ML19261C366
| ML19261C366 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 11/08/1978 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML17053A513 | List: |
| References | |
| 50-220-78-15, NUDOCS 7903220337 | |
| Download: ML19261C366 (3) | |
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APPENDIX A NOTICE OF VIOLATION Niagara Mohawk Power Corporation Docket No. 50-220 Based on the results of an NRC inspection conducted on September 25-29, 1978, it appears that certain of your activities were not conducted in full compliance with NRC regulations and the conditions of your NRC Facility License No. DPR-63 as indicated below.
Items A and B are categorized as Infractions, the rest of the items as Deficiencies.
A.
Section 3.2 and Table 3.2 of Appendix B (ETS) require, in part, that water samples from the Nine Mile Point Unit 1 intake, James A.
FitzPatrick plant intake, and Oswego City water intake shall be collected and analyzed on a monthly basis for gemma emitters by germanium lithium detector spectroscopic analysis.
Contrary to these requirements, the analyses of the monthly lake water samples from the Nine Mile Point Unit 1 intake, the James F.
Fitzpatrick intake, and Oswego City water intake were inadequate in that the relatively high radiation background in the sample counting area, resulted in erroneous analytical results for several of months in 1977, including January, February, March, April, May, June, and July.
B.
Section 6.8.1 of the Technical Specifications requires, in part, that written procedures and administrative policies shall be estab-lished, implemented, and maintained.
Plant Operating Procedures No. NI OP-19 requires in part that, prior to the plant flow reversal, the station load be reduced to 75% capacity by adjusting reactor recirculation flow.
Section 2.1.5, ETS requires, in part, that following a flow reversal, the discharge temperature shall not exceed the ambient lake temperature by more than 50 F two hours following flow reversal and thereafter.
Contrary to these requirements, prior to a flow reversal on January 3, 1978, the station load was ot reduced to 75% capacity and during the flow reversal peric. on January 3 and 4,1978, the discharge temperature exceeded the ambient lake temperature by more than 50*F for seven hours during the period from 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> on January 3 through 0500 hours0.00579 days <br />0.139 hours <br />8.267196e-4 weeks <br />1.9025e-4 months <br /> on January 4.
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Appendix A 2
C.
Section 5.5.1 of the Appendix B (ETS) requires, in part, that detailed written procedures including applicable checklists and instructions be prepared and followed for all activities involved in carrying out the environmental monitoring program.
Procedures include sampling, data recording and storage, instrument calibration, measurements, and analyses.
Site procedures No. S-RTP-29, " Radiation Protection Technical and Analytical Procedures," requires, in part, that the environmental station radiation monitors shall be calibrated semi-annually. Section 3.2 (Table 3.2) of the ETS requires, in part, that gamma dose be continuously monitored by radiation monitors at nine onsite and one offsite locations.
Contrary to the above, one of the required onsite environmental station radiation monitors (location J) was not calibrated semi-annually during the period from July 12, 1977, to March 15, 1978.
D.
Section 2.1.1 of Appendix B (ETS) requires, in part, that maximum AT across the main condenser during normal Station operation shall be limited to 32 F.
If during normal Station operation the inain condenser AT exceeds 32 F for a period of eight hours in any given 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> period, the cause of this deviation shall be investigated and positive action shall be taken to reduce the AT to within the Specification.
The temperatures at the main condenser inlet and in the screenwell bay (upstream from the discharge tunnel) shall be monitored by two RTD's in each location.
The difference of these temperatures, AT, shall be computed.
A AT of 31.2 F corresponds to the AT Specification of 32 F, because the) water in the screenwell 7
bay is a mixture of main condenser cooling water and service water.
Contrary to these requirements, the AT) exceeded 31.2 F for nine hours on March 5,1978, and positive action was not taken to reduce the AT to within the Specification.
E.
Section 5.6.3 of Appendix B (ETS) requires, in part, that in the event a Specification limit or a report level is exceeded, a report shall be made within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> by telephone, telegraph, or facsimile transmission to the Director of the NRC Regional Office, followed by a written report within 10 days to the Director of the Regional Office (with a copy to the Director, Office of Nuclear Reactor Regulation).
Contrary to these requirements, neither a telephone nor a written report were made and submitted to the NRC as required when the Specification thermal discharge limit was exceeded on March 5, 1978.
Appendix A 3
F.
Section 2.3.2, lable 2.3-1 of Appendix B (ETS), " Limiting Values for Chemicals in Liquid Effluents," requires that the maximum annual discharge from plant sources for phosphorus be limited to 10 lb/ year.
Contrary to this requirement, the maximum annual phosphorus discharge limit was exceeded for 1977 by 0.72 lb.
We note that the actions to prevent recurrence of this noncompliance were completed prior to the end of the 1977 annual discharge period.
No additional information is required regarding this item at this time.