ML20085K285

Telecopy Ro:On 731010,following Routine Monthly Isolation Censor Check,Feed Breaker for MO3-1301-1 Tripped.Cause Not Stated.Breaker Reset

ML20085K285
Person / Time
Site:	Dresden
Issue date:	10/10/1973
From:	Worden W COMMONWEALTH EDISON CO.
To:	James Keppler NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20085K273	List: ML20085K272 ML20085K285
References
NUDOCS 8310200377
Download: ML20085K285 (2)

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e 03V:3Ja en' 7 O'M VEE 147(1316)(1-015001C283)PD 10/10/73 1315 106 IPMVEIA MVN l9730CT 10@@ ;hff g g gg gg h9, lf 01126 TDVE MORRIS IL 71 10-10 1148A CDT 3 W ,e, % ,

t)MS JAMES G KEPPLER DIR DIVI 0F,.. COMPLIANCE:REqION 3 N f S ' NW  !

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N Mfkk k dLEN ELLYN IL 60137 h ji . , l 5 odoJECT DPR-25 DRESDEN NUCLEAR POWER STATION UNIT 3 q;If THIS WILL CONFIRM A CONVERSATION WITH MR. FRED MAURA 0F Y0tJ8 i L, j OFFICE AT 1100 HOURS THIS DATE CONCERNING A BREAKER TRIP OF[aMUTOR j

OPERATED VALVE M05-1301-1 FOLLOWING ROUTINE MONTHLY ISOLATION CENSOR'S CHECK THE FEED BREAKER FOR M03-1301-1 TRIPPEDWHENTHEOPE(AT ATTEMPTED TO REOPEN THE VALVE THE BREAKER WAS RESET AND THMkALV ' I:; 3 ,

h]l THEN OPERATED SATISFACTORILY 55 l ;5 E+ h: . <a V P WORDEN SUPERINTENDENT DRESDEN NUCLEAR POWER STATION 2 !6 : 1 COMMONWEALTH EDISON C0 ROUTE 1 MORRIS ILL hh">,>3it j 8310200377 731018 sPDR ADOCK 05000249 Ih$

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~ Address Reply to: Post Office Box 767 l Chicago, I!!inois 60690 WPR Ltr #53-7h Dresden Nuclear Power Station R. R. #1 Morris, Illinois 60h50 January 23, 197h -

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, /' h Mr. J. F. O' Leary, Director

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Directorate of Licensing k1 U. S. Atonic Energy Connission Washington, D. C. 205h5

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SUBJECT:

IIISPEC'"IC'I CF BERGEI-PATIESCU FYDPitULIC SHOCK SUFF?l,5SCHS AT DR ODI; :;UCLEAR PC.ER STATIO:i UUIT es, AM Du so-c9

References:

1) Letter frca Mr. D. J. Skovholt to Mr. J. S. Abel dated October 1,1973

2) Letter from Mr. W. P. Worden to Mr. A. Giambusso dated August 16, 1973

Dear Mr. O' Leary:

This letter is to report infomation concerning the station's third inspection of Bergen-Paterson hydraulic shock suppressors on Unit #3 The unit was shutdown on January 17, 78 days after the previcus snubber inspection outage, to repair electronatic relief valve 3-203-3A and to effect repairs to the HPCI systen. Because the reactor was shutdown for longer than 2h hours, a snubber inspection was perfomed as required by Reference (1).

The inspection revealed that all h3 Bergen-Paterson snubbers on Unit #3 were operable, and exhibited overall integrity. There were eight (8) snubbers in the drywell that had low oil level indication on the accunulator. In addition, torus snubber #73 had slightly low oil level indication on the accumulator. It is believed that the low oil level is due to small leaks, but because the leakage is small there is no evidence of fluid leaks or loss of overall integrity. All nine of these snubbers had satisfactory oil level during the previous inspection. The attached lists contain piston rod extensions and fluid level indicator positione found during this inspection.

Eleven Grinnell snubbers, located in the turbine and isolation condenser pipeways, were inr:pected to supplement the above described inspection. All were operable, but one of the Grinnell snubbers had low oil indication. All ten (10) snubbers mentioned in this report as  ;

exhibiting low oil level were filled prior to resuming power operation. I i

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Mr. J. F. O' Leary, Director January 23, 197h The failed snubber support, which was found and repaired during the initial inspection, was exactined on January 8 utili::ing ultrasonic and dye penetrant testing techniques. See Reference (2).

No indications of a faulty weld were detected.

Sincerely, Y hY M.

W. P. Worden Superintendent WPd:ls I

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O O Fluid Level Station I.D. Piston Rod Position (in.) Indicated Position (in.)

n 3 1/8 3 1/2 T3 3 1/8 h (low)

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3 1/2 T7 2 3/h 2 3/h T8 3 31A U 3 31A l T10 3 1/h 31A

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Snubbers in Drywell Fluid Level Station I.D. Piston Rod Position (in.) Indicated Position (in.)

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2 3.00 h.co (low) 3 3.00 3.00 h 3.00 1.00 '

. 5 3.00 3.00 6 3.00 2.50 7 3.5o h.oo 8 3.50 6.00 (low) 9 h.50 h.50

'lo 3 00 3.33 ,

11 3.50 3.50 12 h.50 h.oo 13 3.50 3.50 1h h.oo h.oo 15 3.50 3.50 16 h.co 3.50 17 2.50 2.50 18 3.00 3.00 19 3.50 6.00 (low) 20 3.50 3.50 21 2.12 3.50 (low) 22 3.38 6.00 (low) 23 2.75 6.00 (low) 2h 2 75 3.25 25 3.50 3.75 26 3.00 3.50 27 1.75 1.50 28 2.25 6.00 (low) 29 2.75 1.75 30 2.25 2.00 '

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/ ATOMIC ENERGY COMMISSION

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\; m,n Wqf e wasmucron. o c. as4s Docket Nos, 50-237, 50-254, and 50-265 Commonwealth Edison Cocpany ATTN: fir. J. S. Abel Nuclear Licensing Moinistrator -

Boiling Water Reactors Post Office Box 767 Chicago, Illinais 60690 Gentlemen:

Inspections of hydraulic shock suppressors (snubbers) as required by RO Bulletin 73-3 revealed that a large percentage of the seals in Bergen-Patterson units were defective. Reinspections in compliance with RO Bulletin 73-4 indicated that defects can recur in six weeks' time or less.

Two different seal materials have been used in Bergen-Patterson snubbers; a tillable gum polyurethane which contains plasticizers and other additives and a colded polyurethane known to be free of these additives. It has been postulated that dissolving of the plasticizer into the silicone hydraulic fluid has caused seal shrinkage and deterioration. Therefore, millable gum polyurethane should not be used in hydraulic snubbers, except on an emergency basis.

The performance and reliability of unadulterated molded polyurethane in a reactor environment has not yet been established. Test data indicate that an incompatibility exists betueen molded polyurethane and the silicone fluid which may limit the inservice life of the molded material. The use of colded polyurethane seals should, there-fore, be considered an interim repair until more data is available or an improved material is established.

Based on the above considerations, we require the following action be taken on all Bergen-Patterson snubbers installed on safety related systems af ter the shutdown required by RO Bulletin 73-4.

1. Snubbers , Inaccessible During Reactor Operation During the shutdown required by R0 Bulletin 73-4, replace seal material in all snubbers inaccessible during reactor operation with material deconstrated to be compatible with the hydraulic 3

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(:) (:);ct i e:3 fluid at the operating environment. (If such material is unavailable, the use of molded polyurethane known to be free of additives will be acceptable as an interim repair.) Reinspect these snubbers whenever the reactor is shutdown for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or longer and snubbers have not been inspected for 30 days, but in no event should the interval between inspections exceed 120 days. Repair defective units before returning to power operation. If unavailability of materials prevents the changcout of all inaccessible snubbers or dictates repairs with millable gun seals, only defective units need be repaired.

Under these conditions, reinspect every 30 days until improved

- seal-material is J.nstalled<. which should be-accomplished at the earliest practical time.

2. Snubbers Accessible During Reactor Operation Repair defective snubbers accessible during reactor ope, ration as outlined in 1. above. Reinspect accessible snubbers every 30 days or less and repair defective units as needed.

During the required surveillance, inspect snubbers supplied by manufacturers other than Bergen-Patterson. Report the results of the inspections and corrective action taken to the Directorate of Licensing within-15 days after the inspection. This report should include for each manufacturer the number of snubbers . inspected, identification of defective units, and corrective action taken, .

including specific description of materials used in your repair.

Bergen-Patterson is coordinating a development program to determine a long-term solution to the current snubber problem. Based on'the results of this program, the results of your reinspections, and any other pertinent information available, submit to the Directorate of Licensing at an appropriate time, but within one year, your proposed program to improve snubber service life and reliability and propospd changes to your Technical Specifications describing a snubber surveil-lance program with basis.

We also request that you submit to us within 60 days af ter your next shutdown information describing snubber temperature and radiation environment at full power.

Sincerely,

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nald J,.?Skovholt Assistant Director for Operating Reactors Directorate of Licensing j cc: See next page 9

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O o cc: Mr. Charles Whitmore -

President and Chairman Iowa-Illinois Gas and Electric Company

'i 206 East Second Avenue

Davenport, Iowa 52801 i

j John W. Rowe, Esquire 1 Isham, Lincoln'& Beale .

I Counselors.at Law '

l One First National Plaza

Chicago, Illinois 60670 i ,

j Morris Public Library J 604 Liberty Street '

Morris, Illinois 60451 Moline Public Library 504 - 17th Street Moline, Illinois 61265 3 y 4

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n) , One F..st Nat:cna.,-. ara, CNcago. Illinois f, Address Reply to: Post Office Box 767

% Chicago. Ilknois 60690 August 29, 1973 Mr. Boyce H. Grier Regional Director Directorate of Regulatory Operations - Region III U.S. Atomic Energy Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137

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Subject:

Dresden, Quad-Cities and Zion Stations

, Hydraulic Shock Absorbers Lear Mr. Grior:

In response to your letter of August 17, 1973, the following program for reinspection of Bergen-Patterson ,

hydraulic shock absorbers installed on safety-related systems is provi,ded. The reinspections are scheduled to be performed on approximately the following schedules.

Unit Returned Date Scheduled Unit To Service For Reinsocction Quad-cities 1 8- 6-73 9-21-73 Quad-Cities 2 8- 5-73 10-10-73 Dresden 2 8-13-73 10- 3-73 Dresden 3 8-10-73 10-17-73 4

Zion 7-27-73 9-22-73 Reinspection will be conducted by each station in accordance with Directorate of Regulatory Operations Bulletin 73-4, dated August 17, 1973. Specif,ically, the inspection will l include the following:

a. Determination of condition of seals - this will be accomplished by visual insepction of each hydraulic shock absorber for signs of leakage, change in ffuid indicator position,'etc. Absence of any indication of degradation provides assurance that the  !

seals are functioning properly. Additionally, one shock

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, mrnonwealth Edison'Cornpa:O Mr. Boyce H. Grier . August 29, 1973 one of the hotter locations in the containment, will be completely disassembled and inspected for signs of deterioration of the seal material.

b. Verification of overall integrity of shock absorber assemblies -

this will be accomplished by visual inspection.

c. Examination for loss of fluid, fluid leaks and other signs of distress - this will be accomplished by. visual inspection.

d. Recording of piston rod extension and fluid level indicator 9 position.

Reporting of the results of these reinspections will be in accordance with Item 4 and Item 5 of your August 17, 1973 Directorate of Regulatory Operations Bulletin 73-4.

If you have any further questions or comments .

please contact me.

Very truly yours, e a Qn.

au ByronLee,Jr.g(

Vice-President V 2 .

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%:'/' Chicago, Illinois 60690 August 27, 1973 Mr.'Boyce H. Grier Regional Director Directorate of Regulatory Operations - Region III U.S. Atomic Energy Commission 799 Roosevelt Road Glen Ellyn, Illinois 60137 '6

Subject:

Updated Report on Inspection of Bergen-Patterson Shock Suppressors and Restraints at the Dresden, Quad-Cities and Zion Nuclear Generating Stations, AEC Dkts 50-10, 50-237, 50-249, 50-254, 50-295 and 50-304

Dear Mr. Grier:

On July 27, 1973, you requested inspection of Bergen-Patterson shock suppressors and restraints in use at Commonwealth Edison's nuclear generating stations. My letter of August 6, 1973 summarized the results of the inspections as of that date. t This letter revises and expands the data contained in the August 6 letd ter based upon more detailed examination of the " snubbers".

Minor errors in the previous tabulation are also corrected.

There are no Bergen-Patterson " snubbers" in use at  ;

Dresden Unit 1. Of the total of seven (7) " snubbers" furnished I by- others , five have been inspected and found to be operable. .

The other two will be inspected during the refueling outage scheduled to begin in mid-September, 1973.

Dresden Units 2 and 3 each utilize forty-three (43)

Bergen-Patterson " snubbers" on safety-related systems. A total of twenty-eight (28) on Unit 2 and twenty-nine (29) on Unit 3 were found to be inoperable due to loss of fluid resulting from seal failures. The inoperable units were all located inside the drywell. To avoid releasing more oil in the drywell and to expedite repairs the units were rebuilt without determining specifically which seals on each unit were failed.

I 4 G t & r g 7) 2.

O Commonwealth Edison Company O

i Mr. Boyce H. Grier August-27, 1973 The previous report listed eleven " snubbers" on each unit which were not manufactured by Bergen-Patterson. It has been determined that eight out of the eleven are not installed on safety-related systems. Of the remaining three per unit, none were found to be inoperable.

There are twenty-nine (29) Bergen-Patterson " snubbers" on each of the two Quad-cities units. It has been determined that twenty-five (25) of those on Unit 1 and twenty (20) on Unit 2 were inoperable as a result of seal failures. All the u

" snubbers" are tabulated in the attachment to this' letter.

Specific seal failures on each " snubber" were not identified.

Unit 1 safety-related systems utilize eighteen (18) " snubbers" made by other manufacturers. Two were inoperable but neither failure was related to seal deterioration. A Grinnel model G5x5 (bore x, stroke), serial No. 4451, on the main steam piping outside the containment had a broken oil line with resultant fluid loss. A Grinnel model G 3-3/4 x 5, serial No. 4443, outside the containment on the feedwater piping had a loose connection and had lost its oil. Unit 2 has twenty (20) non-Bergen-Patterson " snubbers" including four (4) which were not included in the previous report. All except one were found to be operable. A Grinnel model G S x 5, serial No. 4694, on the main steam piping outside the containment had a loose tubing connection with resulting oil loss.

It has been determined that the safety-relnted systems on Zion Unit 1 contain sixteen (16) Bergen-Patterson " snubbers" and a total of 503 others. All were checked during hot functional testing early this year. The Bergen-Patterson units were ,

reinspected on July 27, 1973 and found to be satisfactory in all respects. Of the 503 others, all but.136 have been inspected and found to be operable. It is planned to complete the inspection of the others before proceeding above 50% power.

Defective " snubbers" identified during these inspections were repaired prior to resumption of operation.

Very truly yours, i

ac ch . 1 Byr n Lee, Jr.[4 Vice President y

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O , DRESDEN I'AILCD nFRGEN-PATTE!

"SMUPDERS" emmSem 2 System Site .

HPCI Stroke x Bor_c,e Model No, 6" x 2-1/2" Serial No.

6" x 2-1/2" HSSA-10 6" x 2-1/2" 11SSA-10 487511 LPCI 6" x 2-1/2" IISSA-10 487556 6"'x 2-1/2" IISSA-10 487560 6* x 2-1/2"  !!SSA-lO 487500 Core Spray 6" x 2-1/2" IISSA-lO 487541 6" x 2-1/2" HSSA-10 487567 Feedwater 6" x 2-1/2" IISSA-lO 487533 6" x 2-1/2" 11SSA-10 487500 Cleanup 6" x 2-1/2* IISSA-10 487539 6" x 2-1/2" 11SSA-10 487570 6" x 2-1/2" HSSA-10 487553 6" x 2-1/2" HSSA-10 487575 .i

.. P.ecirculation 6" x 2-1/2" HSSA-10 487572 6" x 4" IISSA-10 487544 6" x 4" IISSA-30 487545 6" x 4"  !!SSA-30 407769 6" x 4" .

HSSA-30 487776 6" x 4" IISSA-30 487759

. 6" x 4" IISSA-30 487781 6" x 4 " 11SSA-30 488788 6" x 4" USSA-30 487757 6" x 4"  !!SSA-30 487762 6" x 3-1/4" IISSA-30 487814 6" x 3-1/4" IISSA-20 487758 6* x 2-1/2"  !!SSA-20 487616 6" x 2-1/2" HSSA-10 487617 HSSA-10 482597 482596 IIPCI DnESDEN 3* .

6" x 2-1/2" 6" x 2-1/2" USSA-10 6" x 2-1/2"  !!SSA-10 51035 LPCI 6* x 2-1/2" HSSA-10 51035 6" x 2-1/2" IISSA-10 51035 6* x 2-1/2" HSSA-lO 51035

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Core Spray 6" x 2-1/2" IISSA-10 F51035 Cleanup 6" x 2-1/2" HSSA-10 51035 6" x 2-1/2" USSA-10 F51035

• 6* x 2-1/2" HSSA-10 51035 Ns 6* x 2-1/2" 11SSA-10 51035 Feedwater 6" x 2-1/2" }ISSA-10 F51035 6* x 2-1/2" HSSA-lO F51035 6" x 2-1/2" IISSA-10 F51035 Recirculation 6" x 2-1/2" " IISSA-10 51035 6" x 4" IISSA-10 F51035 6" x 4" IISSA-30 F51035 6" x 4" IISSA Missing 6" x 4" HSSA-30 Illegible 6" x 4" HSSA-30 407785 6" x 4" IISSA-30 42781

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6" x 4" HSSA-30 487784 6" x 4" 11SSA-30 487767 6" x 4" IISSA-30 487771 6" x 4" 11SSA-30 487800 6" x 4" IISSA-30 487783

. *6" x 3-1/4" IISSA-30 487819 9

6" x 2-1 "

- IISSA-2 407789

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O OUAD-CITIES FAIT.ED_nE3CEN-PATTERSON " S NUBB12RS "

Page 2 ,

OUAD-CITIES 1 Size System Stroke x Born Model No. Serial No.

Core Spray 6" x 2-1/2" 11SSA-10 61204-1 6" x.2-1/2" HSSA-10 61284-1 6". x 2-1/2" IISSA-lO Missing 6" x 2-1/2" IISSA-10 F-61284 RIIR 6",,x.2-1/2" IISSA-10 61284-1

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6"..x 2-1/2" HSSA-10 F-61284-1 6" x 2-1/2" IISSA-lO Missing

' , .- , 6" x 2 1/2" HSSA-10 F-61284-1 6" x 2-1/2" IISSA-10 F-61284-1 6". x 3-1/4" HSSA-20 F-51035 Recirculation 6" x.2-1/2" HSSA-lO 482594 6". x 2-1/2" IISSA-10 482604 j 6". x.2-1/2"

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. 11SSA-10 482500 6". x 2-1/2" HSSA-lO 482605 6" x 2-1/2" HSSA-lO 482559 6", x 4" HSSA-30 487792

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6" x 4" HSSA-30 407761 6". x 4" HSSA-30 48700-9 6".,x 4" HSSA-30 87775 6 *. , x ' 4 ". HSSA-30 487820 6". x 4" HSSA-30 487780 6"..x 4" HSSA-30 487760

, 6" x,4" IISSA-30 487774 6", x _ 5" HSSA-50 68290 6".x 5", HSSA-50 68290 l*

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l Core Spray HSSA-10 F62955-2 6" x 2-1/2" '

6" x 2-1/2" HSSA-lO F62955-2 6" x 2-1/2" -

IISSA-10 F62955-2 6". . x .,2-1/2 " HSSA-10 F62955-2 RER' 6",.x,2-1/2" HSSA-10 F-6128-1 6",',x ; 2-1/2 " HSSA-10 F--612 8-1 6*,,x.2-1/2" HSSA-10 F-6128-1 6 *, , x ' 2-1/2" HSSA-10 F-6128-1

., 6 ". . x ,' 2 -1/2 " HSSA-10 6128411 Tec, m,..irculation 6",,x 5" HSSA-50 68290 *

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6",x.4" HSSA-30 487801 6".,x'4" ~

-HSSA-30 407773 6".x 4" HSSA-30 487811 6" x 4" HSSA-30 487796 N. recC. d e', 6 ". . x , -/" . SA- 0 482590 6".x 2-1/2" HSSA-10 F-61284-1 6", . x . 2-1/2" HSSA-10 F-61284-1

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Chicago Ilhnois 60690 vp-y 4 f p g y August 6, 1973 Mr. Boyce H. Grier Regional Director Directorate of Regulatory Operations - Region III U.S. Atomic Energy Commission 799 Roosevelt Road ,,

' Glen E.llyn, Illinois 60137 *

Subject:

Inspection of Bergen-Patterson Shock Suppressors and Restraints at the Dresden, Quad-Cities and Zion Nuclear Generating Stations, AEC Dkts 50-10, 50-237, 50-249, 50-254, 50-265, 50-295 and 50-304

Dear Mr. Grier:

On July 27, 1973, you requested that Commonwealth Edison cond,uct immediate inspections of all Bergen-Patterson shock suppressors and restraints (" snubbers") in use at our nuclear generating stations. This letter is to inform you of the status of those inspections.

It has been determined that no Bergen-Patterson " snubbers" are in use at Dresden Unit 1. Of the total of seven (7) " snubbers" furnished by others, five have been inspected and found operable.

The 2 other " snubbers" on this unit will be inspected during the refueling outage scheduled to begin in mid-September, 1973.

Zion Unit 1 has sixteen Bergen-Patterson " snubbers" -

and over one thousand others made by Grinnel. All " snubbers" at Zion 1 were checked during hot functional testing early this year. All sixteen Bergen-Patterson " snubbers" were re-inspected on July 27, 1973, and found to be satisfactory in all respects.

It is planned to complete this inspection before proceeding above 50% power.

Quad-Citics Unit 2 was shut down on July 28, 1973 to inspect " snubbers" in the drywell. Of the 29 Bergen-Patterson units in use a total of 19 are considered to be inoperable due to loss of fluid. The attached list details those failures.

Sixteen (16) " snubbers" on Unit 2 were made by others. One of the 16 was found inoperable due to a loose tubing connection and loss of fluid. .

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O . O Commonwealth Edison Company Mr. Boyce H. Grier August 6, 1973 On August 1, 1973 Unit 1 at Quad-Cities was removed from service for inspection of the 29 Bergen-Patterson " snubbers".

A total of 24 were found to be inoperable due to loss of fluid.

Those failures are also detailed on the attached list. Inspection of the 18 other " snubbers" revealed two which were inoperable.

Neither failure was attributed to seal problems. One had a broken oil line and the other had a loose connection.

Dresden Unit 3 was taken off our system on July 31, 1973 u

, fo'r inspection. Of the 43 Bergen-Patterson " snubbers" on that unit 29 are inoperable due to loss of hydraulic fluid. The locations of those units are included on the attached list. One of the eleven other " snubbers" was inoperable due to low fluid level in accumulator. It was attached to the turbine bypass line to the condenser. ,

The inspection outage on Dresden Unit 2 began on August 2, 1973. A total of 28 out of the 43 Bergen-Patterson

" snubbers" have been found to be inoperable due to loss of fluid.

.The attached list gives the specifics. Two of the eleven other " snubbers" were inoperable. They were also attached to the turbine bypass line to the condenser.

The defective " snubbers" identified during these inspections will be repaired prior to resumption of operation.

The first time that Dresden 2 and 3 and Quad-Cities 1 and 2 are shut down following one month's operation, the drywells will be de-inerted and the Bergen-Patterson " snubbers" inspected. A program of more frequent surveillance on the Bergen-Patterson

" snubbers" located outside the drywell at Dresden will be implemented.

Very truly yours, s

eEbcivv1 A. G' Byran Lee, Jr.

Vice-Presidentd

Unit System Number Failed Size (Stroke x Bore)

Dresden 2 HPCI 5 6" x 2-1/2" LPCI 2 6" x 2-1/2" core spray 2 6" x 2-1/2" feed wa'ter 3 6" x 2-1/2" cleanup 3 6 " x 2-1/2 "

recirculation 9 6" x 4" 2 6" x 3-1/4" 2 6" x 2-1/2" ,,

Dresden 3 HPCI 5 6" x 2-1/2" LPCI 2 6" x 2-1/2" core spray ,.

- 2 6" x 2-1/2" cleanup ,

3 6" x 2-1/2" feedwater 3 6" x 2-1/2" recirculation 11 6" x 4" 1 6" x 3-1/4" 2 6" x 2-1/2"

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Quad-Cities 2 core spray 4 6" x 2-1/2" RHR 5 6" x 2-1/2" recirculation 1 6" x 5" 5 6" x 4" 4 6" x 2-1/2" Quad-cities 1 core spray 4 6" x 2-1/2" RHR 6 6" x 2-1/2" Recirculation 5 6" x 2-1/2" 8 6" x 4" 1 6" x 5" '

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UNITCO STATES

! ATOMIC ENERGY COMMISSION

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REGION til

'Cis o' 799 ROOSEVELT ROAD nmog GLEN ELLYN. ILLINOlG 60137 (312) 853-2650

, August 17, 1973 Cerconucalth Edison Conpany Dockets !!o. " 0 "'t ATn!: fir. Eyron Lee, Jr. 50-2/

P. O. boa 767 50-254 Chicago, Illinois 60590 50-205 50-295 Centicaan:

The reports of your action in recponec to Ecculatory Operationc Eulletin

!!o. 73-3, dstcd July 27, 1973, and othnr inforr.ation concerning Ecr:;cn-Patcrnon hydraulic shock cbcorbers, indicato that additional action is advicable.

Enclosed is Regulatory Operations Eulletin !!c. 73-4 uhich providen you with cdditional informtion and lists certain actione that appear appropriate on a tinely basic. The Directorate of Liccucin?. currently is evaluating tha uced for a continuing curve 111ance pror,ren for bydraulic shock absorbers.

You are requected to take the actica chorn under ACTIO:: IIGICATED in the encicsed neculatory Opcrations Eulletin 1:o. 73-4, dated August 17, 1973.

Should you have quections concerning thic catter, pleace contcet ne.

Sinecrcly, Boyen H. Crier Regional Director

Enclosure:

RO Eulletin 73-4 bec: RO Files DR Central Files PDR '

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August 17, 1973 Directorate of Regulatory Operations Bulletin 73-e DEFECTIVE BERGEN-PATERSON HYDRAULIC SHOCK ABSORBERS INFORMATION Reference is made to Regulatory Operations Bulletin 73-3, dated July 27, 1973, entitled DEFECTIVE HYDRAULIC SHOCK AISORBERS AND RESTRAINTS which provided information on known probices with hydraulic shock absorbers and which requested actions, including inspections of installed hydraulic shock absorbers, by certain utilities.

The compiled results of these inspections of Bergen-Paterson shock absorbers, based on telephone reports from affected licensees to the fise Regional Offices of the Directorate of Regulatory Operations, reveal that a large percentage of installed Bergen-Paterson hydraulic shock absorbers were not fully operational. In addition, preliminary information indicates that routine repairs, replacing defective seals and. filling hydraulic oil reservoirs may not be an adequate long range solution to this problem.

There is also some indication that deter.ioration of the affected hydraulic shock absorbers can occur over a relatively short period of time (less thah 90 days).

ACTION INDICATED ,

1. Schedule a reinspection of Bergen-Paterson hydraulic shock absorbers installed in safety related systems to be conducted approximately 45 days and no longer than 90 days after the plant has been at operating temperature subsequent to the inspection performed as requested in RO Bulletin 73-3.

2. The inspection should include the following:

a. Determination of condition of seals.

b. Verification of overall integrity of shock absorber assemblies.

c. Examination for loss of fluid, fluid leaks, and other signs of

.' distress.

d. Recording of piston rod extension and fluid level indicator positions.

3. Inform this. office of the planned date for reinspection of'the Bergen-Paterson hydraulic shock absorbers.

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4. Provide this office with a prompt telephone report of the significant findings of this reinspection. If defective shock absorbers are identified, a written report should be submitted to this office within 10 days following completion of the inspection; if_no defective shock absorbers are identified, the written report should be submitted within 30 days following the completion of the inspection.

5. The written report should include the following:

a. As appropriate for each defective shock absorber identified, a description of the mode of failure, corrective action and tests i performed to determine the adequacy of the repair,

b. A description of the program for the development and subsequent installation of a permanent modification to the hydraulic shock absorber installation to assure proper operation. The description i should include the technical basis for the conclusion that i deficiencies in the Bergen-Paterson hydraulic shock absorbers j have been resolved.

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UNITED STATES 7/ ' cf i - ' '['. ATOMIC ENERGY CCMMiSSION

-'.J ' /4 OlV6lON OF CC'MLI AtJCl?

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m nooncvELT noAD HLEPHONC GLcN ELLvN. ILLirJols 60137 012) 23-M 00 AUG 171973 LOCAL PUBLIC DOCD'2NT ROOMS Enclosed are copies of documents listed below relating to Cormon aalth Edi son Ccrpaw , Docket No(s). 50-23 7 andM'3

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Letter to Co=onwealth Edison Company from B. H. Crier dated August 17, 1973.

This correspondence is submitted pursuant to arrangements made by the Public Proceedings Branch, Office of the Secretary, for use by the public.

Where possible, these materials should be punched and filed in a folder labeled as follows:

CORRESPONDENCE TO AND FROM APPLICANT OR LICENSEE (Excluding Environmental and Antitrust)

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f, G Jf B I. Grier Regional Director

Enclosures:

As noted above cc: Washington Public Document Room, w/ enc 1 Central Mail & Files Unit, Document Room Clerk, w/o enci s e 3 s f '

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