ML19309E491
| ML19309E491 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 04/18/1980 |
| From: | Sylvia B VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| References | |
| NUDOCS 8004220493 | |
| Download: ML19309E491 (3) | |
Text
L VrnorxrA ELECTHrc AND 180WHH CO M PANY RrcarMown Vzmorn zA 20201 April 18, 1980 Mr. James P. O'Reilly, Director Serial No. 305/032680 Office of Inspection and Enforcement P0/RMT:baw U. S. Nuclear Regulatory Commission Docket Nos. 50-338 Region II 50-339 101 Marietta Street, Suite 3100 License Nos. NPF-4 Atlanta, Georgia 30303 NPF-7
Dear Mr. O'Reilly:
We have reviewed your letter of March 26, 1980, in reference to the inspection conducted at North Anna Power Station on February 4-19 and February 25-29, 1980, and reported in IE Inspection Report Nos. 50-338/80-11 L
and 50-339/80-09. Our response to the specific infraction is attached.
We have determined that no proprietary information is contained in the reports. Accordingly, the Virginia Electric and Power Company has no objection to these inspection reports being made a matter of public disclosure.
Very truly yours, Q
i B. R.
ylvia Manager-Nuclear Operations and Maintenance Attachment v
cc:
Mr. Albert Schwancer 1
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Attachment, prga 1 Response to Notice of Violation Item Reported in IE Inspection Report No.
50-338/80-11 and No. 50-339/80-9 NRC Comment
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As required by Unit 1 Technical Specification 6.5.1.6.b, the Station Nuclear _
Safety and Operating Committee (SNSOC) shall review all proposed tests and experiments which affect nuclear safety.
Contrary to the above, a test involving " perking" of a main steam line non-return valve to determine if this was the source of loose parts indications on February 23, 1980, was not reviewed by the SNSOC prior to conduct. The test resulted in a safety injection actuation.
This is an infraction.
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RESPONSE
I The above infraction is correct as stated.
Specifically, pursuant to section 2.201 of the NRC's " Rules of Practice" Part 2, Title 10, Code of Federal Regulations, the following information is submitted:
1.
Corrective steps taken and results achieved:
A review was made of the test method used to perk the main steam line non-return valve. This review determined that the test did not involve an unreviewed safety question as defined in 10CFR Section 50.59 (a) (2).
A review was also made of our test control program and it was determined that the test control program described in the Nuclear Power Station Quality Assurance Manual Section 5, paragraph 5.8.17, Special Test Prceedure, and Section
.1, paragraph 5.5, Special Tests is adequate.
Special Test Procedures have been established to asse,e that special tests or experiments receive the proper review. These procedures may in-volve the acquisition of data associated with unit or equipment performance, or other technical data required for engineering or operational evaluation.
Since the test control program is adequate, station management will re-emphasize the requirements of the Special Test Program. This re-emphasis will include the requirements of Technical Specification 6.5.1.6.b in that the SNSOC shall review all proposed tests and experiments that affect nuclear safety and the requirements of 10CFR Section 50.59 in that test or experiments not described in the safety analysis report must be evaluated to determine if the test or experiment involves an unreviewed safety question.
i Attachment, page 2 2.
Corrective action taken to avoid further non-compliance:
To ensure established procedures are followed correctly station manage-ment will distribute a letter re-emphasizing the requirements of Test and 4
Experiements to station supervisors.
Station supervisors will then discuss this letter with their personnel.
3.
Date when full compliance will be achieved:
Full compliance will be achieved by May 31, 1980.
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