ML18139B042

Responds to NRC 801117 Ltr Re Violations Noted in IE Insp Repts 50-280/80-34 & 50-281/80-37.Corrective Actions: Awareness of Specific Reporting Requirements Increased & Personnel Reinstructed on Requirements of 10CFR50.72(a)

ML18139B042
Person / Time
Site:	Surry
Issue date:	12/11/1980
From:	Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139B041	List: ML18139B042 ML18139B043
References
867A, NUDOCS 8102050330
Download: ML18139B042 (3)

Text

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RJ:CKHOND, Vi::HG:Dl J:.A. 23261 P 12  : 30 COMPANY December 11, 1980 Mr. James P. O'Reilly, Director Serial No. 867A Office of Inspection and Enforcement NO/RMT:ycf U.S. Nuclear Regulatory Commission Docket Nos. 50-280 Region II 50-281 101 Marietta Street, Suite 3100 License Nos. DPR-32 Atlanta, Georgia 30303 DPR-37

Dear Mr. O'Reilly:

In reference to our letter of November 17, 1980,. Serial No. 867, in which we provided responses to IE Inspection Report Nos. 50-280/80-34 and 50-281/80-37.

We are hereby forwarding the attached supplemental information.

Should you require any additional information, please contact this office.

Very truly yours, Manager - Nuclear Operations and Maintenance Attachment cc: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of licensing

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Attachment NRC COMMENT D. As required by 10 CFR 50. 72 (a) (6), personnel errors or procedural inadequacies which, during normal operations, anticipated operational occurrences, or accident conditions, prevents or could prevent, by itself, the

• fulfillment of the safety function of those structures, systems, and components important to safety, must be reported to the NRC Operations Center by telephone as soon as possible and in all cases within one hour of the occurrence.

Contraray to the above, when the main steam flow instrumentation was found to be inoperable at 12:30 a.m. on August 19, 1980, the NRC Operations Center was not notified within one hour.

This is a deficiency.

VEPCO RESPONSE The item is correct as stated.

Although this isolation "by itself" did not or could not prevent the ful-fillment of a safety function, this fact was not fully evaluated and documented at the time of the incident. Due to the installati_on of Integral Flow Restrictors while the Surry Unit 2 steam generators were being replaced, the break flow area for the steam break accident was reduced from 4.6 ft 2 to 1.4 ft 2

• This, along with the incident occurring early in core life assure that the FSAR licensing analysis results remain bounding with the main steam flow transmitters inoperable. Even though a thorough evaluation revealed that the one hour reporting requirement does not apply, it

• would have been prudent to have reported the incident promptly.

1. Corrective steps which have been taken and the results achieved:

Investigations leading to the development of supplemental information has led to an increased .awareness of the specific reporting require-ments.

2. Corrective steps taken to avoid further noncompliance:

All applicable personnel will be reinstructed on the reporting require-ments of 10CFR 50.72 (a).

3. The date when full compliance will be achieved:

Full compliance will be achieved before January 10, 1981.

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NOV l 9 198iJ VIRGINIA ELECTRIC AND POWER COMPANY R:IClDlOND,VJ::HGXNIA 23261

• November 17, 1980 Mr. James P. O'Reilly, Director Serial No. 867 Office of Inspection and Enforcement NO/FHT:ms U.S. Nuclear Regulatory Commission Docket Nos. 50-280 Region II 50-281 101 Marietta Street, Suite 3100 License Nos. DPR-32 Atlanta, Georgia 30303 DPR-37

Dear Mr. O'Reilly:

We have reviewed your letter of October 17, 1980 in reference to the*

inspection conducted at Surry Power Station on July 7 through 29, 1980, and reported in IE Inspection Report Nos. 50-280/80-34 and 50-281/80-37. Our responses to the specific infractions are attached.

We have determined that no proprietary information is contained in the reports. Accordingly, the Virginia Electric and Power Company has. no obj ec-tion to these inspection reports being made a matter of public disclosure.

Very truly yours,

. _al{!~

.i/7s'ylvia Manager - Nuclear Operations and Maintenance Attachment cc: Mr. Steven A. Varga, Chief Operating Reactors Branch No. 1 Division of Licensing