ML19325E165

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Documents 891011 Telcon Re Visual Insp of Safety Injection Accumulator Discharge Check Valve SI-50.Anchor-Darling Svc Representative & QC Inspector Performed Insp on 891005 for Installation of New Studs,Per NRC Bulletin 89-002
ML19325E165
Person / Time
Site: Beaver Valley
Issue date: 10/19/1989
From: Sieber J
DUQUESNE LIGHT CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
IEB-89-002, IEB-89-2, NUDOCS 8911020153
Download: ML19325E165 (1)


Text

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., )U gegyw Powe staan shmnoport a nonao4 b

t October 19, 1989 EOhi,n,w mmmw U.

S.

Nuclear Regulatory Commission Attn:

Document Control Desk Washington, DC 20555

Reference:

Beaver Valley Power Station, Unit NO. 1 Docket No. 50-334, License No. DPR-66 Visual Examination of SI-50 Gentlemen:

e The purpose of this letter is to document a telephone conversation between Mr. K.

D. Grada of my staff and Mr.

G. Johnson of the NRC Staff on October 11,

.989 concerning a

visual inspection of a

safety.

injection accumulator discharge check valve (SI-50).

On' October 5,

~

1989, inspection and maintenance was being performed on SI-50 to e

install' new retaining block studs as part of our actions to address NRC Bulletin 89-02.

The inspection was performed by an Anchor Darling Service. Representative and a

Quality Control (QC)

Inspector. 'The following items were checked during the vendor and QC inspection on the valve:

clapper arm shaft and bushings, retaining block dowel' pins and

bushings, trunnion
bushing, disc nut
pin, disc nut, valve disc and
seat, and the body to bonnet and seal plate sealing surfaces.

The valve and internals were found to be satisfactory.

An ASME Section XI Table 2500, B-M-2, VT-3 visual examination of the internal valve body was required.to be performed during maintenance on this valve as part of an alternate examination approved by NRC l

letter dated November 30, 1987.

The Quality Control Inspector and l

vendor representative were not qualified in.accordance with ASME IWA-2300 to perform a VT-3 visual examination.

Duquesne Light Company believes the intent of the alternate l

examination was met since the valve was inspected by a representative of the valve manufacturer, five. (E )'-

identical valves uere also inspected by an ASME IWA-2300 qualified inspector with satisfactory

results, ASME Table
2500, B-M-2, limits the examination to one valve within each group of valves that are the same constructional design, and re-inspection will result in unnecessary radiation exposure.

If there are any questions concerning this matter, please contact my office.

Very truly.yours,.

5 i

8911020153 891019 i.

D. Sieber PDR ADOCK 05000334 i vice president D

G PNU Nuclear Group cc:

Mr..J..Beall, Sr. Resident Inspector

,gg Mr. W.

T.

Russell, NRC Region I Administrator L-Mr. P. Tam, Sr. Project Manager i

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