ML19332C053

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Notice of Violation from Insp on 891016-20.Violations Noted: Testing of Nuclear Svc Water Pumps Failed to Ensure Test Conditions Would Duplicate Conditions at Time Ref Values Determined
ML19332C053
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 11/16/1989
From: Julian C
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML19332C051 List:
References
50-324-89-38, 50-325-89-38, NUDOCS 8911220249
Download: ML19332C053 (2)


Text

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6-ENCLOSURE 1 NOTICE OF VIOLATION Carolina Power and Light Company Docket Nos. 50-325, 50-324 Brunswick.

License Nos. DPR-71, DPR-62 r

During the Nuclear Regulatory Commission (NRC) inspection conducted on

0ctober 15-20,.1989, violations of NRC requirements were identified.

In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1989), the violations are listed below:

A.

Technical Specificatior 4.0.5 requires inservice testing of ASME Code Class 1, 2, and 3 pumps and valves in accordance with Section XI of the -

ASME Boiler and Pressure Vessel Code and applicable Addenda. The licensee is connitted to inservice testing in accordance with the 1980 Edition of the Code and addenda through Winter of 1981.

Section XI, Subsection IWP-3000, requires pumps be tested by comparing mensured data to reference values which are to be at points of operation readily duplicated during. subsequent inservice testing.

Contrary to the above, testing of Nuclear Service Water Pumps A and B by periodic -test procedures 24.1-1 and 24.1-2 (Units 1 and 2 respectively).

Service Water Pump and Discharge Valve Operability Test, failed to ensure test conditions would duplicate conditions at the time the reference values were determined.

Such conditions include. pump flow and boundary valve leakage.

This is a Severity Level IV violation (Supplement I).

B.-

10 CFR 50 Appendix B, Criterion III, and the licensee's accepted QA Program, section 17.2 of the FSAR require establishing measures to assure that applicable regulatory requirements and the design basis are correctly translated into specifications, drawings, procedures, and instructions.

Contrary to the above, design change package, modification number 82-219 specified a motor-operated valve closing limit switch setting of 4 percent for (Jamesbury valves) nuclear service water valves ISW-18, ISW-118 ISW-102, 1

and 2SW-111. The Jamesbury valve technical manual requirea that the closing limit switch have a setting of 1 percent.

This is a Severity Level V violation (Supplement I).

8911220249 891116 PDR ADOCK 05000324 Q

PDC 1

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-c Carolina Power and Light Company 2

Docket Nos. 50-325, 50-324 Brunswick License Nos. DPR-71, DPR '

Corrective' actions for the violations addressed in this Notice were described required.

Therefore, no reply to the Notice is in your letter of September 27, 1989.-

i FOR THE NUCLEAR REGULATORY COMMISSION

[4 Caudie A. Julian, Chief-Engineering Branch Division of Reactor Safety i

Dated at' Atlanta, Georgia

-this -16tWay.of November 1989 r

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