Three: Observation of work related to electrical cable pulling and
~ installation.
Independent inspection was also performed on Units 1 and 2. Q. .
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2-
. The inspection involved 374 inspector hours on site by two NRC Resident
. . Inspectors.
', , , ..Results: In the areas inspected, one violation was identified. 'The 7&41censee failed to assure that welding on HVAC units complied -~with drawing
~
,, ..,. requirements (see paragraph No. 8). _
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a 'h) ) DETAILS I".
- 1. Persons Contacted:
- a. Arizona Public Service Company (APS) i
*E. E. Van Brunt, Vice President, Nuclear Production e .J. R.'Bynum, Plant Manager
' e'
.*W. E. Ide, Corporate Quality, Assurance Manager --
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*D. B. Fasnacht, Nuclear Construction Manager
.W. F. Quinn, Licensing Manager
*C. N. Russo,' Quality Assurance Audits / Monitoring Manager R. J. Burgess, Field Engineering Supervisor E. C. Sterling, Configuration Control Supervisor l R. J. Kimmel, Transition Engineer R. L. Hamilton, Quality Monitoring Supervisor ',
*T. S. Bloom, Licensing Engineer W. D. Roman, Lead Operations Engineer W. L. Bichlmeir, Operations Engineer A. T. Ramey, Quality System Supervisor N. C. Hallas, Quality Engineer
*J. Y. Morita, Licensing Engineer
*R. J. Kimmel, Transition Representative
*W. W. Montefour, Quality Assurance Engineer
- b. Bechtel Power Corporation (Bechtel)
*W. J. Stubblefield, Project Manager S. M. Nickell, Project Superintendent J. Black, Chief Resident Engineer R. Randel, Startup/ Operations Resident Engineer
.D. Freeland, Pipe and Pipe Support Resident Engineer
*D. R. Hawkinson, Project Quality Assurance Manager
*H. D. Foster, Project Quality Control Engineer
*T. L. Horst, Project Field Engineer 4
R. H. Roehn, Lead Quality Assurance Engineer
.
- Denotes personnel attending the NRC Exit Management Meeting conducted j on February 1, 1985. <
l , The inspectors also talked with other licensee and contractor personnel ; during the course of the inspection. '
- 2. Plant Status l
- a. Unit One:
On December 31, 1984, Unit No. I was granted an operating license. Fuel ~ loading started'on January 7, 1985, and completed on January 11, 1985. At the end of the inspection the Unit was in Mode 5 while preparations were made to enter Mode 4.
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,, Unit ho:
, ' Unit 2 has a scheduled fuel load date of December, 1985. Construction completion of Unit 2 was estimated at 99.5% by the , -licensee. Unit Three: ,,
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All major components and equipment have been installed. The major l activity ongoing is the installation of electrical cable and *
. instrumentation terminations, which is estimated at 80% complete.
- Unit 3 has a scheduled fuel load date of March, 1987. '
4 -
- Construction completion of Unit 3 was estimated at 94.6% by the' l licensee.. '
- 3. Followup on NRC Notice of Violation - Unit 1 (Closed) Notice of Violation No. 50-528/84-38/04 " Failure to Comply With Trainina Requirements for Resident Engineers".
-The inspector had previously identified that 30 out of 160 Bechtel i
~ project engineers did not have training records to substantiate compliance with training procedural requirements. The licensee's - investigation determined that, based.on interviews conducted with resident engineers, all but two of the engineers had previous ' experience on other. Bechtel projects. All engineers had sufficient on-the-job familiarity with their work assignments for the inspector to conclude.that the training had been completed, though not formally documented. Further, the licensee has. revised engineering training
- procedures to ensure that any individual who has not completed the requisite training within 30 days is inmediately identified to engineering management. The licensee attributed this viclation to an .I 1
omission in the job site Quality Assurance Schedule wherein~ resident engineering was not soecifically identified in the audit schedule. The licensee has now modified the audit schedule to include resident engineering training, and other aspects of resident engineering which j had been previously omitted. 4 Based on the licensee's corrective action as indicated above and the inspector's examination of the licensee's stated actions,. this
-violation is closed.
F
. 4. Followup on NRC-Notice of Deviation-- Unit 2 F (Closed) Deviation No. 50-529/84-08/04 " Failure to Qualify Sealant
- for Use as a Gasketina Material on Heatina, Ventilatina,and Air
! ' Conditioning (HVAC) Ducts. i The licensee's response to the Notice of Deviation was provided to the NRC by letter dated May 9, 1984. The licensee's response outlined the ) corrective measures-taken to prevent recurrence of the discrepancy, and -l 1 l l
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'the date when all action taken by the licensee was completed.
Additionally, on May 10, 1984,- the licensee issued a potential construction deficiency report [Deficienc
- 84-37).in accordance with 10 CFR 50.55(e)y onEvaluationthe use of Report unauthorized (DER) No.
sealants which were not environmentally qualified. .
- ligl ' Based.on the inspector's examinati'on of the licensee's corrective i W"[F a'ctions as related to DER No. 84-37 and the inspector's findings, as l
{g.w discussed in paragraph 7c of this-report, this item is closed. 5.- Followup on NRC Identified Unresolved Items - Unit 2 . (Closed) Unresolved Ites No. ~ 50-529/84-08-03 "Use of-Duct Sealant on a Gasketed Heatina, Vectilatina and Air Conditioning (HVAC) Duct Joints" Without Qualifying the Sealant for Harsh Environments In NRC Inspection Report No. 50-529/84-08, the inspector identified the use of unauthorized sealants in IVAC ducts, including the metal to gasket seal. This NRC inspection report also contained a Notice of , Deviation on the failure of the licensee to environmentally qualify sealants in accordance with FSAR commitments. , the licensee Subsequent reported to theto NRC theaissuance of the NRC potential construction inspection report,[ Deficiency deficiency Evaluation Report (DER) No. 84-37] in accordance with the requirements i oi 10 CFR 50.55(e). This report addressed the use of unauthorized ealants which were not environmentally qualified. Based on the inspector's examination of'the licensee's corrective actions as related to DER No. 84-37,.and the inspector's findings, as 1 discussed in paragraph 7c of this report, this ites is closed.
- 6. Licensee Action on NRC Information Notice 84 Units 1, 2 and 3 (Closed) Information Notice No. 84-30, " Potential Deficiencies Elated to the Construction of Safety-Related HVAC-Units by the Bahnson Company" Discussion with licensee personnel indicated they had responded to this NRC Information Notice by letter' dated July 31, 1984, wherein, they i i
indicated that six Bahnson units were received on site, that two HVAC units were currently installed in Unit 2, and four HVAC units were installed in Unit 3. Due to the potential welding deficiencies described'in the Information Notice, the licensee instituted a special ; program to examine the six Bahnson units. The licensee's special ; program was in progress ~at the time of.the inspection. I
.? To assure that the other BVAC units installed in Units 1 and 2 did not 1 have'similar discrepancies,.the inspector examined four HVAC units in Unit 1, and two EVAC units in Unit 2. These were manufactured by CTI-Nuclear (Bahnson Company was a subcontractor to CTI-Nuclear)., The inspector found's number of welding discrepancies with these units.
Subsequent ~ investigation determined _that the HVAC units were shipped in
, sections and then welded on site by the Waldinger Company (TWC). The
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" - welding discrepancies identified with these units are discussed further '
in paragraph No. 8 of this 'eport. r l
~ l Based on the licensee's program for examining the Bahnson manufactured EVAC units, the inspector concluded that the licensee's actions were appropriate for addressing the deficiencies identified in the NRC l J -Information Notice'on Bahnson manufactured HVAC units. l
- 4b -
I { This item is closed. ,
- ~
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' ' ' 7.
Licensee Action on 10 CFR 50.55(e) Construction Evaluation Reports ' (DERs) - Units 1, 2 and 3 . The following 50.55(e) reports were reviewed by the inspector for. reportability, and to determine the thoroughness of the licensee's corrective action.
- a. (Closed) DER No. 84-13. "Heatina, Ventilatina and Air
'Conditionina (HVAC) Acceptance Criteria" On March 13, 1984,.the licensee reported a potential construction deficiency, in accordance with the requirements of 10 CFR 50.55(e), wherein a licensee examination of The Waldinger
- Corporation's (TWC) installed HVAC ducts ' determined that, due to insufficient detail on design drawings, and the incorrect i
interpretation of the drawings by TWC,-a number of HVAC ducts' supports were found to not comply with the seismic acceptance criteria. On December 12, 1984, the licensee submitted their final report on this deficiency, describing the safety implications and their corrective actions.. The inspector reviewed the documentation related to this identified discrepancy, and determined that the licensee had initiated a walkdown of all accessible safety-related, important to safety, and potentially hazardous condition duct supports 3 (non-safety-related over safety-related duct supports). The , non-accessible duct supports were defined as those supports that could not be inspected due to the covering of fire proofing material. However, the licensee's inspection results concluded that, because of the small percentage (2.8%) of duct supports found to require-rework, a high confidence existed that the non-inspected duct supports.would perform as intended. ' Additionally, the type of rework performed tended to be very minor in nature for the rework supports, l m Subsequent to this finding,.*.he licensee revised all design I drawings to ensure that sufficient details existed to prevent timproper installation and misinterpretation of the drawings by the } installers. The inspector reviewed the documentation related'to this deficiency, the revised drawings, and examined a number of the G
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o o s revorked duct supports. The inspector found that the licensee's action appeared to properly address the safety concern, and i sufficient action had been taken to prevent recurrence of the discrepancy. . The licensee is following this ites for Units 2 and 3,.'through Design Change Package Nos. 2SM-HF-014 and 3SM-HF-014,
~
respectively. D/:;
~ This item is closed.
-~
- m. .
~
- %; - b. (Closed) MR No. 31, " Unsealed Piping Penetrations in the Main Steam Support Structure (MSSS)".
On May 17,:1984, the~ licensee reported _a potential construction deficiency, wherein, contrary to design requirements, 14 piping floor penetrations, in the Unit No. I Main Steam Support Structure (MSSS) were found to be unsealed. _On July 12, 1984, the licensee submitted their final report which _ described the deficiency, the safety implications, and their corrective actions. The inspector reviewed the documentation related to this 1
; identified discrepancy. It indicated that unsealed floor penetrations at elevation 100 feet could expose the Auxiliary Feedwater (AW) pumps to environmental conditions (flooding) for which the pumps had not been qualified, and therefore the-operability of the pumps could not be assured.
3 At the end of the inspection, only four of the 14 penetrations had not been sealed. Work on these four penetrations had not been completed due to the unavailability of sealing materisl. The-licensee has stated that work on these four penetrations will be completed prior to March 1, 1985. Additionally, the licensee has ; ! conducted n walkdown c.f other below grade penetrations to assure 4 that a generic condition does not exist. No other penetrations were found to have a flooding potential for the AFW pumps. The licensee has issued Design Change Package Nos. 2SA-ZM-011 and i 3CA-ZM-011 to insure that the required seals are installed in Unit . - Nos. 2 and 3. ' Based on the licensee's actions with respect to the sealing of the i ten floor penetrations, and the other corrective actions, as
- stated above, this item is closed. However, the inspector will
~ follow the licensee's program for the sealing of the remaining four penetrations to assure compliance with'the licensee's stated
- actions. . (0/I 50-528/85-01-01) y
,i This. item is closed.
se .
- c. (0 pen) DER No. 84-37, " Unqualified Heating, Ventilating and Air Conditioning (HVAC) Sealant"- ,
l
- On May.10, 1984, the licensee reported a potential construction deficiency, wherein unqualified sealants were found to have been I
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used by the EVAC contractor to reduce leakage in EVAC ducts. The licensee identified 21 different types of sealants which were available for use by the EVAC contractor, and over one-hundred locations in Units 1, 2, and 3 where unauthorized sealants were used.
-The licensee submitted their~ final report on December 17, 1984',
. t
' describing the deficiency, the safety implications,.and their
. 3r-
{ corrective actions. -
' . i
.The inspector reviewed.the documentation related to this
' 1 identified discrepancy, and determined that the licensee has submitted the 21 sealants to an environmental qualification . program consisting 'of aging, elasticity, leazage tests, and l radiation exposure analysis. 'A testing laboratory was in the process of qualifying all 21 scalants to a 40 year life. All sealants had been previously qualified to a 5 year life. This item will remain open'until the inspector can review the 4 laboratory report on the qualification of.the' sealants for 40 years.
- d. (Closed) DER No. 84-56, " Fire Dampers Fail to Close Consistently" On May 10,.1984, the licensee reported a potential construction deficiency wherein a number of' vertically and horizontally mounted fire dampers would not fully close in accordance with design requirements.
On December 8, 1984, the licensee submitted their final report, describing the deficiency, the safety implications and their corrective actions. The inspector reviewed the documentation related to the identified discrepancy. It indicated that the two primary causes for the ; failures were the interference of the electrothermal link (ETL) conduit for horizontal and vertical dampers,'and a weak " negator" spring for horizontal dampers. The electrothermal link is the , fusible link in the damper which melts upon 'a signal from the Fire Control Panel. The licensee issued Design Change Packages to modify the dampers. These included removing the ETL conduits from horizontal and vertical dampers, and the addition of a stronger i negator spring for the horizontal dampers. On December 20, 1984, the licensee tested the dampers, but one damper failed to close as required. At the end of the inspection, the licensee had l corrected the problem with the damper (interference with the ETL conduit), and planned to retest the damper during the first week of February. . Based on the licensee's corrective actions as stated above,'this item is closed.. 1
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,, e. (Closed) DER No. 84-93 "Missina Seismic Rails in Control Panel
't No. 305" On November 9, 1984, the licens'ee reported s potential construction deficier.ty, wherein, contrary to design requirements, the CPC/CEAC operator modules on main control panel No. 305 were
- 3. ., ,
found to have no support rails installed. fy'
'^
A Ci December 8, 1984, the licensee submitted their final report E- which described the deficiency, the safety implications and their corrective actions. * , The inspector reviewed the documentation related to the identified ' discrepancy and determined that the panel vendor
-(Consip-Customline) failed to' incorporate the required support
, rails in panel No. 305 for Units 1, 2 and 3. All other panels had
'the required support rails.: On December 19, 1984, the inspector examined panel No. B05 in Unit No. I and found that the support rails were installed, as stated by the licensee in their final report on this subject, dated December 8, 1984. The licensee has
' issued Design Change Package Nos.-2SJ-RM-800 and 3CJ-RM-800 to install the support rails in Unit Nos. 2 and 3.
l This item is closed.
- f. -(Closed) DER No. 84-99, " Improper Mountina of Regenerative Heat
, Exchanter" On November 30, 1984, the licensee reported a potential construction deficiency, wherein the upper support bracket bolt i holes for the Regenerative Heat Exchanger had been modified such that the design thermal expansion of the heat exchanger had been precluded. 'This condition was determined by the licensee to possibly induce rtresses beyond design allowables.
I The-licensee submitted their final report on December 14, 1984, which described the deficiency, the safety implications, and their corrective actions. 1 The inspector reviewed the documentation related to the identified l discrepancy, and determined that on December .10,1984, the mounting brackets had been reworked to comply with design requirements. On December 20, 1984, the inspector verified the licensee's corrective actions. The inspector determined that this , condition was unique to the Unit 1 Regenerative Heat Exchanger j upper mounting brackets. l'
-Based'on the licensee's actions as described above, this item is L closed.-
[ :3 . (Closed) DER No. 103, " Diesel Generator Buildina Roof Hatches". On December 13,"1984, the licensee reported a potential construction deficiency, wherein Diesel Generator Building roof 4 L.
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' hatches ~were determined to have the potential for lifting off and possibly damaging safety-related equipment during postulated high winds or tornados.
The licensee submitted their final report on December 14, 1984, describing the deficiency, the safety implications, and their 1-n -. corrective actions. 2Q.9- __ 4
/%- Discussions with licensee representatives determined that due to lf@
' ~the heavy weight of the roof hatch covers (approximately 11,000 pounds each), the original engineering design omitted the 1
consideration of the roof hatches lifting during high winds and tornado conditions. ' Subsequent calculations indicated the ! possibility exists that the roof hatches could lift during
. postulated conditions. The inspector reviewed the documentation related to the identified discrepancy, and determined that on Decenber 20, 1934, the roof hatches were provided with restraints to prevent uplift during postulated situations. The inspector examined the welding, bolting, and the configuration of the
- restraints,~ and verified conformance with the design package. The licensee has issued Design Change Package Nos. 2CC-ZG-800 and 3CC-ZG-800 to install the restraints in Unit Nos. 2 and 3.
Based on the licensee's actions as stated above, this item is , closed.
- 8. Independent Inspection ' Units 1 and 2
- s. During the inspection related to Information Notice 84-30 (see paragraph No. 6), the inspector found that HVAC units installed in Unit Nos. I and 2 did not conform to velding requirements as specified by code and drawing requirements. The inspector found the HVAC units had been shipped in sections and welded together on site by.the HVAC contractor. The HVAC contractor was the
- Waldinger Corporation'(TWC).
' On December 18, 1984, the inspector found that contrary to drawing No. 10407-M721B-582-4, Section 11.1, Sketch 31254, Revision X, and the AWS code, the Unit 1 Control Room Essential Air Handling Units Nos. 1-M-HJA-F04 and'1-M-HJB-F04 had 16 areas where partial
! penetration velds had been installed, instead of the required full penetration welds. The full penetration welds are required at
- stiffener to stiffener connection, the plate-to plate connection ;
and the intersection between these connections. Subsequent to this finding, the licensee issued an Engineering Evaluation ; ! Request (EER) No. 84-HJ-010, to address the identified i discrepancies. On January 3, 1985, the licensee's engineering evaluation determined that based on calculation No. 13-CC-ZJ-086, y- 1the welds could be accepted-as-is, and the welds would perform their intended function.
- On January 29, 1985, the inspector examined the Unit 2 Control Room Essential Air Handling Units Nos. 2-M-HJA-F04'and 2-M-HJB-F04. . The inspector found that for Air Handling Unit No.
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~ . . ~ . , - - . . . - 2-N-HJA-F04, the stiffener to stiffener connections and the l plate-to plate connections beneath the stiffener to stiffener connections did not have full penetration welds as required. The plate-to plate welds were not. fully welded for a total of six inches on the top north side of the unit and four inches on the
. .f,7 top south side of the unit. -Stiffener to stiffener connections on 3 >
Air Handling Unit No. 2-H-HJB-F04 were also found not to have full i penetration welds as required. These welds were inspected and i
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~ accepted by Quality Control Inspectors of the Waldinger Corporation (TWC) for Unit I on October 12, 1982, and for Unit 2, on or before October 3, 1979.
The inspector did not examine the four Air Handling Units in Unit 3 and the other two Air Handling Units in Unit 2 because these ' units were manufactured by the Bahnson Company and as stated in paragraph 6, the licensee had established a program to identify and correct any deficiencies in these units. Although the licensee had been made aware of the inspector's findings with the Air Handling Units in Unit 1, the licensee failed to promptly ensure that similar discrepancies did not exist
- in the other units, apparently because of a problem in transmitting EER No. 84-HJ-010 to Bechtel. This problem is discussed further in item b.
The failure to assure that welding for safety-related Air Handling Units comply with code and drawing requirements is considered a violation of NRC requirements. (NRC Violation No. 50-528/50-529/85-01-02)
- b. Discussion with licensee personnel determined that, although EER No. 84-BJ-010 indicated similar discrepancies might exist in Unit Nos. 2 and 3, the EER was never transmitted to Bechtel for their resolution. The inspector determined that because the licensee's method of transmitting EERs to Bechtel lacked a positive acknow-ledgement system, the EER coordinator failed to ensure that Bechtel had received the EER and that Bechtel was working on assuring that no similar discrepancies existed in Units 2 and 3.
The licensee stated that the EER procedure would be modified to include a posif.ive acknowledgement system for EERs transmitted to other parties. The inspector will examice changes to the EER procedure during a future inspection to assure that the licensee has complied with their stated intentions. (Follow up Ites No. 50-528/85-01-03)
- 9. Follow-up to Allegation No. RV-85-A-005 - Unit 1 Characterization: The Unit No. 1 Reactor Vessel Head Closure Studs Were Alleged to be Either "Too Soft" or "Too Hard On January 22, 1985, John Staggs, a reporter for the Arizona Republic called the NRC resident inspector's office concerning information ,.
received from an anonymous source, that indicated that eight to twelve
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1 of the Unit 1 Reactor Vessel closure head studs were either "too soft" 1 or "too hard". The reporter stated that he had also called Arizona l Public Service (APS) on this matter and APS was currently investigating this, allegation.
. Implied Safety Significance to Plant Design, Construction, or jgm - Operations:
1 s 5c The failure of the Reactor Vessel ~ closure head studs could result in ) f' . placing the Reactor in an unanalyzed accident condition. Assessment of Safety Significance: The inspector, in order to resolve this allegation examined all drawings, material certifications, NDE records, nonconformance reports.
-and the applicable code requirements related to the Reactor Vessel head closure studs. The inspector found that all fifty-four closure studs ,
met the physical, chemical and hardness requirements, as required by ' the 1971 Edition of the ASME Code Section II and III, with addenda 4 through Winter 1973. , Staff Position The allegation was not substantiated and is closed.
- 10. Electrical Cable Pulling - Unit 3 The inspector observed the pulling of ten 600 volt control cables from ;
the Unit No. 3 Auxiliary Building, to the Control Building Safety . Equipment Status System Cabinet. The cable pull was observed by the l inspector to ascertain compliance with Specificatiou Nos. 13-EM-300 and 301, and WPP/QC1 No. 254.0 requirements. The inspector noted the cable card was properly filled out and quality control inspectors were present throughout the cable pulling process.
]
No violations of NRC requirements were identified.
- 11. Review of Quality Records - Unit 2
- a. Structural Concrete l 1) 'Areae Examined:
The inspector examined the quality records associated with 25 concrete placements for the Unit No. 2 containment building exterior walls and done. This inspection included review of completed construction inspection plans (CIP's) for preplacement, placement and post placement of concrete.to determine if the records reflected work accomplishment consistent with specifications and procedures. The inspector also examined material test records including daily aggregate test reports s'nd certified mill test reports for cement supplied'during the period in which the concrete was placed.
-Compression test results and the records of the analysis of
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- ' ' the standard deviation were reviewed to assure that the test
-coefficient of variation for the particular concrete mix used i .in these placements was within the code requirements.
'. . Additionally the audit records of Engineering Testing Laboratory, the organizatior. that performed this testing, 1_ _
lwere reviewed. "-
- 2) Applicable Specificatio s and Procedures: ,
- n. .
p?%' ~ ' . 'The following is a-listing of specifications and Work Plan 1 Procedures / Quality Control Procedures (WPP/QCI) governing the ! placement of concrete that were reviewed during the course of' ; this inspection: 13-CM 101 -
" Specification for Furnishing and Delivering Concrete."
13 CM 191 -
" Specification for Testing of Concrete ,
Materials." l 13 CM 365 .- " Installation Specification for Forming, , lacing, Finishing and Curing Concrete." WPP/QCI 52.0 " Concrete Preplacement" t WPP/QCI 53.0 " Concrete Placement" WPP/QCI 54.0 " Concrete Post placement" No violations of NRC requirements were identified.
- b. Containment Structural Steel
- 1) Areas Examined:
l The inspector examined the quality records associated with the installation of the Unit 2 containment cylindrical and 4 done liner plate. This inspection included review of i completed construction inspection plans for the 1/4" SA-285 ' Grade A cylindrical and done liner plate and the 1/2" SA-516
- liner penetration plate. Material certifications for 21 of the 168 containment cylindrical liner plates and 5 of the 17 L
penetration plates were examined.
- 2) Applicable Specifications and Procedures:
1 .
, The following is a listing of specifications and procedures
. . governing the installation of containment cylindrical and 1.L; "* '
done liner plate which were reviewed during the course of this inspection. 13 CM 370 " Containment Building ~ Liner Plate System Installation Specification." 1 .
. - - . . nn . - , -_- - ~.
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' WPP/QCI 61.0 -
" Containment Cylindrical Liner Plate
' Installation." i WPP/QCI 61.2 -
" Containment Liner Plate Installation (Dome)." l
,. I pi * ; ,- 3) Findinas:
.4
- -WN- The inspector determined that the licensee had not prepared a
, summary sheet of inspections performed on the containment cylindrical liner plate, or inspections performed on containment liner penetration plates. The licensee was, however, able to produce supporting documentation which indicated that all required inspections had been performed.
The licensee committed to prepare the summaries as required. ' The inspector will review the completed summaries as a part
.of a future inspection (Follow up Item No. 50-529/85-01-04).
No violations of MRC requirements were identified.
- 12. Review of Quality Records - Unit-2:
Reactor Vessel Installation The inspector teviewed the pertinent records related to the Unit No. 2 i Reactor Vessel handling, protection, installation and inspection activities. The inspector assured that quality records indicated that
.the Reactor Vessel was installed in accordance with specially prepared
- construction inspectior. plans, that access was controlled to the reactor ve sel, the required cleanliness was maintained and protective devices were installed at all vessel opening.
, No violations of NRC requirements were identified. l 13. Inspection Tour of Site: f l i Weekly, the inspector and licensee representatives toured the site to observe general housekeeping conditions., care and preservation of equipment, handling of components, tagging and identification of material. No violations of NRC requirements were identified.
- 14. Manazement Meetina:
i - On February 1, 1985, the inspectors met with the licensee and Eechtel
- representatives identified in Paragraph No. 1. The scope of the inspection, the observations, and the findings of the inspectors were discussed. The licensee acknowledged the concerns, and the apparent i violation of NRC requirements as identified in paragraph No. 8 of this report.
i
I 4 a 1 WASHINCTON PUBLIC TELEPHONE CALL PR PART 21 REPORT:
} POWER SUPPLT LICENSEE ON 03/11/ 5 HAS INFORMED THE( TITUS PRdDUCTS OF RICHARDSON, LIAWUPTEEAS PER MC 2512 1 WMP-3 LICENSEE TMA: muzi. rus. 272 CRILL CONSTRUCTION DN S0-508 TENSION WIRES FOR DAMPERS IN HVAC SYSTEMS COME OUT OP SUMES. PORWAAD CUIDE CLIPS AND CAUSE TME DAMPER BLADES TO SMUT OR 'PART 21 REPORT 70 lett l
REMAIN CLOSED. TITUS WILL REPA!R OR DEVEtAP A POR CENERIC REPLACEMENT UNIT. PART 21 REPORT WILL BE SUBNITTED CONSIDERATION BY TME LICENSEE WITHIN FIVE DAYS. I s {, s. . 4 i . l 1 } l i l\ . 4 ) i 1 . . i l . l ' I r .
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. KIRKPATRICK & LOCKHART
- 1500 ouYER BUILDING ITTTSBURGH, PENNSYLVANIA 15222 ONE BOSTON FLACE BOSTON MA 02108 TELEPHONE (412) 3554500 (617) 9715400
* " 1428 Blut.kEli AVENUE TE12 COP!ER (412) 2812299 M1AMI. FL 331)I 005) 3744112 1900 M STRIET, N W.
TASHINCTON, D.C. 20036 11GTTRS DIRICT DIAL NUMBER CO2) 452 7000 (412) 355-8608 March 15, 1985 fBEEDOM OF INFCF' / *,';,'; Director Office of Administration U.S. Nuclear Regulatory Commission FaIA- 85-1BI Washington, D.C. 20555 Gentlemen: nue3 lIs ss Pursuant to the Freedom of Information Act, 5 U.S.C. S 552, this is to request a copy of any response of the Nuclear Regulatory Commission to a letter sent to the NRC in or around early August 1984 regarding an alleged deficiency with certain model 272 grilles furnished by Titus Products for installation at the Clinton Nuclear Station. To assist you in locating the referenced letter and any NRC response thereto, the letter reporting the alleged deficiency is on the stationery of Ruskin . Division of Philips Industrial Components, Inc. but is apparently signed by Steven Schneider of Titus Products Division. To further assist you, I am enclosing an undated version of the letter reporting the alleged deficiency. In addition to any response to the referenced letter, I would also request any NRC documents specifically discussing the subject matter of the referenced letter. Please forward all such documents together with a statement of costs, which I agree to pay, to me at: Jerry S. McDevitt, Esquire , Kirkpatrick & Lockhart 1500 Oliver Building Pittsburgh, PA 15222 In the event you have any questions about the scope of this request, please call me at (412) 355-8608. Very truly yours, f' Y N C 0iLM 0 f. 0
' Jerry S. McDevitt JSM/ll Enclosure d cn u t t?'n n e1 I Q W V/ / v v v ( I
l Box 129 ggyg 1 Grandview, Missouri 64030 Phone 816 7617476
, o .. . . c .= TELEX 42 4192 J
Factorie Parsons and Great Bend. Kansas; Anaheim, California; Minden, Louisiana; and Bronx, New York
. Representatives in all Maior Cities
- Dir ctor. Office of Inspection and Enforcement United States Nuclear Regulatory Commission Washington, D. C. 10555 Sir In cecordance with requirements of 10 CFR Part 21. Titus Products, located at 990 Security Row, Richardson, Texas 75081, is herewith reporting that we have diccovered a deficiency with products furnished by Titus Products for Nuclear Power Plant application. On March 2,1984, it was determined that the tension wires on Titus Grille (Model 272) would nct remaiti in place when deflection blades were closed. The grilles were gnivanized material supplied to The Waldinger Corporation for installation in the
. , c:ntainrant building at Palo Verde Nuclear Generating Station.
k S1':.ce Palo Verde was the only jobsite for which galvanized grilles were supplied. Titus notified The Waldinger Corporation of this deficiency, which to the best of cur knowledge was reported to the client. Subsequent to the above notification, a jobsite review was coaducted which resulted in the discovery of additional deficiencies. It was determined during this jobsite vicit that the tension wire problem was also apparent on aluminum grilles, thus c:nstituting a total review of all products furnished for other nuclear sites. Further review showed that Model 272 grilles were supplied for two additional jobsites. Attachment I identifies the affected jobsites by location. W2 are currently testing these products to provide an acceptable fix for retention of tension wires. Upon determination of method of rework, Titus will schedule p2rsonnel to complete this activity. In closing, please find' enclosed a copy of the letter describing the situation c:ntained in this letter. which will be sent to each affected site. If further questions should arise, please contact us at once. (
- CONTROL DAMPERS = FIRE DAMPERS
- BACKDRAFT DAMPERS
- LC'UVE%
ev o nv,:.,o., . i., o,,,s.o . ..n. o.v, n . .. v,.csom n nu. c. w c.. .i.o.... w .u e c w . t .~ .. t o,,, sic-. . m.. p . : - __ _ - . ~ _ , _ _ _ _ . . _ _ . _ . _ . . _ . _ _
i kinkted'Stctco Nuclocr R;gulctcry Conniccien Pcg3 2 ( ,
. Thank you for your cooperation.
Si:tcorely.-
.TITUS PRODUCTS DIVISION l 1
l I Steven Schneider
-Prc0ident.
SSacsh
Enclosures:
Attachment.I Motification Form Letter . cc: File NOTE: For further discussions, questions, or concerns on this matter, please contact: l Richard J. Yarges (816) 761-7476 ( O 9 l 1
- l 9
0 1 1 a , I (
ATTACWEENT I'
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. 1. - Washington Public Power Supply System Unit 111
(- F.O. Box 1223 , , Elma. Washington '98541 Atta:. Wayne,Nutt
' Construction Supervisor s
Y
- 2. Falo Verde Nuclear Generating Station Units 1.'11. and III F.O. Box 215 Buckeye. Arizona- 85326 Atta: Robert Strait Project Engineer ,
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- 3. Clinton Nuclear Station
- . The Zack Company
- 4600 12th Street Chicago.-Illinois _ 60650 Atta
- Ralph Usinger Project Engineer ,
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