ML20030B634
| ML20030B634 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 06/16/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20030B623 | List: |
| References | |
| 50-338-81-07, 50-338-81-7, 50-339-81-08, 50-339-81-8, NUDOCS 8108180375 | |
| Download: ML20030B634 (3) | |
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APPENDIX A NOTICE OF VIOLATION Virginia Electric and Power Company Docket Nos. 50-338 & -339 North Anna 1 and 2 License Nos. NPF-4 & NPF-7 As a result of the inspection conducted on April 27 - May 1 1981. and in accord-ance with the Interim Enforcement Pol i c;, 45 FR 66754 (October 7, 1980), the following violations were identified.
A.
10 CFR 50, Appendix B, Criterion II and the accepted Quality Assurance (QA) program,.. action 17.2.2 require the identification of the structures, syster.s, and components to be covered by the QA program. The introduction to Appendix B states that QA comprises 111 those systematic actions neces-sary to orovide adequate confidence that a structure, system, or componert will perform satisfactorily in service.
Control of consumable / expendable items used in those structures, systems ard components covered by the QA prograat is one aspect of those systematic actions to be included in the QA program.
Contrary to the above, the iicensee has not e:tablished a program for the control of consummable/ expendable items ust.d in the structures, sy-tems a'd components covered by the QA program.
This is a Severity Level V Violation (Supplement I.E).
B.
Technical Specification 6.8.1 requires that procedures identified in Appen-dix A of Regulatory Guide 1.33, Revision 2, February 1978 be provided.
Section 8 of this Guide requires procedures to ensure that tools, gauges, instruments, controls and other measuring and testing equipment are properly calibrated at specified periods to maintain accuracy.
Contrary to the above. Period Test 1-PT-32.7.1, Safety Related Instrumenta-tion Calibration, Revision 2 dated February 1981, does not ensure that equipment is calibrated at specified periods.
Although it specifies a two year calibration frequency for safety related instrumen*.s not covered by 3
Techni 31 Specificar. ions, the periodic test permits an indefinite extension of the calibration frequency.
This is a Severity Level V Violation (Supplement I.E).
C.
10 CFR 50 Appendix B Criterion V and the accepted QA Program, Section 17.2.5 require that activities affecting auality shall be prescribed by instruc-tions, procedures and drawings.
The accepted QA Program endorses ANSI N18.7-1972.
Section 5.4 of this Standard requires periodic review of procedures and the frequency of these reviews shall be specified.
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Virginia Electric and Power Company 2
Docket Nos. 50-338 & -339 Nortn Anna 1 and 2 License Nos. NPF-4 & NPF-7 Contrary to the above, periodic reviews and frequency of reviews are not specified in that Nuclear Power Station Quality Assurance Manual (NPSQAM)
Procedures 1, 8, 9 and 10 have not been periodically reviewed, and the frequency of review is not specified.
This is a Seserity Level V Violation (Supplement I.E).
D.
10 CFR 50, Appendix B Criterion XVII and the accepted QA Program. Section 17.2.17, require sufficient r:-cords to be maintained to furnish evidence of activities affecting quality.
1.
The accepted QA Program endorses ANSI N45.2.12, Draft 3, Revision 4-1974.
Section 5.2 of this Standard requires audit records to be generated and maintained.
Records shall include written replies to audits.
Contrary to the rPove, written replies for audits N-79-52 and N-80-02 were not maintained.
2.
Criterion XVII and Section 17.2.17 additionally. require that the records shall include the results of qualifications of personnel.
Contrary to the above, mandatory attendance for system lectures required for Shift Technical Advisors (STA) qualifications were not maintained.
This is a Severity '-"el VI Violation (Supplement I.F).
E.
Technical Specif
.so 6.4 states that the Station Manager is responsible for ensuring that retraining and replacement training programs for the facility staff are maintained and that such programs meet or exceed the requirements of Section 5.5 of ANSI N18.1-1971. Section 5.5 of ANSI N.18.1 requires a training program be established which maintains the proficiency of the operating organization through periodic training exercises. Section 3.2 of ANSI N18.1-1971 states the operating organization of a nuclear power plant consists of onsite personnel concerned with the do to day operation, maintenance, and certain technical se rv. ice s.
Administrative Procedure ADM-12.0, Station Training dated 4/80, implemcnts the training program.
Paragraph 12.2.2 of ADM-12.0 requires that offsite personnel retrain and recertify every 12 months.
Contrary to the above, retraining was not provided every 12 months for the operating organization in that 3 offsite personnel (2 Stone and Webster Engineers and 1 Westinghouse engineer) had not received the required retraining within the specified retraining period of 12 months.
This is a Severity Level VI Violation (Supplement I.F).
M
Virginia Electric and Power Company 3
Docket Nos. 50-338 & -339 Nortn Anna 1 and 2 License Nos. NPF-4 & NPF-7 F.
10 CFR 50, Appendix 2, Criteric i V and the accepted QA Program, section-17.2.5 require that activities affecting quality be accomolished in accord-ance with documented precedures.
1.
The Nuclear Power Station Qualit: Assurance Manual, Section 4, Procure-ment Document Control, Revision 4 cated March 2980 reauires that the requisitioner list the Uuality Assurance category on the purcnase requisition.
Contrary to the above. the requisitioner did nct recorc :ne Quality i
Assurance category on requisitions for purc"ise c dars 42437 and 41159.
2.
The VEPCO Development Policy Manual requires that the individual being trained, the supervisor, the Nuclear Training Supervisor and the Station Manager sign the end-of-step examination and the comprehensive examination given to auxiliary operators.
Contrary to the above, the Station Manage, did not sigt both the end of step 7 and the comprehensive examination for one incisidual ano the Station Manager and the immediate iuperiisor Jic not sign tF~ compre-hensive examination for another individual.
This is a Severity Level VI Viola'. ion (Supplement I.F).
Pursuant to tne provisions of 10 CFR 2.201, you are hereby required to submit to this office within twenty-five days of t.ie date of this Notice, a written state-me;>c or explanation in reply, including: (1) admission or denial of the alleged l
violations; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will be taken to avoid further violations; and (5) the date when full compliance I
will be achieved. 'Jnder the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under Sath or af firmation.
l JHN 1 R 1AR1 Date: