ML20202B175

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Pressure Testing Program for Third Ten-Yr Interval at Bvps,Unit 1, & Second Ten-Yr Interval at Bvps,Unit 2, Relief Request BV3-IWA-1,Rev 1, Re Insulation Removal for Class 1 & 2 Bolted Connections
ML20202B175
Person / Time
Site: Beaver Valley
Issue date: 10/03/1997
From: Legrand R
DUQUESNE LIGHT CO.
To:
Shared Package
ML20202A937 List:
References
NUDOCS 9712030070
Download: ML20202B175 (2)


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PRESSURE TESTING PROGRAM AT BVPS UNIT 81, FOR "I1E THIRD TEN YEAR INTERVAL AND BVP2 UNIT #2, FOR THE SECOND TEN YEAR INTERVAL RELIEF REQUEST BV3-lWA 1, REY.1

SUBJECT:

lasulation Reanovel for Class I and 2 bolted connecticas Prepared by: d / 9Dh -

L 'c: b- \5-9 7 Supeniso'r, Nuclear Programs Rniewed by: Date: 7!??97 Director, Design Basis F# gin 6ering Resiewed by: Date:

ANII [/

Rniewed by: ._BV OSC- 36-97 Date: Cf ho /c(7 osC Reviewtd by: Rtvttw (Acue e. for Mccbh4 J7-4 C Date: %bI ORC Approval by: 'k .* A 4

-._ Date: /O - l N Div. VP, Nuclear Operations / Plant Minager 9712030070 971124" gDR ADOCK O g4

6 ,

DUQUESNE LIOfff COMPANY Besver Vaney Power Stataan Unit Nos. I and 2 RELIEF REOUEST NO. BY3-IWA 1 Rev.1 COMPONENT Class I and 2 bohed nama=+ha in systems horated for the pwpose of controlling reactMty ASME SECTION XI REOUIREMENT (39 Editlan)

Examinadon Categories B P of Table IWB 2$001 and C H of Table IWC 2$001 require visual, VT 2 examination of au presswe retaining components during pressum tesdag. IWA $242(a) regwres insuladon reasoval hom hohed aaaaar*ha for the visual VT 2 ===1ameia= La syssoms borened for the pwpose of controlling reacdvity.

BASIS OF RELIEF in accordance with 10CFR$0.S$a(sX3Xii) reliefis requested from ASME Section XI,1989 Edition,IWA 3242(a).

IWA 3242(a) requires that for systems borated for the pwpose of control 11ag reactivity, lamitath shnu be renoved from presswe retaining bolting for visual namianah VT 2. r'ampilaare with this Code requirement would result in hardship and unuseal dSculty wit; ge' a compensating increase in the level of quality and safety, based on the following:

1. Code Class I and 2 systems borate i for the pr . pose of centmtling reactivity are large systems covenng many areas and elevations of the reassor.am.,' w at building. Many of the bohed aaaaareiana are located in areas d2 cult to access and have significa:e imian levels. Scaffolding is required to access the sudority of the bolted connections As required by IWB 5221, the System Lankage Test is aaadaread at normal operating presswe and temperatwe The visual, VT 2 examination is perforined prior to plant startup at mode 3. This examination is a critical path activity and normnHy has a short dwation of approximately 4 to 6 hows. To delay reactor criticality due to lassaltatian ofinmilariaa and disassembly and removal of scaffoldmg under sub -

atmospheric conditions is an undue burden without a compensadng increase in the level of quality and safety.

Outage durations and costs will be significantly increased and H..c .2: safety will be impacted under these operating conditions.

2. Leakage of borated water will leave a residue of boron. Boron residue is evidence ofleakage cond inconsequential to whether the syssem piping is under presswe or not at the time of the usual VT 2 examination.

PROPOSED ALTERNATIVE EXAMINATION A visual, VT 2 an=laasian wiu be perfonned during the system presswe tests ofIWB 5000 and IWC-$000 with the inanimeh installed. In addition, insulation will be rennoved hose all Class I bolted nannarviana each refueling outage and host all Class 2 bolting connections on a h,u y of.,,, gF 7 3 and 1/3 years (nory other refueling outags, but not to exceed once per period), when the Code r-~%a*. regarding inantatian remm31 (IWA 5242), is not enet. A visual VT 2 exandantion shall be p.Ln i with the inulation removed, for evidence ofleakage (boric acid residue)indtradam of the system pressure test.

Duquesne Light requests NRC approval of the proposed ahernatiw requirements for VT 2 visual examination of Class I and 2 insulated presswe retaining bohad an==ar+Aaan in lieu of those of IWA-5242(a). NRC approval is

requested in a time hame that will support implamentarian of the ahernauve requirements for the Unit ! tweihh refueling outage currently scheduled to begin in hraamhw of 1997. Unk i twelAh reibeling outage will be the first outage of the third ten year interval at Sleever Valley Power Station Unk No.1. '!he manand ten year interval at Beaver Valley Power Station Unit No. 2 will begin November 17,1997, 4 -

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