ML20206C722: Difference between revisions
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i I | i I | ||
APPENDIX A | APPENDIX A | ||
[ | [ | ||
Notice of Violation P | Notice of Violation P | ||
Vermont Yankee Nuclear Power Corporation | Vermont Yankee Nuclear Power Corporation Docket No. | ||
During a routine NRC inspection conducted on August 23 - October 10, 1988, cer- | 50-271 Vermont Yankee Nuclear Power Station License No. OPR-28 i | ||
tain violations of NRC requirements were identified. | During a routine NRC inspection conducted on August 23 - October 10, 1988, cer-tain violations of NRC requirements were identified. | ||
Part 2, Appendix C (Enforcement Policy 1986), the violations are listed below: | In accordance with the "General Statement of Policy and Procedure for NRC Enforcement Actions", 10 CFR Part 2, Appendix C (Enforcement Policy 1986), the violations are listed below: | ||
i n. | |||
Technical Specification 3.13.G.2 requires that from and after the date that the recirculation motor generator (MG) set foam system is inoperable, a firewatch shall be established to inspect the location at least once every hour; a foam nozzle shall be brought to the recirculation MG set elevation; and a 100 gallon foam concentrate supply shall be verified to be available onsite. | |||
Contrary to the above, on September 20, 1988, the recirculation MG set was made inoperable without the requirements of TS 3.13.G.2 being established. | Contrary to the above, on September 20, 1988, the recirculation MG set was made inoperable without the requirements of TS 3.13.G.2 being established. | ||
This is a Severity Level IV Violation (Supplement I). | This is a Severity Level IV Violation (Supplement I). | ||
r B. | r B. | ||
Table 3.9.1 requires grab samples of the SW effluent stream be obtained | Technical Specification 3.9. A.1 requires service water (SW) system efflu-l ent radiation monitor operability to be in accordance with Table 3.9.1. | ||
and analyzed every 24 hours if the SW effluent radiation monitor is inoperable. | Table 3.9.1 requires grab samples of the SW effluent stream be obtained and analyzed every 24 hours if the SW effluent radiation monitor is inoperable. | ||
Contrary to the above, on numerous occasions from August 15 to October 10, 1988 when the plant was operated in hybrid and closed cycle, the SW effluent radiation monitor was effectively inoperable due to a nonconservative alarm setpoint and the req Jired grab sampling was not | Contrary to the | ||
accomplished. | : above, on numerous occasions from August 15 to October 10, 1988 when the plant was operated in hybrid and closed cycle, the SW effluent radiation monitor was effectively inoperable due to a nonconservative alarm setpoint and the req Jired grab sampling was not accomplished. | ||
This is a Severity Level IV Violation (Supplement I) | This is a Severity Level IV Violation (Supplement I). | ||
C. | C. | ||
such as by the performance of design reviews. | 10 CFR Part 50, Appendix B, Criterion III requires that design control f | ||
Yankee Atomic Electric Company Operational Quality . Assurance Manual | measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews. | ||
8811160301 001104 ADOCK 050 | Yankee Atomic Electric Company Operational Quality. Assurance Manual l | ||
0FFICIAL RECORD COPY | Section III requires that design reviews be performed to assure that design characteristics can be controlled. | ||
11/03/88 | 8811160301 001104 ADOCK 050 1 | ||
gDR l | |||
0FFICIAL RECORD COPY IR VY 88 0004.0.0 11/03/88 m_,_, | |||
Appendix A | Appendix A 2 | ||
Contrary to the above, the licensee failed to perform adequate reviews of the plant design change requests which installed and modified sevceal fire protection system control | |||
: panels, such that an undetected design deficiency had rendered these sytems technically inoperable since installation. | |||
This is a Severity level IV Violation (Supplement I). | This is a Severity level IV Violation (Supplement I). | ||
Pursuant to 10 CFR 2.201, Vermont Yankee Nuclear Power Corporation is hereby required to submit to this office, within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, includ-ing: (1) the reasons for the violation; (2) ti i corrective steps which have been taken and the results achieved; (3) correct.ve steps which will be taken to avoid further violations; and (4) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time. | Pursuant to 10 CFR 2.201, Vermont Yankee Nuclear Power Corporation is hereby required to submit to this office, within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, includ-ing: | ||
OFFICIAL RECORD COPY | (1) the reasons for the violation; (2) ti i corrective steps which have been taken and the results achieved; (3) correct.ve steps which will be taken to avoid further violations; and (4) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time. | ||
OFFICIAL RECORD COPY IR VY 88 0005.0.0 11/03/88}} | |||
Latest revision as of 02:13, 7 December 2024
| ML20206C722 | |
| Person / Time | |
|---|---|
| Site: | Vermont Yankee File:NorthStar Vermont Yankee icon.png |
| Issue date: | 11/04/1988 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20206C716 | List: |
| References | |
| 50-271-88-14, NUDOCS 8811160381 | |
| Download: ML20206C722 (2) | |
Text
_ _ _ _.
i I
APPENDIX A
[
Vermont Yankee Nuclear Power Corporation Docket No.
50-271 Vermont Yankee Nuclear Power Station License No. OPR-28 i
During a routine NRC inspection conducted on August 23 - October 10, 1988, cer-tain 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 (Enforcement Policy 1986), the violations are listed below:
i n.
Technical Specification 3.13.G.2 requires that from and after the date that the recirculation motor generator (MG) set foam system is inoperable, a firewatch shall be established to inspect the location at least once every hour; a foam nozzle shall be brought to the recirculation MG set elevation; and a 100 gallon foam concentrate supply shall be verified to be available onsite.
Contrary to the above, on September 20, 1988, the recirculation MG set was made inoperable without the requirements of TS 3.13.G.2 being established.
This is a Severity Level IV Violation (Supplement I).
r B.
Technical Specification 3.9. A.1 requires service water (SW) system efflu-l ent radiation monitor operability to be in accordance with Table 3.9.1.
Table 3.9.1 requires grab samples of the SW effluent stream be obtained and analyzed every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> if the SW effluent radiation monitor is inoperable.
Contrary to the
- above, on numerous occasions from August 15 to October 10, 1988 when the plant was operated in hybrid and closed cycle, the SW effluent radiation monitor was effectively inoperable due to a nonconservative alarm setpoint and the req Jired grab sampling was not accomplished.
This is a Severity Level IV Violation (Supplement I).
C.
10 CFR Part 50, Appendix B, Criterion III requires that design control f
measures shall provide for verifying or checking the adequacy of design, such as by the performance of design reviews.
Yankee Atomic Electric Company Operational Quality. Assurance Manual l
Section III requires that design reviews be performed to assure that design characteristics can be controlled.
8811160301 001104 ADOCK 050 1
gDR l
0FFICIAL RECORD COPY IR VY 88 0004.0.0 11/03/88 m_,_,
Appendix A 2
Contrary to the above, the licensee failed to perform adequate reviews of the plant design change requests which installed and modified sevceal fire protection system control
- panels, such that an undetected design deficiency had rendered these sytems technically inoperable since installation.
This is a Severity level IV Violation (Supplement I).
Pursuant to 10 CFR 2.201, Vermont Yankee Nuclear Power Corporation is hereby required to submit to this office, within 30 days of the date of the letter transmitting this Notice, a written statement or explanation in reply, includ-ing:
(1) the reasons for the violation; (2) ti i corrective steps which have been taken and the results achieved; (3) correct.ve steps which will be taken to avoid further violations; and (4) the date when full compliance will be achieved. Where good cause is shown, consideration will be given to extending this response time.
OFFICIAL RECORD COPY IR VY 88 0005.0.0 11/03/88