ML20151X828

Replacement Notice of Violation from Insp on 851209-13

ML20151X828
Person / Time
Site:	Sequoyah
Issue date:	01/29/1986
From:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
To:
Shared Package
ML20151X795	List: ML20151X790 ML20151X828 ML20151X879
References
50-327-85-46, 50-328-85-46, NUDOCS 8602120509
Download: ML20151X828 (2)

Text

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t ENCLOSURE 1 NOTICE OF VIOLATION Tennessee Valley Authority Docket Nos. 50-327 and 50-328 Sequoyah License Nos. DPR-77 and DPR-79 The following violations were identified during an inspection conducted on December 9-13, 1985. The Severity Levels were assigned in accordance with the NRC Enforcement Policy (10 CFR Part 2, Appendix C).

1. Technical Specification (TS) 6.8.1 requires that adequate written procedures be established and maintained covering safety-related activities stated in Appendix A of Regulatory Guide 1.33, Revision 2, which include the use of surveillance procedures anc system operating instructions.

Contrary to the above, in the instances cited below, the licensee inade-quately established or maintained surveillance instructions and system operating instructions.

a. SI-256, Periodic Calibration of Overcurrent Relays and Distance Relays on 6.9 KV Reactor Coolant Pumps on 6.9 kV Unit Boards, contains the following inadequate acceptance criteria:

(1) For primary overcurrent protective devices, the procedure esta-blishes a trio setpoint amperage tolerance value of :5%. TS Table 3.5-1 for coth units requires a 2% tolerance.

(2) For primary overcurrent orotective devices, the procedure esta-olishes a 75 degree impedance angie of maximum torque. The proper value is 105 degrees.

(3) For primary overcurrent orotective devices, the procedure requires distance relay targets to coerate between 1.0 and 2.0 amperes with  !

CC voltage aoplied. The vendor manual for these type IAC 66K l

relays requires proper operation between 0.1 and 2.9 amperes.  !

b. Procedure SGI 30.6, Auxiliary Building Gas Treatment System, listed use l of fuses with incorrect amperage ratings and prescribed positioning of I; a block switch which nad been previously disconnected from the circuit.

c. Instrument maintenance procecure IMI-99, Reactor Protection System Calibration and Functional Testing, prescribed use of inadeouate i measuring anc test ecuipment. The measuring anc test equipment pre- I scriced was only 2 to 2.5 tires more accurate than tne measurec para-meter wnen the setpoint methodalogy used to determine reactor protec-ticr setcoints assumed the ecutoment was ten times ? ore accurate than the measured carameter.

This is a Severity Level IV Violatton (Sucplement I).

66021?O'KW 060129 PDR ADOCK 05C(XKW/

9 PDR l

Tennes'see Valley Authority 2 Docket Nos. 50-327 and 50-328 Sequoyah License Nos. DPR-77 and DPR-79

^ 2. TS 6.5.1.6.d requires that the Plant Operations Review Committee (PORC) review unit. operations to detect potential nuclear safety hazards.

Contrary to the above, the PORC failed to conduct a formal review of the potential nuclear safety hazards associated with accuracy of Measuring and Test Equipment (M&TE) used for calibration of Reactor Protection System (RPS) instrumentation. The M&TE accuracy for such test equipment as Fluke 8600 and Ashcroft Digigage used for calibrating RPS instrumentation did not meet the accuracy assumptions used in the setpoint methodology for RPS trip setpoints.

This is a Severity level IV Violation (Supplement I).

3. TS 6.8.1 requires that written procedures be implemented covering safety-related activities stated in Appendix A of Regulatory Guide 1.33, Revision 2, which includes the use of surveillance and administrative procedures. Surveillance Instruction (SI) 256, Periodic Calibration of Overcurrent Relays and Distance Relays on 6.9 kv Reactor Coolant Pumps on 6.9 kv Unit Boards was established to control testing of the primary and secondary overcurrent containment penetration protection devices required by TS 3/4.8.3. Administrative Instruction (AI) 4, Plant Instructions - Docu-ment Control, was established to provide controls for procedure changes, as required by TS 6.8.3.

Contrary to the above, these procedures were not implemented in that:

a. Initial and independent verification signoffs for conformance to SI-266 Relay Test Record Sheet acceptance criteria were made when the recorded value was outside the procedure acceptance criteria. In addition, supervisory review of the surveillance package did not identify these deficiencies.

b. Proper procedure change control requirements of AI-4 were not imple-mented for pen and ink changes made in the units of measure for Relay Test Record parameters of SI-256. Supervisory review of the surveil- 1 lance package did not identify these deficiencies. l This is a Severity Level IV Violation (Supplement I). l Pursuant to 10 CFR 2.201, you are required to submit to this office within 30 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 tcken 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 facili-tate withholding it from public disclosure as required by 10 CFR 2.790(d) or 10 CFR 73.21.

Date: JAN 2 9 GSS L.____________________________________________________________ ____.______________J