ML20058M789
| ML20058M789 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 11/14/1993 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20058M787 | List: |
| References | |
| 50-334-93-26, 50-412-93-26, NUDOCS 9312210108 | |
| Download: ML20058M789 (2) | |
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ENCLOSURE 1 NOTICE OF VIOLATION I
Duquesne Light Company Docket Nos. 50-334; 50-412 Beaver Valley Power Station License Nos. DPR-66; NPF-73 Unit 1 & 2 During an NRC inspection conducted between October 26 and November 27,1993, two violations of NRC requirements were identified. In accordance with the " General Statemeit i
of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1992), the violations are listed below:
A.
Unit I and Unit 2 Technical SpeciDeation 6.8.1.a requires that written procedures be established, implemented, and maintained, covering activities listed in Appendix A of Regulatory Guide 1.33, Revision 2, February 1978.
Four instances of failure to correctly implement operational procedures occurred as listed below:
1.
Operating Manuai Procedure 6.4E, " Filling and Venting an RCS Loop with Fuel in the Vessel," Issue 4, Revision 0, specifies, in part, that the 480V breaker control handles for loop 'C' hot and cold leg isolation valves shall not be placed in the "on" position. Technical Specification 3.4.1.4 requires, in part, that the RCS isolated loop stop valves shall have power removed from the associated valve operators whenever and RCS loop has been isolated in Mode 5. Contrary to the above, on November 1,1993, breaker control handles for MCCl-18, cubicles U and V, were placed to the "on" position and energized the 'C' loop stop valves while in cold shutdown conditions with the
'C' loop isolated.
2.
Operational Surveillance Test 1.47.3A, "Three Month Containment Isolation and ASME Section XI Test," Issue 2, Revision 7, specifies that fuel pool heat exchanger reactor plant component cooling water inlet isolation valve TV-ICC-128, be stroked timed from full closed to full open. Technical Specification 4.0.5 requires, in part, that TV-lCC-128 be tested to the open position per ASME Section XI testing. Contrary to the above, on July 31, 1993, TV-1CC-128 was stroked tested to the closed position.
3.
Step A.7 in Operations Manual Procedure 2.50.4 requires verification that the -
shift supervisor clearance is in effect on the incore nucle.ar instrumentation.
Contrary to the above, on November 19, 1993, an operator initialed for completion of this step without the shift supervisor clearance in effect.
9312210108 931214 PDR ADOCK 05000334 G
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OFFICIAL RECORD COPY
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2 4.
Operational Surveillance Test 2.11.3 requires 2CHS-37 to be verified closed if the plant is in Mode 4 or 5. Contrary to the above, on November 5,1993, with the plant in Mode 5, an operator erred in indicating that the valve was closed, when, in fact, the valve was open.
This is a Severity Level IV violation (Supplement 1).
t B.
10 CFR Part 50, Appendix B, Criterion 111 (Design Control) requires, in part, that measures be established to assure that regulatory requirements and design basis are irrectly translated into design documents.
3VPS Unit 2 FSAR, Section 7.2.1.1.4, Coolant Temperature Sensor Arrangement, states, in part, that hot and cold leg temperature signals required for input to the reactor protection functions are obtained using thermowell mounted resistance temperature detectors (RTDs) installed in each loop.
Contrary to the above, the licensee failed to establish adequate design control measures for the installation specification of reactor coolant system RTDs installed under Design Change Package 1469 in September 1990. The RTDs were installed in a configuration without adequate thermal insulation to protect against convective heating. The installation was not consistent with environmental qualification test report N9004-87-A used to determine the effects of ambient temperatures on the temperature inside the RTD head.
This is a Severity Level IV violation (Supplement 1).
Pursuant to the provisions of 10 CFR 2.201, Duquesne Light Company is hereby required to submit a written statement or explanation to the U.S. Nuclear Regulatory Commission, ATTN: Document Control Desk, Washington, D.C. 20555 with a copy to the Regional Administrator, Region I, and a copy to the NRC Resident Inspector at the facility that is the subject of this Notice, within 30 days of the date of the letter transmitting this Notice of Violation 93-12-01. This reply should be clearly marked as a " Reply to a Notice of Violation" and should include for each violation: (1) the reason for the violation, or, if contested, the basis for disputing the violation, (2) the corrective steps that have been taken and the results achieved, (3) the corrective steps that will be taken to avoid further violations, and (4) the date when full compliance will be achieved, if an adequate reply is not received J
within the time specified in this Notice, an order or a Demand for Information may be issued to show cause why the license should not be modified, suspended, or revoked, or why such other action as may be proper should not be taken. Where good cause is shown, i
consideration will be given to extending the response time.
1 Dated rt King of Prussia, Pennsylvanit this 14thlay of November
,1993 OFFICIAL RECORD COPY
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