ML20127C484

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Forwards 850117 Event Rept & Part 21 Rept on Fire Dampers Mfg by Ruskin Mfg.Following Insp Scheduled for mid-Feb, Issuance of IE Notice Will Be Considered
ML20127C484
Person / Time
Site: Beaver Valley, Millstone, Calvert Cliffs, Browns Ferry, 05000000
Issue date: 02/07/1985
From: Holohan G
Office of Nuclear Reactor Regulation
To: Parr O
Office of Nuclear Reactor Regulation
Shared Package
ML20127C488 List:
References
FOIA-85-264, FOIA-85-265 NUDOCS 8502260053
Download: ML20127C484 (20)
v • d • e


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a UNITED STATES NUCLEAR REGULATORY COMMISSION

$ ij WASHING TON, D. C. 20555

% . , , , , .o# FEB 0 ~ .'58. .

MEMORANDUM FOR: Olan Parr, Branch Chief Division of Systems integration Auxiliary Systems Branch Victor Benaraya, Chief Chemical Engineering Branch Division of Engineering FROM: Gary M. Holahan, Chief Operators Reactor Assessment Branch Division of Licensing

SUBJECT:

FIRE DAMPERS FAILURE TO CLOSE 1

Enclosed for your infonnation and use in your licensing reviews, are a January 17, 1985 event report and a Part 21 report on fire dampers manufactured by Ruskin Manufacturing. Following an inspection scheduled for mid-February, I&E will consider the issuance of an IE notice. If you have questions regarding this material, please contact Daniele Tarnoff/0RAR extension 29526.

Y Gary M. olahan, Chief Operators Reactor Assessment Branch Division of Licensing cc: R. Clark V. Rooney C. Stahl S. Burwell T. Kenyon M. Slosson R. Buckley D. Wigginton In:ddcitre K. Jabbour -

D. Mcdonald D. Osborne K. Heitner J. Shea H. Shierling M. Thadani D. Wagner L. Olshan B. Siegel J. Stevens D. Hood E. Reeves A. Bournia V. Nerses J. Wilson P. O'Connor R. Bevan A. DiAgazio J. Stefano J. Norris M. Campagnone H. Nicolaras G. Vissing R. Auluck R. Hernan G. Rivenbark E. Weinkam B. Baer

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t PRIORITY ATTENTION REQUIRED MORNING REPORT - REGION I PRIORITY ATTENTION REQUIRED 1/17/85 3 TO . James Blaha, Director, Program Support and Analysis Staff FROM: Thomas E. Murley. Regional Administrator, Region I .

Licensee / Facility Notification / Subject Description of Items or Events Calvert Cliffs Unit 1 50-317 / 1/1* RRI fax At 4:42 p.m., 1/16 after performing surveillance testing for i check valve operability required by the tech specs the licensee initiated a controlled shutdown of Unit 1 after discovering in-leakage into 811A Safety Injection Tank (SIT) when the High Pressure Safety Injection (HPSI) system is operating. The leakage path was identified to be 38 gpm reverse flow through the SIT discharge check valve. In accordance with their emergency plan the licensee declared an Unusual Event due tg TS required shutdown The HPSI system was declared inoperable due to potential.

insufficient flow rate to the RCS as a result of the identified leakage to the SIT. The licensee plans to proceed to Mode 4 (hot shutdown) to repair the valve. Main Steam Isolation Valve testing will also be performed to demonstrate MSIV reliability as a result of previous repairs to the MSIV hydraulic actuating system.

The licensee made appropriate notifications for the unusual event.

Beaver Valley Unit 1 1/17 RRI fau/

50-334

(/ Reactor Trip and A reactor With trip and the reactor safety at operating injection occurred 95% power, at 3:28top.m.

the breaker V ital1/16.

Safety Injection Bus No. 3 malfunctioned and tripped open. This resulted in the f eedwater regulating valves going f ull open, causing a shrink of steam generator level. When operators took manual control of the feed system and closed the feed-reg valves, a feed flow-steam flow mismatch resulted and a reactor trip occurred. The safety injection resulted from a low steam line pressure signal and pumped approximately 1500 gallons of borated water into the reactor. Due to the safety injection an Unusual Event was de-clared at 6:15 p.m. and was terminated at 6:30 p.m. The breaker was replaced and the reactor restarted at about 7:05 a.m. 1 Resident inspectors are following up on the post-trip review /17. .

Millstone Unit 3 P"'

50-423 Potential Significant Construction The licensee reported that fire dampers manufactured by Air '9 Deficiency Balance and by Ruskin Mfg.

These are non-motor-operated curtain t failed to close during testlng.

1 category I HVAC systems (CDR 85-00-03)ype dampers used in

-o MORNING REPORT - REGION II DATE: January 17, 1985 LICENSEE / FACILITY NOTIFICATION / SUBJECT DESCRIPTION OF ITEM OR EVENT Browns Ferry 1 / HQS Duty Officer, DN: 50-259 1/16 At 2:40 (CST) the reactor. tripped from 100% power on vessel low water. The and RI Telecom main steam line isolation valves closed, HPCI and RCIC initiated, and two SRV's were manually opened for 15-20 seconds to control pressure. One SRV failed to close untti the hand switch was cycJed several times HPCI injected and tripped on high water level. RCIC tripped on overspeed. dause of the reactor trip was initially thought to be a failure of the master feedwater controller but a bench test found no problem with the controller. Region II is monitoring the licensee actions.

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. DERs 50.55(e) REPORTS DER FOLLOW-UP NUMBER TYPE REPORT I STATUS DESCRIPTION 80-02 N/R 82-08 C TUBING SUPPORT CALCULATION ERROR

- SEISMIC CATEGORY 1 INSTRUMENTATION 80-03 N/R 82-07 C SPECIFIED SIZE OF STRUCTURAL STEEL FILLET WELDS 80-04 N/R 82-03 C POSSIBLE DISQUAL. OF ROCKBESTOS CLASS IE CABLE 80-05 NR 82-07 C VISUAL INSPECTION INSTEAD OF PENETRANT INSPECTION OF 2" THRU 4" ASME III, CLASS III PIPE WELDS 80-06 REPORTABLE 82-07 C UNDERSIZE FILLET WELDS - ITT GRINNELL SWAY STRUTS FABRICATED PRIOR TO 11/15/78 80-07 N/R 82-03 C WELD DOCUMENTATION ERROR -

. INTERPASS TEMP - ASME III, CLASS 2, CVN TESTED MATERIAL 80-08 N/R 82-07 C SUITABILITY OF HILTI HDE CONCRETE ANCHORS 80-09 REPORTABLE 82-07 C RUSKIN VERT. FIRE" DAMPERS FAILURE CLOSE - COMPLETELY DUE TO FRAME DISTORTION - ALL UNITS

- PART 21 REPORT 80-10 REPORTABLE 82-08 C FAULTY NAMCO LIMIT SWITCHES -

ALL UNITS PART 21 REPORT !& IEB 79-28 80-11 REPORTABLE 82-12 C FAULTY PRES. SWITCH-CHLORINE

~

DETECT. - PART 21 80-12 N/R 82-08 C NONCODE SPOOL INSTALLED IN 3" CODE LINE-CVCS SYSTEM 80-13 REPORTABLE 82-08 C REINFORCING STEEL DOWELS OM'ITTED FROM CONCRETE PLACEMENT - UNIT 3

! AUX BLDG WALL 70' 80-14 N/R 82-12 C PIPE SUPPORT ANCHOR STRAP l CONFIGURATION Y E -yy 1.

.* 25

Y DERs 50.55(e) REPORTS DER FOLLOW-UP NUMBER TYPE REPORT # STATUS DESCRIPTION C4esrD 84-53 q M VALVE NUTS / STUDS FOUND LOOSE OR

.A/R["'

A/ 35-o ? MISSING cwxD 84-54 REPORTABLE b*k M SUMP ISOLATION VALVE COULD NOT 6h 55-C.5 BE OPENED ELECTRICALLY 84-55 REPORTABLE 84-60 UNQUALIFIED FOXBORO MODULES M .61 INSTALLED IN CLASS QlE CABINETS 84-56

$a d=ble caxv DPEIC~

'/3-O f FIRE DAMPERS NOT CLOSING FULLY DURING PRE-OP TESTS

'84-57 N/R OPEN VALVE FAILED TO CLOSE IN REQUIRED 10 SECONDS 84-58 N/R 84-54 C VALVE FAILED TO OPEN MECHANICALLY 84-59 REPORTABLE 84-60 u nt:'/dl OPEN CABLE INSULATION DAMAGED BY FIRE f,$- C5 STOPS

, 84-60 REPORTABLE 84-60 C TWO INCOMPATIBLE LUBRICANTS USED IN VALVE OPERATORS 84-61 N/R 84-54 OPEN IF LOOP CHARGE VALVE STICKS OPEN AUX. SPRAY SYSTEM MAY FAIL 84-62 OPEN IF HPSI RECEIVES CONCURRE:TILY OPEN/CLOSE SIGNAL, HPSI DOES NOT

! COME ON LINE l 84-63 N/R OPEN SOLENOID VALVE FAIL TO CLOSE

, DURING DEMO TEST

' gfe t.* *

~ri:n

/' ' -

84-64 kg ~OpEN 6 SNUBBERS ARE LOCKED UP

i. . 84-65 N/R OPEN INST. LEAD OUT SHIELD SPLIT l EXPOSING CERAMIC INSULATION 84-66 REPORTABLE OPEN DOWNCOMER FWIV FAILED TO CLOSE UNDER DYNAMIC TEST (TIA) 84-67 N/R OPEN MAGNETIC REED POSITION SWITCH l FAILED TO CHANGE STATE WHEN ENERGIZED 84-68 REPORTABLE 84-60 C CHILLER "A" WOULD NOT RESEQUENCE
ON LINE AFTER LOSS OF POWER

28 .,

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DERs ,

50.55(e) REPORTS DER FOLLOW-UP NUMBER TYPE REPORT # STATUS DESCRIPTION CLOSED 84-100 SPt$~ 480V MCC TERMINAL OVERHEATING p,gq ff g k-(th 84-101 M$T - CONTAINMENT PURGE VALVES FAILED

$[M6g}v Q .-@f a TO OPEN ad.h/ e.6 5'O 20

.NeA O 84-102 , OPE [ ANCHOR DARTING CHECK VALVES HAVE 56 % 5 t00SE SHAFTS 8'H* 3 f,,.thl<f>5-0I g o/& gisp ,,,,.; ,,,ga ,,4 6 o u . / / n , w s y l e g ,, g y 1, N *E h.b 4"$ A Ygt'oser $p IJ L ofgg 3 /# *titi o a o do## 3MfB Of

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Oms.on_of PhJps_andusenes Inc .

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an ew. Messouri 64030 Phone 816 7617476 TELEX 42 4192

. Li Factories: Parsons and Great Bend. Kansas. Anaheim. Cahforraa.

Menden. Louisiana; and Brons. New York Representatsves in all Maior Cotres November 6, 1984 i

Director, Office of Inspection and Enforcement

, U. 5. Nuclear Regulatory Commission Washington, D. C.. 10555 Sir:

f In accordance with the requirements of 10 CFR part 21. Ruskin Manufacturing

  • Company, located at 3900 Dr. Greaves Road, Grandview, Missouri 64030, is herewith rcporting that we have discovered alleficiency with equipment furnished by Ruskin Manufacturing Company for Nucisar Power Plant application.  :-

On August 7,1984 Ruskin received a' letter from The Waldinger Corporation addressing seven (7) fire dampers failure to close under normal duct pressure at  : '

( Palo Verde Nuclear Generating Station.

On August 13, 1984 Ruskin visited the Jobsite to inspect dampers. The results of I the inspection revealed damper condition to exhibit bent blades, . bent blade tracks, rust and zine rich paint on springs.

On August 20, 1984 after Engineering review of inspection results, Ruskin again  !

i visited the jobsite for Engineering review of above referenced damper conditions.  ;

As a result of.this review Ruskin recommended that the blade packages be replaced in the affected fire dampers.

  • On October 30, 1984, Ruskin was notified, tay The Waldinger Corporation, that the new blade packages had been installed and tested. The fire dampers with the newly installed blade packages would still not cycle under normal duct pressur*.

Ruskin Engineering tamediately began to evaluate the probles to deterul'ne the cause of the dampers failure to clou under air flow. Results of this evaluation indicated the test methods originally utilfred to test dampers under flow may not accurately depict actual installed conditions. .

Ruskin fire dampers were tested in accordance with AMCA 500, test figure 5.5, mounted on the face of the test tunnel. Actual installed condition, la ductwork, may not result in proper performance as tested to AMCA. Ruskin, on November 2, cad 51984, performed air flow tests in accordance with AMCA 500 with damper mounted on. face of tunnel as well as with damper mounted in ductwork. The results of this test indiccted that face mounted damper would close at much higher static pressure than the damper which was installed in ductwork; .,

CONTROL DAMPERS

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November 6,1984 U. S. Nuclear Regulatory Comission Page 2 Since no facility exists to properly test dampers under flow that would simulate all field installed conditions, and relationship between face mounted damper and damper Installed in ductwork cannot be accurately calculated, Ruskin recommends that fire dampers supplied with closure springs, which require closure under air flow conditions, be tested to verify proper operation. This condition affects only interlocking blade fire dampers Model 180-21, 180-23 and NIBD-23 supplied with

, closure springs by Ruskin.

Ruskin is currently researching methods to modify fire dampers to ensure closure under air flow.

Attachment I to this letter identifies the affected jobsites by location and the

, number of units supplied to each, i In closing, please find enclosed a copy' of the letter describing the situation contained in this . letter, which will be sent to each affected site.

If further questions should arise, please contact us at once.

Thank you for your cooperation.

Sincerely.

RUSKIN FACTURING DIVISJ

/ /

.j -n - /

Thomas D. Hill President

Enclosures:

Attachment I Notification Form Letter NOTE: For further discussions, questions, or concerns on this matter, please contact:

Richard J. Yarges Ruskin Manufacturing Division (816) 761-7476, I

S , 2 .'gi d ~. % ,.t

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  • e e* * * * * * * * " ' " * ' * *

\ -- -- - - - - - .- - - - - - - - - - - - - - - -

Attachment I Page 1 of 3 Browns Ferry Nuclear Plant Maine Yankee Atomic Power Tennessee Valley Authority Maine Yankee 400 West Summit Hill Drive R.R. 2 Box 3270 Knoxville, Tennessee 27902 Wiscusset, Maine 04578 11 Units 20 Units 1

Sequoyah Nuclear Plant Diablo Canyon Tennessee Valley Authotrty Pacific Gas and Electric See Above 77 Beal St.

64 Units San Francisco, California 94106 19 Units Watts Bar Nuclear Plant Hope Creek Tennessee Valley Authority Bechtel Construction Inc.

See Above P.O. Box 3955 .

. 344 Units .

San Francisco, California 94119 '

893 Units Bellefonte Nuclear Plant Clinton Tennessee Valley Authority Zack Company See Above 4600 W. 12th Place 144 Units Chicago, Illinois 60650 262 Units Yellow Creek Nuclear Plant Midland Tennessee Valley Authority Zack Company See Above See Above 204 Units -

366 Units 1 -

i Palo Verde Nuclear Generating Station LaSalle The Waldinger Corporation Zack Company

P.O. Box 215 See Above Buckeye, Arizona 85326 106 Units 963 Units Turkey Point '

He. H. Zimmer Nuclear Power Station Florida Power and Light Waldinger-Young & Bertke P.O. Box 3088 2601 Bell Avenue Florida City Florida 33034 Des Moines. Iowa 50321 2 Units 5 Units W.P.P.S.S. Unit I Waterford #3 8echtel Power Corporation Loutstana Power and Light -

P.O. Box 650 142 Delaronde St.

Richland, Washington 99352 New Orleans, Loutstana 70174 303 Units 26 Units t

es 6

~ ~ ~ - ~ * - - - - - - -- e w- --n--ww,- , - - - - - - - ,w - ,---,-- - - - - - - -----e-,--w--, _,e-w,,,.- ,, -- ----,n-,---m -- e- - - . --n,-,-,--,,,- , - - - , -n g -,

~

, Attachment I Page 2 of 3 Quad Cities D. C. Cook Zack Company American Electric Power Service Corp.

4600 W. 12th Place  ?.0. Box 16631 Chicago, Illinois 60650 Columbus, Ohio 43216 19 Units 22 Units Morrison Construction Catawba Nuclear P.O. Box 1130 Bahnson Service Hammond, Indiana 46320 P.O. Box 384 4 Units Clover, South Carolina 29710 -

421 Units Perry Nuclear Millstone Robert Irsay Stone and Webster P.O. Box 205 P.O. Box 345 Perry, Ohio 44081 Waterford, CT. 06385 i

520 Units 17 Units Susquehanna Duane Arnold Peabody and Wind Eng. CO. Iowa Electric Light and Power 275 Geiger P.O. Box 351 Philadelphia, PA. 19115 Cedar Rapids, Iowa 52406 95 Units 22 Units

  • Arkansas Nuclear One Byron Nuclear Arkansas Power and Light American Warning & Ventilating P.O. Box 551 1310 Indian Wood Circle -

Little Rock, Arkansas 72203 Maumee, Ohio 43537 144 Units 51 Units Monticello Braidwood Nuclear AZC0 Inc.

American Warning & Ventilating c/o Northern States Power See Above P.O. Bor 655 51 Units Monticello, Minnesota 55362 -

30 Units Comanche Peak Farley Nuclear Texas Utilities Alabama Power P.O. Box 1002 P.O. Box 2641 Glen Rose, Texas Birmingham, Alabama 35291 379 Units 72 Units South Texas Project Callaway Internech, Inc. Bechtel Power P.O. Box 2279 15740 Shady Grove Rd.

Bay City, Texas 77414 Gaithersburg, Maryland 20877-1454 353 Units 375 Units Indian Point #3 Wolf Creek Power Authority of the state of New York Bechtel Power P.O. Box 215 See Above Buchanan, New York 10511 355 Units 2 Units

3 1

l l

  • 1 Attachment I Page 3 of 3 Davis Besse W.P.P.S.S. #2 Toledo Edison W.P.P.S.S.

300 Madison Avenue P.O. Box 968 Toledo, Ohio 43652 Richland, Washington 99352 2 Units 14 Units Zion E. I. Hatch Comonwealth Edison Bechtel Power P.O. Box 767 15740 Shady Grove Rd.

Chicago, Illinois 60690 Gaithersburg, Maryland 20877-1454 6 Units 1 Unit Oconee River Bend Mill Power Supply Stone and tiebster P.O. Box 32307 P.O. Box 5200 -

s Charlotte, North Carolina 28232 Cherry Hill, New Jersey 08034 2 Units 98 Units -

Oconee McGuire Bahnson Service Bahnson Service Company P.O. Box 159 P.O. Box 57 Seneca, South Carolina 29678 Cornelius, North Carolina ?8031 56 Units 11 Units

. e mun O

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NORTHEAST UTILITIES j ,1 co=cian a.o .a = ~~ P O BOX 270 l **'*-"'N"*"'

HARTFORD. CONNECTICUT 06141-0270 Z,.,$'L".".,' "1,,,, (203) 666-6911 L ' J .. m --

February 22, 1985 Docket No. 50-423

. F0674A Dr. Thomas E. Murley Regional Administrator Region I U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

Dear Dr. Murley:

Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies in Design and Construction:

Non-Motor Operated Curtain Type Fire Dampers (SD-70)

In a January 16, 1985 telephone conversation between your Mr. T. Rebelowski and our Mr. 3. Putnam, Northeast Nuclear Energy Company (NNECO) reported a potential significant deficiency in the construction of Millstone Unit No. 3 as required by 10CFR50.55(e).

The potential significant deficiency involves non-motor operated curtain type fire dampers which may not close under flow conditions. These fire dampers are used in the HVAC systems at Millstone Unit No. 3 and are manufactured by Air Balance Company or Ruskin Manuf acturing. We have determined that this is a significant deficiency for Millstone Unit No. 3.

All of the subject QA Category I fire dampers requiring closure under system flow will be tested in place for closure under design flow conditions. Any dampers which fail this test will be evaluated on a case-by-case basis to determine the best course of corrective action and modified accordingly.

We consider this to be our final report for SD-70. As discussed with Mr. T. Rebelowski, this report is being provided by February 22 rather than February 15, 1985. We trust that the above information satisf actorily responds to your concer Very truly yours, 3 NORTHEAST NUCLEAR ENERGY COMPANY 412 'd W. G. Counsi!

Senior Vice President

. .t 4

cc: Mr. 3. M. Taylor, Director Division of Inspection and Enforcement U.S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, MD 20814 6

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< NORTHEAST UTILITIES

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HARTFORD. CONNECTICUT 06141-0270

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o .e wi.m === co-a= (203) 666-6911 esostag as' Mf aa re s tag.Cou.aw March 20,1985 Docket No. 50-423 B11491 Dr. Thomas E. Murley Regional Administrator Region i U.S. Nuclear Regulatory Commission 631 Park Avenue King of Prussia, PA 19406

References:

1. W. G. Counsil letter to T. E. Murley, F0674A, dated February 22,1985.
2. U.S. Nuclear Regulatory Commission, Branch Technical Position CMEB 9.5-1, dated July 1981.

Dear Dr. Murley:

Millstone Nuclear Power Station, Unit No. 3 Reporting of Potential Significant Deficiencies in Design and Construction:

Non-Motor Operated Curtain-Type Fire Dampers (SD-70)

Amendment to Final Report in a January 16, 1985 telephone conversation between your Mr. T. Rebelowski and our Mr. J. Putnam, Northeast Nuclear Energy Company (NNECO) reported a potential significant deficiency in the construction of Millstone Unit No. 3 as required by 10CFR30.55(e). We determined that this is a significant deficiency for Millstone Unit No. 3 and provided you with a final report in Reference 1.

The significant deficiency involved non-motor operated curtain-type fire dampers which may not close under flow conditions. These fire dampers are used in the HVAC systems at Millstone Unit No. 3 and are manufactured by Air Balance Company or Ruskin Manufacturing.

We informed you in Reference I that all of the subject QA Category 1 fire dampers requiring closure under design flow would be tested in place for closure under design flow conditions. Any dampers which f ail this test will be evaluated on a case-by-case basis to determine the best course of corrective action and modified accordingly.

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9 Subsequent discussions with the NRC identified the need to extend this testing l

and evaluation to QA Category 11 and III fire dampers. Therefore, we would like to amend our final report on 5D-70 to include testing in place for closure under design flow conditions for all QA Category II and III fire dampers installed in fire bou'ndaries separating redundant safety-related areas at Millstone Unit No. 3, as defined in Reference 2.

Very truly yours, NORTHEAST NUCLEAR ENERGY COMPANY

_ . . h W. G. Counsi,t j A. w, m Senior Vice Pr'sident e

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-O t% N. h.t m By: R. P. Werner Vice President cc: Mr. J. M. Taylor, Director Division of Inspection and Enforcement U.S. Nuclear Regulatory Commission Phillips Building 7920 Norfolk Avenue Bethesda, MD 20814

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