ML19308C733

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Notice of Violation from Insp During Oct 1979
ML19308C733
Person / Time
Site: South Texas  STP Nuclear Operating Company icon.png
Issue date: 12/12/1979
From:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
To:
Shared Package
ML19308C730 List:
References
50-498-79-16, 50-499-79-16, NUDOCS 8002010215
Download: ML19308C733 (2)


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Docket No. 50-498/79-16 50-499/79-16 Appendix A NOTICE OF VIOLATION Based on the results of the NRC it.spection conducted during the period of October 1979, it appears that certain of your activities were not conducted in full compliance with the conditions of your NRC Construction Permits No. CPPR 128 and CPPR-129 as indicated below:

F,ilure to Include Appropriate Quantitative or Qualitative Acceptance Criteria in Instructions, Procedures, or Drawings Criterion V of 10 CFR 50, Appendix B, states in part, " Instructions, procedures or drawings shall include appropriate quantitative or quali-tative acceptance criteria for determining that important activities have been satisfactorily accomplished."

Brown & Root (B&R) Specification 2A010CS028-C, paragraph 6.1.1.1,

" Construction Joint Preparation" states, "The surface of all construction joints shall be saturated for 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or as required in order that the concrete surfaces immediately prior to placement is in a saturated surface dry (SSD) condition unless otherwise approved by the Design Engineer." Paragraph 3.2.8, " Placement Preparation," states, "No excessive amounts of free standing water or foreign material which would reduce the quality of the concrete shall be present in the placement or on the surface on which concrete is to be placed."

Quality Construction Procedure CCP-3, Revision 11, paragraph 3.3.1 states, "The individual engineer and/or supervisor who performs the prepour inspection will assure conformation to plans and specifi-cations.... The inspection will be performed by the B&R construc-tion craft supervisor (foreman, general foreman or superintendent) and by the B&R Senior Discipline Engineer or his representative and by the respective discipline Quality Control Inspectors." Para-graph 3.3.3(2) states " Assure that all surfaces are wetted and no significant amount of free water remains."

Contrary to the above:

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On September 17, 1979, the Resident Rea tor Inspector- (RRI) observed the placement of Pour No. CS2-W, a port.on of the Reactor Building Containment wall.

Final inspection had been performed prior to the pour by individuals responsible for the inspection, however, the RRI found excessive free standing water on the prepared joint between Az 240 - 311. Closer examination revealed a significant 80'02014 b

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.1 amount of water (k to inch deep over an area 4' (wall thick-ness) x 8-10' (portion of the circumference). Water at this location was entrapped.

Subsequently, the water was removed by soaking rags after blowing with air failed to remove the water.

A small puddle of water 1-3" deep x 12". diameter was also entrapped at Az 245" between the main steam penetration.

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The RRI also determined that the specifications ~and procedures failed to give quantitative or qualitative acceptance criteria to define what constitutes the saturated surface dry (SSD) con-dition. The specification or procedures do not define " excessive" or "significant" in regard to amounts of free standing water and accordingly free standing water is not limited.

This is an infraction.

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