ML19259C639
| ML19259C639 | |
| Person / Time | |
|---|---|
| Site: | Marble Hill |
| Issue date: | 05/19/1979 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19259C638 | List: |
| References | |
| 50-546-79-04, 50-546-79-4, 50-547-79-04, 50-547-79-4, NUDOCS 7908070319 | |
| Download: ML19259C639 (4) | |
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Appendix A NOTICE OF VIOLATION Public Service of Indiana Docket No. 50-546 Docket No. 50-547 Based on the results of an NRC inspection conducted on April 30 -
May 3,1979, it appears that certain of your activities were not conducted in full compliance with NRC requirements as noted below.
Item I is a deficiency, Items 2, 3 and 4 are infractions.
1.
10 CFR 50.55(e), Conditions of Construction Permit, requires the holder of the permit to notify the Commission of each deficiency found in design and construction, which, were it to have remained uncorrected, could have affected, adversely, the safety of operations of the nuclear power plant at any time throughout the expected lifetime of the plant and which represents
.. a significant deficiency in construction of or significant damage to a structure, system or component whicb will require extensive evaluation, extensive redesign, or extensive repair.
In addition, the holder of a construction permit shall within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> notify the appro-priate Nuclear Regulatory Commission Inspection and Enforcement Regional Office of each reportable deficiency.
Public Service of Indiana, Quality Assurance Procedure (QAP) 6.12, Revision 18, applies during the design, procurement, construction, and testing phases of the Marble Hill Generating Station to ascertain if any deviations are reportable under the requirements of 10 CFR 50.55(e). QAP 6.12, Section 4.2 states, in part, " Managers and Supervisors associated with the nuclear generatica facility are responsible for promptly notifying a Safety Review Committee (SRC) member of any conditions adverse or potentially adverse to the safety aspects concerning design, procurement, systems, construc-tions and testing of the nuclear facility." Section 4.5 states, in part, "It will be the responsibility of the SRC after it has classified the deviation or a significant deficiency or safety hazard to report their recommendations for reporting to the NRC as promptly as possible, to the Vice President - Nuclear or his designated representative for notifying the NRC.",
Contrary to the above, the following two construction deficiencies were not handled in an expeditious manner nor is the governing QA procedure sufficiently specific to permit compliance with the prompt reporting requirements of 10 CFR 50.55(e).
2100 333 7908070M..
Appendix A NCR No. 325 relative to damaged prestressing system trumplates a.
due to excessive heat was identified by the licensee contractor on February 12, 1979.
Site quality assurance group did not inform the PSI SRC to requcst evaluation for reportability to the NRC until April 9, 1979. Subsequent to this request, the NRC was not notified until April 19, 1979.
b.
NCR No. 105 relative to excessive concrete pour rate on the Unit I containment liner was identified by the licensee contractor on February 13, 1979. Site quality assurance did not properly inform the PSI SRC until April 10, 1979.
Minutes of the SRC meeting on April 16, 1079, indicate a decision regarding reportability to the NRC could not be made until more information was available. The NRC had not been notified of this as of the date of this inspection.
Concrete backfill material on the exterior of the containment has been subsequently placed thus not permitting direct inspection of the subject area.
2.
10 CFR 50, Appendix B, Criterion X, requires that a progrsm for inspection of activities affecting quality shall be established and executed by or for the organization performing the activity to verify conformance with the documented isstructions, procedures and drawings for accomplishing the activ.ty.
The Marble Pill PSAR, Chapter 17.0, Section 17.1.10.1.(b) requires that, " Inspections or tests are performed for each work operation as necessary to verify quality."
Contrary to the above, immediately prior to concrete placement, the NRC inspector observed the following specific conditions adverse to quality which had not been corrected in two concrete pour areas which had been inspected and released for concrete placement by responsible QA/QC personnel, At least 12 reinforcing steel shear ties which had not been a.
properly secured.
b.
Loose wood pieces, tie wire, duct tape, and other general construction debris.
c.
Standing water.
d.
Embedded wood in a horizontal construction joint within the pcur area.
e.
Unacceptable cleanliness of formwork.
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Appendix A 3.
10 CFR 50, Appendix B, Criterion XVI, requires that measures shall be established to assure that conditions adverse to quality are promptly identified and corrected.
The Marble Hill PSAR, Chapter 17.0, Section ?.7.1.2.3 states that it is PSI's objective to comply with the Industry Standard ANSI N45.2-1971. ANSI N45.2-1971, Section 17 states that,
" Measures shall be established... to assure that conditions adverse to quality.... are promptly identified and corrected.....
Contrary to the above, on April 30 and May 1 - 3, 1979, the inspector, wah licensee personnel present, observed that curing of the Unit I containment wall ICW-Ext. 6 was not being performed in accordance with Sargent & Lundy Specification Y-2722 and Newberg WPN-9, Rev. 8, Section 4.8.
This lift of the containment wall was placed April 27, 1979 and was required to be properly cured for seven days.
The inspector was unable to verify that adequate corrective action to assure proper curing of containment wall ICW-Ext. 6 was taken at any time during this inspection.
4.
10 CFR 50, Appendi,c B, Criterion VI states, in part:
" Measures shall be established to control the issuance of documents which prescribe all activities affecting quality. These measures shall assure that documents.
. are distributed to and used at the location where the prescribed activity is performed.
Paragraph 17.1.6.1 of the Marble Hill Preliminary Safety Analysis Report states, in part:
" PSI procedures establish requirements for document control which include the following:
. d) Approved changes... are promptly issued.
f)
Documents are distributed promptly to ensure availability prior to commencement of work for which they are needed."
Paragraph 4.3.1 of PSI Quality Assurance Procedure (QAP) 4.1,
" Site Document Control," Rev. 7, dated May 28, 1976, states, in part: " Drawings, specifications, and other documents describing activities.
. affecting quality shall be distri-buted to organizations performing the work affecting nuclear safety (usually contractors) by the Site Document Controller 2100 335
Appendix A Contrary to the above, the Site Document Controller was unaware of the requirements of paragraph 4.3.1, QAP 4.1 and was not controlling the distribution of specifications to site contractors.
Two different revisions of S&L specificat. ion Y-2722 " Concrete Structures and Site work," were observed in use at the U.S. Testing Company site laboratory neither of which were the current issue.
In additioo, the copy in the Newberg Marble Hill QA Supervisor's office was also not current, although Newberg Marble Hill is the principal contractor for S&L Specification Y-2722.
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