ML20057A416
| ML20057A416 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/03/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20057A412 | List: |
| References | |
| 50-327-93-33, 50-328-93-33, NUDOCS 9309140173 | |
| Download: ML20057A416 (2) | |
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s ENCLOSURE 2 NOTICE OF DEVIATION Tennessee Valley Authority Docket Nos. 50-327 and 50-328 Sequoyah, Units I and 2 License Nos. DPR-77 and DPR-79 During an NRC inspection conducted July 11 through August 7, 1993 a deviation i
of written commitments were identified.
In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C, the deviation is listed below:
Sequoyah Nuclear Plant Final Safety Analysis Report (FSAR), Section 9.3.2.2, System Description, identifies the physical configuration and capability of the Process Sampling System.
j Section 9.3.2.5, Instrumentation Applications, identifies the applications for which the sampling system is designed.
Table 9.3.2-1, Process Sampling System Sample Locations and Data, lists for each sample the system, sample location, system design temperature and pressure, and sample type.
Sequoyah Nuclear Plant Final Safety Analysis Report (FSAR), Section l
7.7.1.3.1, Monitoring Functions Provided by the Nuclear Instrumentation
)
System for power range Channels, identifies the physical configuration of the power range channel recorders.
Contrary to the above, the actual physical configuration and operation of the Process Sampling System and the Nuclear Instrumentation System i
differed from that described in the FSAR, as evidenced by the following examples:
j A.
Not all sample lines originating within containment have air-operated valves installed, as described in Section 9.3.2.2 of the FSAR. Work Packages WP-1515 and WP-1516, were completed in 1990 to install solenoid operated valves in the steam generator blowdown sampling system.
i B.
No portable sample analyzer equipment is available to measure boron concentration in the reactor coolant system, as described in the Section 9.3.2.2 of-the FSAR.
C.
FSAR Section 9.3.2.2 states that boron concentration monitors (one e
per unit) are located in the hot sample room, and the readout is
)
recorded in the' main control room. These monitors are currently abandoned in place, and thus are non-functional.
I D.
Hot sample room primary samples are not analyzed for pH, as stated in Section 9.3.2.2 of the FSAR.
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Tennessee Valley Authority 2
Docket Nos. 50-327 and 50-328 Sequoyah, Units 1 and 2 License Nos. DPR-77 and DPR-79 l
E.
Automatic analyzers and/or recorders do not analyze silica or sodium, as stated in Section 9.3.2.5 of the FSAR. The equipment associated with these variables are abandoned or out of service.
F.
Specific components of the condensate demineralizer, Waste and i
Auxiliary Waste Evaporator systems, and Waste Treatment syste.n, as described in FSAR Table 9.3.2-1, Sheets 1 - 10, are abandoned or out of service.
In addition, sampling points currently being used by chemistry laboratory technicians are absent from the itemized list in Table 9.3.2-1.
G.
Power range channel recorders installed in the control room to record overpower excursions up to 200 percent of full power have not been operable for over 2 years.
Please provide to the U. S. Nucle.r Regulatory Commission, ATTN: Document Control Desk, Washington, D.C.
20555, with a copy to the Regional Administrator, Region II, and a copy to the NRC Resident Inspector in writing I
within 30 days of the date of this Notice, the reasons for the deviation, the corrective steps which have been taken and the results achieved, the corrective steps which will be taken to avoid further deviations, and the date when your corrective action will be completed. Where good cause is shown, consideration will be given to extending the response time.
Dated at Atlanta, Georgia this 3rd day of September 1993 i
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