ML20023D552

Final Deficiency Rept Re Failure of Liquid Carbon Dioxide Storage Tank/Piping & Affect on Operability of Emergency Diesel Generators.Issue Not Reportable Per 10CFR50.55(e)

ML20023D552
Person / Time
Site:	Shoreham File:Long Island Lighting Company icon.png
Issue date:	11/12/1981
From:	Milligan M LONG ISLAND LIGHTING CO.
To:	Brier B, Grier B NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
Shared Package
ML20023D547	List: ML20023D552
References
10CFR-050.55E, 10CFR-50.55E, SNRC-635, NUDOCS 8305200594
Download: ML20023D552 (2)

Text

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g,,N f D LON G IS LAN D LIG HTI N G COM PANY_ .

T fc,EI,.6.Y SHOREHAM NUCLEAR POWER STATION

\ P.O. BOX 618 tJORTH COUNTRY ROAD e WADING RIVER. N.Y.11792 November 22, 1981 SNRC-635 Mr. Bovce F. Grier

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Of fice of ' Inspection and Enforcement Region I U.S. Nuclear Regulatory Commission 631 Park Avenue -

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King of Prussia, PA 19406

! LONG ISLAND LIGHTING COMPANY Shoreham Nuclear Power Station - Unit 1 t

Docket No. 50-322

Dear Mr. Grier:

On September 14, 1981 in accordance with 10CFR50.55(e), we reported verba11.~ to Recion I a cotentially recortsble deficiency concerninc the impact a failure o'f our liqu'id CO2 storage tank an'/or its

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(_,)/ associated piping might have on the operability of our Emergency Diesel Generators. Since, no additional information was available concerning this subject en the "due date" of our 30-day letter, we requested entensions of the filing date in telecons with Mr. L.

Narrow on October 13th and Mr. H. Kister en November 5th, 1981.

. This letter serves as our 30-day written report of this deficiency.

l .

1 Description of Potential Deficiancy

. An analysis has been performed by our Architect Engineer, Stone &

Webster Engineering Corp. to determine the potential hazard to the 2

operability of the emergency diesel generators posed by the relatite l

location of the CO2 storage tank and the diesel air intakes. The

!. diesel generators for the Shoreham Station are located in adjacent r 4 rooms in the Control Building. The air intakes for the diesels are lined up on the west wall cf the Control Building. The CO2 f tank for the fire protection system is located in the yard, west i of the Control Building, about 40 feet north of the nearest diesel air intake.

i j Seismic design requirements are not specified for fire protection

.; systems, except for piping supports in the areas of safety related i

j structures, systems, and components. Since the CO2 tank is not seismically designed, possible system interaction with the diesel i

[~'N) generatrrs has been censidered.

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An analysis was performed to determine the likelihood that the I diesel generators could be adversely affected by CO2 due to tank damage. The analysis conclufes that t.hc diectlr would not be affected. A sunmary of the analysis is presented below.

The CO2 tan'. supports are not seismically designed. Analysis shows that for the Design Basis Earthquake (DBE),the internal tank supports could fail. In that etent, the tank will drop about one foot to the pad belev. For this conditien, it has been determined that the tanh itself "c-*'~s unaffected. It,'could be assumed that piping cor.ec:sc to t.ne tan.-; wouic rupture; however, it has been determincd that the piping would deform, and at worst develon minor leaks releasing insignificant amounts of CO2- Even if'it were to be assumed that the line :ere to rupture, specific and unlikely unf=verable meteorology would have to exist for one diesel generator (or, far less likely, two diesel generators) to be affectn* r ven in this event, at least one, and crobably two, -

olesels woua..c operate as expected.

If a diesel were affected, which is not predicted, the effect would be limited to a slicht delay in starting, with no long term impact on diesel perfor5ance or plant response.

e6 T (s./ / _ Conclusion / Corrective Action Since the analysis indicates that the CO2 tank will have no adverse l

i effect on safety of operation, no corrective action is rcquired and we have concluded that this situation is not recortable under 10CFR50. 55 (e) . No further reports will be forthecm'ing on this issue.

Very truly yours, G ": .

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.u. i.l.I u s x M. H. Milligan Project Engineer bcc: Distribution al4 Shoreham Nuclear Power Station _

SR2/Eng. File. . . A21. 200 q[d TJS/pd cc: Mr. Victor Stello, Director NRC Office of Inspection and Enforcement Division of Reactor Operations Inspection Washington, D.C. 20555 ,

M. J. Higgins Site NRC Trailer i

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P.O. BOX 618. NORTH COUNTRY RCAD e WADING RIVER. N.Y.11792 Decerber 23, 1981 SNRC-649 Mr. Ronald C. Haynes Office of Inspection & Enforcement, Region 1 ~

U.S. Nuclear Regulatory Ccamission 631 Park Avenue King of Prussia, PA 19406 SHOREHA': NUCLEAR PC' DER STATION - UNIT I DOCKET NO. 50-322 h

Dear Mr. H5vnes:

f w, On November 25, 1981, in accordance uith 10 CFR k.55(els we reported verbally to Region 1 of a deficiency within our Diesel Generators manufactured by Transamerica DeLaval. This letter serves as our 30-day written report of this deficiency, and des-cribes our corrective action.

Description of Deficiency On Noverber 24, 1981, LILCO was informed by Region I that Trans-america DeLaval informed the Ccmmission of a potential defect .

concerning standby diesel generators in accordance with the re-guirements of 10 CFR 21. This defect affects a spherical washer used in the fastening of the piston crown to the associated piston skirt. DeLaval has informed us that a failure of these spherical washers was experienced on one piston of a diesel at another nuclear site, resulting in separation of the piston crown from the skirt. We have reviewed our diesel generators in view of this potential problem and on November 24, 1981 deter-l mined that our diesel pistons could be subject to this defect.

It was also determined that if a failure were to occur coinci-dent with the diesel being required to operate, it could prevent it from performing its design basis function.

As a result of this study, it was determined that this situation xv ) constitutes a reportable deficiency under 10 CFR 50.55(e).

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I SNRC-649 O Decerber 23, 1981

( Pp<Je 2 Corrective Action '

Transamerica DeLaval has developed a modified assembly arrange-ment using opposing stacks of belville washers in lieu of the i presently used spherical washers. This modification requires teardown of the diesels for piston removal with subsequent re-machining of the pistons to accept the change.

LILCO has contracted with DeLaval to perform the required tear-down and reassembly following the piston rework using their specialized personnel. As of the writing of this report the teardown of all three diesels has been completed and the pistons including on site spares have been shipped to DeLaval for the rework at their facilities. The rework of pistons should be j completed in early January, 1982 and reassembly of the three j diesels completed by January 31, 1982.

I very truly yours, UHIGINAL sic;xEn g;y M.li..TIIL Lig a s s

I M. H. Milligan d

HE/ law cc: Mr. Richard DeYoung, Director l(,

i NRC Office of Inspection & Enforcement Division of Reactor Operation Inspection Washington, D.C. 20555

} Mr. J. Higgins, Site NRC a

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SR2/Eng File A21.200 I '

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Direct Dial Number October 15, 1982 SNRC-777 l1J Mr. Ronald C. Haynes l

Office of Inspection E. Enforcement t

Region 1

',i U.S. Nuclear Regulatory Commission

'i 631 Park Avenue King of Prussia, PA 19406 l

Long Island Lighting Company I.

Shoreham Nuclear Power Station - Unit 1 Docket No. 50-322 lt

Dear Mr. Haynes:

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I On September 17, 1982, in accordance wit'h 10CFR50. 55 (e) , we

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] reported verbally to. Region I a potential deficiency concerning

,j Jacket Water Pump Shaft failures on the Shoreham Emergency l' Standby Diesel Generators. This letter serves as our thirty-day 4

written report on this deficiency.

Description of the Deficiency The three diesel generators which are affected were manufactured by the Transamerica DeLaval Company of Oakland, California.

These diesel generators, 1R43*G-101, 1R43*G-102, and 1R43*G-103, in the Diesel Emergency Power System are designed to provide standby emergency power for multiple plant safety related

.! systems. The problem was discovered during routine performance

' testing of Diesel Generator 103 (lR43*G-103). The operator received a Jacket Water Low Pressure Alarm and, upon observing an increase in jacket water temperature, initiated a manual shutdown i of the generator. Examination of the Jacket Water Pump revealed that a shaft failure had occurred where the shaft meets the pump impeller. This failure occurred, with 170 hours0.00197 days <br />0.0472 hours <br />2.810847e-4 weeks <br />6.4685e-5 months <br /> of elapsed i running time, after the shaft and impeller had been modified with a tapered fit in accordance with vendor recommendations. This

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SNRC-777 O october 15, 1982 Page 2 modification had been performed to prevent occurrence of a fatigue type failure which was being experienced by-similar units operating in Saudi Arabia. It should be pointed out that this I failure on Diesel Generator 103 appeared to be very similar to a failure that occurred on Diesel Generator 102 (lR43*G-102) on May

( 28, 1982 after approximately 50 hours5.787037e-4 days <br />0.0139 hours <br />8.267196e-5 weeks <br />1.9025e-5 months <br /> of operation. At that time, the failed components were shipped to the vendor for analysis. The preliminary field inspection performed on May 28, 1982 determined that the components failed in a catastrcphic manner rather than by fatigue. Consequently, this was considered an isolated failure.

Since the occurrence of the second failure, detailed inspections have been conducted by vendor representatives, as well as by LILCO and Stone & Webster pump and metallurgy specialists. In addition, the results of the failure analysis performed by DeLaval on the shaft from Diesel Generator 102 have been obtained and indications are that the failure of that shaft was due to a fatigue crack starting at the small keyway bottom radius on the r3 driven side. This resulted in the impeller end of the shaft

(-) twisting off in a conical fracture at about three inches from the end. The initiation of the fatigue crack has been attributed to cyclic movement of the impeller on an improperly tightened impeller hub nut.

Corrective Action At present, engineering of design modifications to the Jacket Water Pump shaft-impeller assembly is actively underway at

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l Transamerica DeLaval. It is expected that these modifications I will involve slight alterations to the shaft, changing the impeller material from bronze to cast iron, and removing the l shaft key at the impeller. Possible alterations to the assembly procedure and the size of the impeller hub washer are also being considered. Current plans are that all modifications will be completed and implemented by the end of November, 1982.

If during the course of performing this work, it is determined l that any major modifications, not discussed in this letter, are O

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SNRC-777

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October 15, 1982 Page 3 necessary, we will notify your office. If you have any questions relative to this matter, please do not hesitate to contact us.

Very truly yours, N

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l M. H. Milligan Project Engineer Shoreham Nuclear Power Station WMJ/ law cc: Mr. Richard DeYoung, Director NRC Office of Inspection & Enforcement Division of Reactor Operating Inspection Washington, D.C. 20555 Mr. J. Higgins, Site NRC

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November 5, 1981 D - M fo y 8  %

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D. 4, ts.g-Director, Office of Inspection and Regulation C U.S. Nuclear Regulatory Commission Vashington, D.C. 20555 g '/

Dear Sir:

In accordance with the requirements of Title 10, Chapter 1, Code of Federal Re-gulations, Part 21. Transamerica Delaval, Inc. , hereby notifies the Commission of a potential defect in a component of DSRV or DSR Standby Diesel Generator.

There exists a potential problem with a spherical washer subassembly which is part of the piston assembly, which could result in engine non-availability.

Transamerica Delaval has supplied the DSR and DSRV engines with the, potential defect to the following sites.

1) Long Island Lighting Co., Shorham Nuclear Power Station ,,/

S/N 74010/12 DSR8

{x } Middlescuth South Errergy, Grand Gulf Nuclear Station

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S/N 74033/36 DSRV16

3) Southern California Edison, San Onofre S/N 75041/42 DSRV20 These spherical washers were purchased from Western Tool and Supply, Oakland, Ca l i fo rn i a. The spherical washers were installed in the Piston Assembly by Transamerica Delaval .

l The potential defect is improperly manuf actured spherical washers. Sphe ri cal washers whicn have not been properly heat treated or machined incorrectly l

l could fall prematurely. If the spherical washer fails, engine availability could be affected.

A copy of this letter will be sent to each of the cognizant parties listed in paragraph 2. Transamerica Delaval has a design available now which replaces the spherical washer design. The existing pistons can be nodified to the new design. Information on this modification will be sent to each party mentioned in paragraph 2, when a copy of this letter is sent as mentioned above. Trans-america Delaval will furnish parts and technical services as requested, and in accordance with each individual contract.

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Tr n,tm3rscs Oliavil Inc.

Transamerica en,,n,cn,C, ,,a,,,,Di.,, ion

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P.O. Box 2161 qq - Oakland, California 94621

= (415) 577-7400 "i

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Di rector, Office of Inspection and Regulation U.S. Nuclear Regulatory Commission Noverber 5, 1981 Transamerica1 Delaval received information on a failure of a spherical washer i piston a sembly at Grand Gulf Nuclear Station on October 27, 1981.

l The corrective action recommended to eliminate this potential problen is to re-place the spherical washer design with the new design. Ve cannot estimate the completion date, since it will depend on the action taken by the engine users.

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anis report confirms an initial telephone call to Mr. R.T. Dodds, Region 5, l Valnut Creek, Cali fornia, on November 5,1981.

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! Our evaluation of this matter was, concluded on November 4, 1981.

I Sincerely, i

2 2. h q w R. E. Eoyer, Panager Quality Assurance l

REB:lc cc: Mr. R.T. Doods U.S. Nuclear Regulatory Commission 1990 N. California Blvd.

Valnut Creek, CA 94596 4m )

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• UNITED STATES OF AMERICA NUCLEAR REGULATORY COMMISSION BEFORE THE ATOMIC SAFETY AND LICENSING BOARD ,,

In the Matter of )

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LONG ISLAND LIGHTING COMPANY ) Docket No."50-322

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(Shoreham Nuclear Power Station, )

Unit 1) )  ;

CERTIFICATE OF SERVICE

! I hereby certify that copies of "NPC STAFF RESPONSE TO SUFFOLK COUNTY MOTION FOR LEAVE TO FILE A NEW CONTENTION CONCERNING THE SH0REHAM EMERGENCY DIESEL GENERATORS" in the above-captioned proceeding have been served on the following by deposit in the United States mail, first "

class, or, as indicated by an asterisk, through deposit in the Nuclear Regulatory Comission's internal mail system, this 18th day of May,1983:

Lawrence Brenner, Esq.* Ralph Shapiro, Esq.

Administrative Judge Camer and Shapiro Atomic Safety and Licensing Board 9 East 40th Street U.S. Nuclear Regulatory Comission New York, NY 10016 Washington, D.C. 20555 Dr. James L. Carpenter

• Administrative Judge Howard L. Blau, Esq.

Atomic Safety and Licensing Board 217 Newbridge Road U.S. Nuclear Regulatory Comission Hicksville, NY 11801 Washington, DC 20555 Dr. Peter A. Morris

• W. Taylor Reveley III, Esq.

Administrative Judge Hunton & Williams Atomic Safety and Licensing Board P.O. Box 1535 U.S. Nuclear Regulatory Comission Richmond, VA 23212 Washington, DC 20555 Cherif Sedkey, Esq.

Matthew J. Kelly, Esq. Kirkpatrick, Lockhart, Johnson Staff Counsel & Hutchison New York Public Service Comission 1500 Oliver Building 3 Rockefeller Plaza Pittsburgh, PA 15222 Albany, NY 12223

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Stephen B. Latham, Esq. .

John F. Shea, III, Esq. Herbert H. Brown, Esq.

Twomey, Latham & Shea -

Lawrence Coe Lanpher, Esq.

Attorneys at Law Karla J. Letsche, Esq.

P.O. Box 398 Kirkpatrick, Lockhart, Hill, 33 West Second Street Christopher & Phillips ,

Riverhead, NY 11901 1900 M Street, N.W. l l 8th Floor i Washington, D.C. 20036 1 1

Atomic Safety and Licensing Board Panel

• Daniel F. Brown, Esq.*

U.S. Nuclear Regulatory Comission Attorney Washington, D.C. 20555 Atomic Safety and Licensing Board Panel Atomic Safety and Licensing' U.S. Nuclear Regulatory Commission Appeal Board Panel * '

Washington, D.C. 20555 U.S. Nuclear Regulatory Commission Washington, DC 20555 James B. Dougherty, Esq.

3045 Porter Street, N.W.

Docketing and Service Section* Washington, D.C. 20008 Office of the Secrbtary U.S. Nuclear Regulatory Comission Stewart M. Glass, Esq.

Washington, D.C. 20555 Regional Counsel Federal Emergency Management Spence Perry, Esq. Agency Associate General Counsel 26 Federal Plaza Federal Emergency Management Agency Room 1349 Room 840 New York, NY 10278 500 C Street, S.W.

Washington, D.C. 20472 f

Lernard M. Bordenick Counsel for NRC Staff F

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COURTESY COPY LIST Edward M. Barrett, Esq. Mr. Jeff Smith General Counsel Shoreham Nuclear Power Station Long Island Lighting Company P.O. Box 618 250 Old County Road North Country Road Mineola, NY 11501 Wading River, NY 11792 Mr. Brian McCaffrey MHB Technical Associates Long Island Lighting Company 1723 Hamilton Avenue 175 East Old Country Road Suite K Hicksville, New York 11801 San Jose, CA 95125 Marc W. Goldsmith Hon. Peter Cohalan Energy Research Group, Inc. Suffolk County Executive 400-1 Totten Pond Road County Executive / Legislative Bldg.

Waltham, MA 02154 Veteran's Memorial Highway

! Hauppauge, NY 11788 David H. Gilmartin, Esq.

Suffolk County Attorney Mr. Jay Dunkleberger County Executive / Legislative Bldg. New York State Energy Office Veteran's Memorial Highway Agency Building 2 Hauppauge NY 11788 Empire State Plaza Albany, New York 12223 Ken Robinson, Esq.

l N.Y. State Dept. of Law Ms. Nora Bredes l 2 World Trade Center Shoreham Opponents Coalition l Room 4615 195 East Main Street New York, NY 10047 Smithtown, NY 11787 f

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