ML20134B515
| ML20134B515 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah, 05000506  |
| Issue date: | 07/30/1985 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20134B511 | List: |
| References | |
| 50-327-85-17, 50-328-85-17, NUDOCS 8508150655 | |
| Download: ML20134B515 (3) | |
See also: IR 05000506/2006005
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ENCLOSURE 1
Tennessee Valley Authority Docket Nos. 50-327 and 50-328
Sequoyah Units 1 and 2 License Nos. DPR-77 and DPR-79
The following violations were identified during an inspection conducted on
May 6 - June 5,1985. The Severity Levels were assigned in accordance with the
NRC Enforcement Policy (10 CFR Part 2, Appendix C).
-1. Technical Specification 6.8.1 requires that written procedures be
established, covering safety related activities referenced in Appendix A of
Regulatory Guide 1.33, Revision 2, February 1978.
a. DPS0-SMI-10G, " Relay Functional Tests for Diesel Generator Protective
Relays," and MI-10.1, " Diesel Generator Inspection," were established
to implement Technical Specification surveillance requirements.
Contrary to the above, adequate procedures were not established in that
DPS0-SMI-1DG did not specify Emergency Diesel Generator (EDG)
local-remote switch position in the EDG cubical nor in the control room
prior to the completion of paragraph 9.A(4)4.1 and did not require that
controlled test equipment be used in the performance of step 9.A(3),
b. SQM-24, " Torque and Limit Switch Settings for Motor-0perated Valves,"
was established to comply with the above requirement for maintenance
procedures on safety related equipment.
Contrary to the above, SQM-24 did not incorporate the limit switch
adjustment technique identified in MI-11.2, " Motor Operated Valve '
Adjustment Guidelines," which resulted in damage to two safety related
valves and a reactor trip.
c. SI-484, " Periodic Calibration of Reactor Vessel Level Instrumentation
System (RVLIS) and RCS Wide Range Pressure Channels (P-403, P-406)
(Refueling Outage)," was established to implement post modification
testing requirements.
Contrary to the above, SI-484 was not adequately established for
configuration control in that the procedure did not include measures to !
assure that a sensing line common to RVLIS and Reactor Coolant System
pressure transmitter PT-68-66 was isolated so as to preclude actuation I
of a pressure interlock for the Residual Heat Removal (RHR) isolation l
valves. This deficiency resulted in the unanticipated isolation of the
RHR system due to a high pressure signal sensed by the transmitter
during RVLIS fill, vent, and pressurization,
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Tennessee Valley Authority 2 Docket Nos. 50-327 e.1d 328
Sequoyah Units 1 and 2 License Nos. DPR-77 and 79
The above examples constitute a Severity Level IV Violation. This violation
applies to both units. (Supplement I).
2. Technical Specification 6.11 requires that procedures for personnel radia-
tion protection shall be prepared consistent with the requirements of
10 CFR 20 and shall be approved, maintained and adhered to for all opera-
tions involving personnel radiation exposure. These requirements are
implemented by procedure RCI-1, " Radiological Hygiene Program," which
requires each employee to adhere to Health Physics procedures and protective
measures. One protective measure, Radiation Work Permit (RWP) 1-85-105,
required a canvas hood be worn in addition to other protective clothing
while conducting activities in the Unit 1 containment radiation area.
Contrary to the above, RWP 1-85-105 requirements were not implemented in
that an individual was observed conducting activities in the Unit I contain-
ment without the prescribed canvas hood.
This is a Severity Level V violation. This violation applies to Unit 1
only. (Supplement IV).
3. Technical Specification 6.8.1 states that written procedures shall be
established, implemented and maintained covering the procedures referenced
in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978. Proce-
dure MI-10.1 was established to implement requirements for Emergency Diesel
Generator surveillance testing. MI-10.1 paragraph 5.3.1.2.2.5 requires
technicians to set up test equipment prior to diesel engine start and
paragraph 5.3.1.2.4 requires the technician to verify receipt of the " Engine
Running" annunciation at 850 rpm engine speed.
Contrary to the above, as of May 21, 1985, MI-10.1 was not implemented in
that technicians did not set up their test equipment prior to engine start
and the technician erroneously recorded 850 rpm as the annunciation speed
when the annunciation actually energized at about 875 rpm.
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This is a Severity Level V violation. This violation applies to both units.
(Supplement I).
4. Technical Specification 6.8.1 requires that written procedures be
implemented covering activities referenced in Appendix A of Regulatory
Guide 1.33, Revision 2, February 1978.
Contrary to the above, Workplan No.11188, which was established to install
the battery racks and battery cells for vital bottery V, was not implemented
in that installation of the intercell spacers for vital battery V was not
completed in accordance with the vendor drawings for installation of the
battery racks as required by the workplan.
This is a Severity Level V violation. This violation applies to both units.
(Supplement I).
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Tennessee Valley Authority 3 Docket Nos. 50-327 and 328
Sequoyah Units 1 and 2 License Nos. OPR-77 and 79
Pursuant to 10 CFR 2.201, you are required to submit to this office within .,
days of the date of this Notice, a written statement or explanation in reply,
including: (1) admission or denial of the alleged 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 will be achieved.
Security or safeguards information should be submitted as an enclosure to
facilitate withholding it from public disclosure as required by 10 CFR 2.790(d)
or 10 CFR 73.21.
Date: JUL 3 01905