ML19327B185

LER 89-011-00:on 890920,engineering Determined That Rupture Restraint Gaps Were Opened to Greater than Original Design Analysis.Caused by Alignment Performed During Hot Functional Testing.Design Change Mod to Be performed.W/891020 Ltr

ML19327B185
Person / Time
Site:	Beaver Valley
Issue date:	10/20/1989
From:	Noonan T DUQUESNE LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-88-001, IEB-88-1, LER-89-011-01, LER-89-11-1, ND3MNO:1978, NUDOCS 8910260193
Download: ML19327B185 (5)

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'm ?1pggtC Telephone (412) 393-6000..

Ntclear Group ' ,

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m October 20,-1989

' Y, ' ND3MNO:1978 o  :

Beaver Valley Power Station, Unit No. 1 i Docket No. 50-334, License No. DPR-66 i LER 89-011-00 L.

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United States Nuclear Regulatory Commission L

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. Document Control' Desk.

Washington,~DC 20555  ;

Gentlemen:

In accordance.with Appendix A, Beaver Valley Technical

• l specifications,'the following Licensee Event Report'is submitted:

l J. LER 89-011-00, 10 CFR 50.73.b.2.ii.B, " Pressurizer Surge Line Rupture Restraints outside The Design Basis".

7 Very truly yours, l,

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L T. P.~ oonan K General Manager l Nuclear Operations l.

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8910260193 891020 -

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,0ctOb0r 20,.1989

n 1. ! ;ND3MNO:1978.

'f ir- .Page.two

, cc: .Mr.~ William'T. Russell Regional Administrator

-c , United States Nuclear Regulatory Commission i Region l' .,

475 Allendale Road  :

' King of Prussia, PA 19406 l

-C. A. Roteck, Ohio Edison Mr. Peter Tam, BVPS Licensing Project Manager .*

United States Nuclear. Regulatory Commission Washington,'DC 20555 J..Beall,. Nuclear: Regulatory Commission,

. BVPS Senior Resident Inspector

'CAPCO Nuclear' Projects Coordinator Toledo EdisonL INPO Records Center '

Suite 1500  !

1100 circle 75 Parkway )

, Atlanta, GA 30339 l G'.'E. Muckle, Factory Mutual Engineering, Pittsburgh HMr..J.-N. Steinmetz, Operating Plant Projects Manager t

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Mid Atlantic Area .

Westinghouse Electric Corporation y Energy Systems Service Division 1 h Box 355 Pittsburgh,'PA 15230 American Nuclear Insurers c/o Dottie Sherman, ANI Library The Exchange Suite 245

^ 270 Farmington Avenue Farmington, CT 06032 Mr. Richard Janati Department of Environmental Resources P. O. Box 2063 16th Floor, Fulton Building

o Harrisburg, PA 17120 Director, Safety Evaluation & Control Virginia Electric & Power Co.

P.O. Box 26666 One James River Plaza Richmond, VA 23261 1

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a#RC Ferm See - U.S. NUCLEMi 4 tIULATORY Coe8MISSlON

., , LPPROvt0 oms 30 3160004 LICENSEE EVENT REPORT (LER) 5 xma'5 **

F ACILITY NAME pl DOCKET NUM9tR Qi PAGE G Beaver Valley Power Station, Unit 1 0 l61010 l 0 l 31314 1 lOFl 013 itTLE tes Pressurizer Surge Line Rupture Restraints Outside The Design Basis (VENT DATE tll Lt R NUMBE R (el REPORT DATE 471 OTHE R F ACILif f t$ INVOLVED (8)

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NAME ftLEPHONE NVM98R Am6 A CODE Thomas P. Noonan, General' Manager Nuclear Operations 61413 I-11 12 1518 411 12 COMPLif t ONE LINE FOR S ACM COMPONENT f A1 LURE DiscRist0 IN THl3 REPORT 1931 "A ntP CAUSt SysttM COMPONENT MA AC- A ORtA E CAu$t SYSTEM COMPONENT g ,AC. yO y pp B AI B XlXIXIX XIXl XIX N I l t i I I I l' l I I I I I I I I I I I I SUPPLL4. INT AL MPORT EXPICTED 1941 l MONTH DAY YEAR SU9 Mis $ ION Yt$ II9 res, cometeen LK9ECTED SusMissION DA TL) kO l l l A ufRACT<t,- ,. ,,= .,.. . ~ . ,,,,, ,,,,,,,.. . ,, - ,.,,,,,,,,o.i On 9/20/89, with the Unit in Refueling (Operating Mode 6),

during an inspection of the Reactor Coolant System (RCS)

Pressurizer (PZR) Surge Line, in accordance with Inspection and Enforcement Bulletin 88-01, Engineering determined that the rupture restraint gaps were opened to greater than the original design analysis. The cause for this event was due to an j alignment performed during Hot Functional Testing which allowed  !

free thermal movement of the surge line due to the piping i movement caused by plant heatups and cooldowns. To correct this '

deficiency, a design change modification, which will readjust the restraint gap settings will be performed during the Seventh Refueling Outage. Additionally, administrative operational i limits have been placed on the temperature differential between .

I the PZR Surge Line and the RCS Hot Leg, to maintain this differential less than 200 degree Fahrenheit during the formation or collapsing of the steam bubble. There were minimal safety implications as a result of this event. In the event of .

a surge line rupture, the surge line restraints may not have  !

l contained the surge line. No other plant rupture restraints I were found to be affected.

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P spitC forsn SetA U.S. NUCLE A3 EtIULaf 0aY COMMW40fd UCENSEE EVENT REPORT (Lat., (EXT CBNTINUATION smovf o ous No. mo-oion

-6 e o EXPIRES: t/316 FACILITY esAME II) - DOCKET NUMBER (21 LIR NUMBER ($1 PAGE (31  !

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0l 0 0l2 0F 0l3 TEXT (# mee space 4 revueos, use esutemer Arec ,onn JeuW (171 DISQRIPTION .

On 9/20/89, with the Unit in Refueling (Operating Mode 6), an c inspection of the Reactor Coolant System (RCS) Pressurizer (PZR) ,

surge Line was performed, by Engineering personnel, in '

accordance with Nuclear Regulatory Commission (NRC) Inspection and Enforcement Bulletin (IEB) 88-01. Enginaering determined that the-rupture restraint gaps were opened to greater than the-original design analysis. This inspection also noted that the shear bars / lugs, which are installed for restraint shear loading concerns, were not installed, as stated in the original design.

This was done to account for thermal movement effects observed -

during Hot Functional Testing.

CAUSE OF THE EVENT The cause for this event was due to an alignment performed '

during Hot Functional Testing which allowed free thermal movement of the surge line, due 1.o the observed effects of

, thermal movement resulting from plant heatups and cooldowns. A verification of the PZR Surge Line restraint calculation, in response to IEB 88-01, discovered that the actual gaps settings I, were greater than the original design specifications, and that

! the shear bars / lugs were not installed. The cause for the j l removal of the shear bars / lugs could not be determined, but it is believed that the shear bars / lugs were not installed due to

bar distortion encountered during the welding of the bars to the j embedment. plate and the restraint baseplate. To eliminate the E bar distortion, the restraint baseplate was originally welded to the embedment plate.

l- CORRECTIVE ACTIONS To correct this deficiency, a design change modification, which will readjust the restraint gap settings will be performed during.the Seventh Refueling Outage. The shear bars / lugs will L also be installed, under this design change modification, to l' provide conformance with the original design. Additionally, administrative operational limits have been placed on the temperature differential between the PZR Surge Line and the RCS Hot Leg, to maintain this differential less than 200 degre Fahrenheit during the formation or collapsing of the steam bubble.

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' SAFETY IMPLICATIONS There were minimal safety implications as a result of this event. In-the event of'a surge line rupture, the surge line h.

restraints may not have contained the surge line.. No other p plant rupture restraints were found to be affected.

REPORTABILITY f This event was reported to the Nuclear Regulatory Commission, at 1531. hours on'9/20/89, in'accordance with 10 CFR 50.72.b.2.i.

This written. report is being' submitted in accordance with 10 CFR

, -50.73.a.2.li.B, as an event that is outside the design basis of the plant system.

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