ML19276H273
| ML19276H273 | |
| Person / Time | |
|---|---|
| Site: | Crane  |
| Issue date: | 09/03/1975 |
| From: | George H Office of Nuclear Reactor Regulation |
| To: | Vollmer R Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 7910160620 | |
| Download: ML19276H273 (2) | |
Text
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9 SEP 3 1975 Richard II. Vollmer, Chief, Quality Assurance Ercach, EL 2 RIP REPORT - li. GEORCE'S VISIT T0 '"HREE }!ILE ISLAND 1, JULY 21-23, 197 3 Purcose The purpose of the trip vac to review the QA progrn= inpleaentation at Three lille Island 1 in conjunction with liRC - I2 Region I personnel. The I&E personnel were R. Glasscock, A. Fasaca, J. Snith, and *I.
Ruhluan. At the tir.c of the visit, the plant was operating at 100! power.
Ot>servations The inspection consisted of procedure and record examinations, personnel interviews, and observations of work performance.
Ibe areas covered in this review included document control, purbhasing, control of maintenance and ex>dification e.ctivitics, surveillanca procedures, control of nonconforcunces, and audits.
The noncompliances and unresolved iters identified in this inspection were relatively minorsin nature; for details on these items, see I&E inspection report No. 75-14. ThA significant observations relevant to EC licensing, but not discussed in the I&E inspection report are as follows:
The QC stalf at the plant is quite large (9 individuals plus a.
the QC Supervisor). QC is aciively involved in plant activities, including audits, review of all caintenance and modification work requests and procedures, insertion of hold points for witnessing or performance of inspuetion by QC, and preparation of work requests and review of reports for NDE services, all of which are enntracted for.
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W. Ruhinan pointed out that Regulatory Guide 1.71, " Welder Qualification for Areas of Limited Accessibility," was not included in the published version of the Standard Review Plan (SRP).
It has since been learned that a revision to the SRP will include this Regulatory Guide.
It was noted that I&E was not inspecting directly against the c.
FSAR.
The FSAR was used as a supplementary docu:nent, and a refercnce ti, cite against. The inspection was actually performed using check 1tsts prepared from the criteria contained in the I&E Reactor Inspection Progra:a Precedures.
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of approach should not cause a problem, provided that the I;E inspection criteria are cor,istent *:ith the criteria in the S'J, section 17.2.
In addition, the chechsheet used by ISE to perfort the recic'i of a utility's QA Manual should be consistent with the criteria in the S?2.
Reccmmendation It is reco= mended that a conparison betvcen the N'tC Regulatory SRP, Section 17.2, and the I&E Reactor Inspection Program-Operations Phasa (MC-2515) be made, and conflicts or & missions resolved; and, a comparison between the ISE QA Manual inspection chechhheet and the SRP also be made.
Original signed byi U. George Quality Assurance Eranch Division of Reactor Licensing cc:
D. Skovholt QAB DISTRIBUTIO_N Central Files QA Reading hu Reading HGeorge JGilray AGarland RVollmer 1419 102 1
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9/3/75 9/3[75h Form AIC-31s (Rev. 9-53) AECM 0243
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