ML20005F340

LER 89-010-01:on 890920,determined That Estimated Leakage for Main Steam Line Containment Penetrations a & B Exceeded Tech Spec Limit During Local Leak Rate Testing.Cause Not Determined.Msiv Poppet Seats & Discs lapped.W/900104 Ltr

ML20005F340
Person / Time
Site:	Susquehanna
Issue date:	01/04/1990
From:	Byram R, Rusanowsky P PENNSYLVANIA POWER & LIGHT CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
LER-89-010, LER-89-10, PLAS-403, NUDOCS 9001160196
Download: ML20005F340 (6)

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,7 Q Pennsylvania Power & Light Company--

Two North Ninth Street + .Allentown, PA 18101 + 21517705151 January 4, 1990 U.S. Nuclear Regulatory Cm mission Document Control' Desk

' Washington, DC 20555 L-SUSQUDIANNA STEAM ELECTRIC STATION .

LICENSEE EVDfP REPORP 89-010-01

?. FILE R41-2 b PIAS - 403 Docket No.:50-388:

License No. NPF-22 89-010-01. This' event was-

-l:AttachedissupplementalLicenseeEventReport determined:to be reportable per 10CFR50.73(a) (2) (ii) in that the Main Steam Line penetrations had exhibited leak rates in excess of.the Technical Specification limit during regularly scheduled Local Leak Rate Testing..

.G. am Superintendent of Plant - Susquehanna PPR/mjm 7 cc: Mr. W.T. Russell

' Regional Administrator, Region I U.S. . Nuclear Regulatory Cmmission 475'Allendale Road King of Prussia, PA 19406

'Mr. G.S. Barber Sr. Resident Inspector U.S. Nuclear Regulatory Cmmission P.O. Box 35 Berwick, PA 18603-0035 I

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90.73telGHvsnH Al Js6At to 4004eH1Hevi g 6033mlGHet 0034tel43Hvanti 30.40steH1Hvl to13telGHed) to 73teH3Het LICENStt CONTACT FOR THl8 LER (135 NAME TittPHONE NUM9tm Amt A COOS P.Pe Rusanowsky - Power Production Engineer, Chupliance 7l1 i 7 5i 4l2 i i 3i7i Si9 COMPLETE ONS LINE FOR B ACM COMPONENT # AILunt ogsCRiet0 IN TH16 REPORT (13p CAUSE SYSTEM COMPONENT CRTa 5 Uh $C- R{0NPR g CAU$t avsTEM COMPONENT "fyTg$0' "fgqpng X SBi lIt Si V A 1 5;8;5 Y i 1 i i i i i l l l I l l f I l ! I I I f SUPPLiutNTAL REPORT EMPECTIO tiet MONTa DAY vtAR SUOMISSION l Yt$ 119 res cemeiere 4x9tCTiO SUO40t$$ TON OATil NO l l l A80TR ACT ILimot te 9000 soeces i e segressmerety 9r9 teen po,ie sonce troewroten knest (168 On 9/20/89, with Unit 2 in its third refueling and inspection outage, evaluation of the data fran regularly scheduled Local Ioak Rate Tests (LIRrs) concluded that the estimated leakage for the "A" and "B" Main Steam Line (MSL) containment penetrations were in excess of the Technical Specification limit for total MSL penetration leakage of 46 standard cubic feet per hour (scfh).

Further testing determined the leak rates to be 356 scfh and 635 scfh, respectively. Several Main Steam Line Isolations Valves (MSIVs) were reworked l and post maintenance LIRTs were performed on the applicable MSL penetrations with satisfactory results. Total MSL penetration leakage was reduced to 32.6 scfh. This event was determined to be reportable under 10CPR50.73(a) (2) (ii) in that containment penetrations had exhibited leak rates in excess of their Technical Specification limit. No definitive cause(s) could be ascertained for the high initial leak rates. An asseset of the safety consequences associated with this event is being performed by Nuclear Plant Engineering.

Based on conclusions in NUREG 1169 (An Evaluation of BWR MSIV Irakage and the l Effectiveness of Icakage Treatstent Methods) concerning public exposure due to l MSIV Ieakage, it is anticipated that the results of this assessnent will conclude that the consequences to the health and safety of the public were minimal.' If these findings are not confirmed, a supplement to this Licensee l Event Report will be issued.

- NRC Perm 350 (H91

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0l1 0l 2 or 0l5 EVPRP On 9/17/89, with Unit 2 in its third refueling and inspection outage, rectlarly scheduled incal Icak Rate Testing (LIRr) of the Main Steam Line (MSL; EIIS Code: SB) penetrations was carmenced.

On 9/19/89, it was suspected that the leak rates of the "A" and "B" MSL penetrations were above the Technical Specification (Tech Spec) limit for total FEL penetration leakage of 46 standard cubic feet per hour (sefh) .

On 9/20/89, evaluation of the LIRr data established that the estimted leakage l for the "A" and "B" MSL penetrations were in excess of 53 sefh and 318 scfh, respectively. he "D" MSL penetration leakage was concluded to be low based on evidence of minim 1 leakage past the "D" Inb3ard (INBD) Main Steam Line Isolation Valve (MSIV), IN-241F022D, but couldn't be gaantified due to excessive Inakage past the "D" Outboard (OLTrBD) MSIV, IN-241F028D. The leakage for the "C" MSL penetration was detemined to be approximtely 1.5 scfh. The condition was determined to be reportable and a phone call via the Pergency Notj fication Systan was made at 1115 in accordance with 10CPR50.72.

On 9/21/89, additional testing to nore accuratelv quantify the "A" and "B" FEL penetration leak rates was completed. The msults vem 356 scfh and 635 ncfh, respectively.

On 9/21/89, the "B" MSL rienetration leakage was reduced to 1.5 scfh by stmking the "B" OltrBD MSIV,IIV-241F028B.

On 10/13/89, the "D" MSL penetration was retested after the "D" OlfrBD MSIV was reworked. Penetration leakage both before and after rework of the "D" OtfrBD MSIV was detemined to be approximately 0.1 scfh.

On 10/14/89, the "A" MSL penetration was retested after the "A" INBD MSIV, IN-241F022A, was reworked.- Penetration leakage was detemined to be 30.3 scfh.

On 11/03/89, the Primry Containmnt (EIIS Coder Nil) Integrated Icak Rate Test (ILRT) was conducted. The initial leak rate was 3629 scfh which exceeded the Tech Spec 3.6.1.2.a limit of 504 sefh. The "B" MSL was detemined to be the major source of leakage. The IIRr leak rate was reduced to an acceptable level of 202 scfh by stroking the "B" OITrBD MSIV.

On 11/06/89, based on the evidence revealed during the performnce of the ITRT and in accordance with 10CPR50 Appendix J, the "B" MSL penetratien was retested l and leakage  %

was detemined to be in excess of 200 scfh.

1 l On 11/13/89, the "B" MSL penetration was retested after the "B" INBD and OtfrBD l MSIVs were reworked. Penetration leakage was determined to be 0.7 scfh.

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O ll 0 13 0F 0 15 Tor a summary of the leak rate test results and associated activitics, see the attachcx1 LVDE SLMARY table.

CORPJXJTIVE ACTIONS As reported in the LVDTP section, four MSIVs were disassembled, their main and poppet seats and discs were lapped, and post maintenance IlRrs were performd with satisfactory results. Total !GL penetration leakage was reduced to 32.6 scfh.

3LV2S RDORKED "D" OLTTBD MSIV (IN-241F028D)

"A" INBD MSIV (!!V-241F022A)

"B" INBD MSIV (!!V-241F022B)

"B" OLTrBD MSIV (IN-241P028B)

• liad no effect on MSL penetration leakage due to miniml leakage exhibitr<1 by the "D" INBD MSIV (IIV-241F022D).

.CAUS3 Initial inspections of the MSIVs that were disassmbled did not reveal any significant flaws that would offer definitive causes(s) for the high initial leak rates. This is not an tracamnn ananaly when reworking MSIVs.

A thorough review was conducted in an attempt to explain the inconsistent leakage demnstrated by the "B" MSL penetration. No definitive cause(s) could be ascertained.

RETORTABILITY/ ANALYSIS

'Ihis event was detemined to M reportable under 10CFR50.73(a) (2) (ii) in that MSL containment penetrations had exhibited a leak rate in excess of the Tech Spec limit. An assesment of the safety consequences associated with this event is being performed by Nuclear Plant Engineering. Based on conclusinns in NUREG 1169 (An Evaluation of BWR MSIV Inahage and the Effectiveness of Inakace Treatunnt Methods) concerning public exposure due to MSIV leakage, it is anticipated that the results of this assessment will conclude that the consequences to the health and safety of the public were minim 1. If these findings are not confirmd, a supplemnt to this Licensee Event Rernrt will be issued.

Details bf the Primary Containment IIRT perfomed on 11/03/89 will be reported in accordance with 10CFR50 Appendix J.

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0l1l0 --l 011 0l 4 or 0l5 ADDITIOl%L IhTOPMATION Past Similar Licensoo Event RWst LER 86-007-00 Although detennined not to be reportable events, the following internal ,

Significant Operating Occurrence Reports (S00R'n) concerning MSIV leak rates have been incued:

S00R 1-83,140 ST)R 1-87-338 '

SOOR 2-88-045 )

SOOR 1-89-146 Failed Conponent Identification: MSIVs  !

Manufacturer: Atwood and Morrill Co., Inc.  ;

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i iTAKAGE (sefh)  :

MSL INITIAL TOST (a) POST (b) FINAL (c) i (9/21/89)' (10/14/89) (11/06/89) (11/13/89)  !

I 30.3 A 356 (30.3) (30.3) a 635 1.5 > 211 0.7 C a 1.5 1.1 (1.1) (1.1) l 0 0.1 0.1 (0.1) (0,1) )

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'KYTAL 992.6 33.0 > 242.5 32.2 (a) "B" OtfTBD MSIV STROKED "D" OlTTBD MSIV RDORKED "A" INBD MSIV RDORKED i

(b) "B" MSL RT' TESTED hased on ILRT data l

(c) "B" INRD MSIV RDORKED "B" OlTTBD MSIV RDORKED l IUTE(1) : Inak rates in (parentheses) wera determined by a previous test (i.e.

not the results of a retest) .

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l IUTE(2) : Tech Spec 3.6.1.2.c leak rate limit for all four main steam lines

cmbined is 46 scfh.

j IUTE(3) : Tech Spec 3.6.1.2.a leak rate limit for the primary containment ILTU' l is 504 scfh.

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( IUTE(4) : All MSIVs were stroked numerous tims during the tim period

'- associated with this event in support of various outage activities.

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