ML19345G211

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Responds to NRC Re Violations Noted in IE Insp Rept 50-369/80-32.Corrective Actions:Test Coordinator Counseled on Importance of Documenting Variance from Procedures
ML19345G211
Person / Time
Site: McGuire 
Issue date: 02/06/1981
From: Parker W
DUKE POWER CO.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19345G210 List:
References
NUDOCS 8103170081
Download: ML19345G211 (2)


Text

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DUKE POWEld COMPANY,,,

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Powen Butt.niwo 422 Socru Cucacu Srazzi, Czuntorre, N. C. 28a42 a

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February 6, 1981

%cr Det$1 DENT TE L EP=so m t:Anta 704 Strano f ooOuCTION 373-4083 Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission Region II 101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 Re: RII:TJD 50-369/80-32 De u Mr. O'Reilly:

Please find attached a response to Infraction No. 80-32-02 and Deficiency No. 80-32-01 which were identified in the above referenced Inspection Report.

Duke Power Company does not consider any information contained in this inspection report to be proprietary.

Ve truly yours,

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William'O. Parker, Jr.

.i RWO:sco Attachment-l 810 3170 Old

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MCGUIRE NUCLEAR STATION RESPONSE TO IE INSPECTION REPORT 50-369/80-32 A.

As required by 10CFR 50, Appendix B, Criterion V, activities affecting quality shall be prescribed by documented instructions.

. and shall be accomplished in accordance with these instructions.

The accepted QA program (Duke 1-A), Section 17.2.5 requires that with regard to specific operational activities associated with nuclear safety-related structures, systems, and components, it is required that such activities be accom-plished in accordance with procedures.

. appropriate to the nature of the activities being performed. Administrative Policy Manual (APM)

Section 4.2.4.1 requires that major changes (other than typographical or editorial) be documented.

TP/1/A/1250/05, Main Steam Safety Valve Set-point Test, Prerequisite 8.2, requires main steam header pressure to ba 955 1 35 psig.

Contrary to the above, for the testing in July, 1980 of 11 of 20 main steam safety valves, main steam header pressure ranged from 1005 to 1025 psig and no change was submitted to TP/1/A/1250/05 as required by APM, Section 4.2.4.1.

Response

The increase of the main steam header pressure noted above was done upon the recommendation of a vendor representative assisting with the perfor-mance of the test.

The test coordinator felt a procedure change was un-necessary since the prerequisite had been met prior to the test and the increase in pressure actually enhanced the significance of the test.

The test coordinator in question has been counseled on the importance of documenting any variance from a test procedure.

B.

As required by 10CFR 50,.Appendir B, Criterion XI test results shall be documented and evaluated to assure that test requirements have been satis-fied.

The accepted QA program (Duke-1-A) Section 17.2.11 states that requirements are also established for verification of test completion and for determining acceptability of test results.

Contrary to the above, preoperational test, TP/1/A/1250/05, Main Steam Safety Valve Setpoint Test, performed in July, 1980 did not have an accept-able verification of test results in that the test was performed at a pres-sure of 1005 psig to 1025 psig while prerequisite 8.2 required a pressure of 955 i psig and the test was signed off as being completed and acceptable by the test coordinator and the maintenance supervisor.

Response

The reasons for the procedure in question passing through the review pro-cess without the discrepancy being noted are the same as stated in the response to Item A.

The maintenance superintendent was also cognizant of the vendors representative's reccmmendation.

A memorandum documenting the circumstances discussed above has been added to TP/1/A/1250/05.

It is felt this is an isolated incident and no program changes are necessary.