IR 05000412/1986003
| ML20202F566 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 03/21/1986 |
| From: | Anderson C, Cheung L, Woodard C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20202F530 | List: |
| References | |
| 50-412-86-03, 50-412-86-3, IEB-83-01, IEB-83-03, IEB-83-04, IEB-83-1, IEB-83-3, IEB-83-4, NUDOCS 8604140176 | |
| Download: ML20202F566 (7) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
Report No.
50-412/86-03 Docket No.
50-412 License No.
CPPR-105 Priority Category B
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Licensee:
Duquesne Light Company Facility Name:
Beaver Valley Power Station, Unit 2
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Inspection At:
Shippingport, Pennsylvania Inspection Conducted:
January 27 - February 7, 1986 Inspectors:
CentA~t'
6cM[ A L. Cheung, Reactor Engine g h 'gu/M date d&Ln C. Woodard e torEngeerJ
/ d te Approved by:
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C. Anderson, Chief, Plant Systems Section,
' date Engineering Branch, DRS Inspection Summary:
Inspection on January 27 - February 7, 1986 50-412/86-03
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Areas Inspected: A routine unannounced inspection consisting of work obser-vation, work in progress, completed work activities, and documentation relative to the installation of instruments and electrical equipment to ascertain wheth-er these activities are being accomplished in accordance with NRC require-ments and licensee FSAR commitments.
Additionally, the inspectors reviewed the status of previously identified inspection findings.
The inspection involved 104 inspector hours onsite by two region-based inspectors.
Results:
No violations were identified.
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i DETAILS 1. 0 Persons Contacted 1.1~ Duquesne Light Company
- L. Arch, Sr. Projection Engineer
- R. Coupland, Director, Quality Control
- C. Davis, QA Director
- D. Denning, Assistant Director Quality Control
- E. Horvath, Senior Project Engineer
- C. Kirschner, Q.A. Supervisor
- C. Majumdar, Assistant Director Quality Control
- T. Noonan, Station Superir.tendent
- R. Swiderski, Startup Manager 1. 2 Stone and Webster Engineering Corporation j
- W. Baranowski, Assistant Project Manager
- P. Bienich, Assistant Superintendent of Engineering
- A. Dasenbrock, Resident Manager l
'*D. Lamson, Assistant Resident Engineer
- J. Purcell, Assistant Superintendent
- R. Wittschen, Licensing Engineer 1. 3 United States Nuclear Regulatory Commission
- G. Walton, Senior Resident Inspection
- L. Prividy, Resident Inspector
- Denotes those personnel present at exit meeting.
2.0 Facility Tour The inspector observed work activities in progress, completed work and plant status in several areas during a general inspection of the site.
The inspector examined work items for obvious defects or noncompliance with NRC requirements or licensee commitments.
Particular note was taken regarding the presence of quality control inspectors and indication of quality control activities through visual evidence such as inspection records, material identification, nonconformance and acceptance tags.
In addition, the inspector interviewed craft and supervisory personnel encountered in the work area.
While in the Diesel General (DG) Building, the inspector noted that:
The backpanels of the DG Control Cubicles were removed, render-a.
ing the I&C equipment inside the cubicles exposed to the con-struction environmt.nt.
These backpanels were never put back to the control cubicles during the two week period when the in-spectors were at the site.
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At the same time construction activities were going on in the DG Building including metal cutting, grinding, and scaffolding.
Contaminant and debris could get into the instruments causing a short circuit.
The insides of these control cubicles were very dusty, c.
d.
There were extension cords, trouble lights and loose fuses stored inside the control cubicles.
The inspectors discussed their concern with the licensee. According to the licensee, the DG system had been turned over from the construction to the startup group.
However the DG Building had not yet been turned over.
The licensee did not have a program to control this situation.
The inspector did not identify similar problem in other areas of the plant.
In addition no obvious equipment damage was observed.
The li-censee plans to establish a program to control this situation.
This item is unresolved pending NRC review of the licensee's program to correct this problem (412/86-03-01).
3.0 Instrumentation Component / System-Work Observations 3.1 The inspector examined work performance, partially completed work and completed work pertaining to the installation of safety-related level instruments in the Quench Spray System and the associated tubing to determine whether the requirements of applicable specifications, NRC requirements and licensee commitments were met in the areas of design drawings, material qualifications, installation and quality control inspectors.
3.2 Items examined for this determination include:
Safety related RWST level transmitters 2QSS* LT 100 A&B, located a.
in Safeguard Yard at elevation 735'4".
b.
Safety related RWST level indicators, located in the Main Control Board, at elevation 735'.
c.
Safety related rack mounted instruments 2QSS* LPW 100 A&B, current to voltage converters and isolators, 2QSS* LSKK 100A1 &
t B1, level measurement bistables, all located in the secondary process racks A&B.
d.
Stone & Webster Instrument Installation Specification 2BVS-977, Rev. 2 dated April 24, 1985.
Stone and Webster loop diagrams for 2QSS* LT100A&B, Rev. 7 dated e.
November 15, 1985 f.
Stone & Webster Isometric Drawings RIC-325 R-1 and RK-325Q-1 l
for transmitters 2QSS*LT100 A&B.
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Instrumentation Inspection Report No. MEMR5354 for seismic support No. 2QSS-TSR-101,105,106,107 and 2QSS-KSA021, dated August 12, 1985 t
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Instrumentation Inspection Report No. ME MR1589 for
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transmitter 2QSS*LT100B, dated August 22, 1985.
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Inspection Report No.16909 for " Maintaining Traceability l
of ASME IV Material and Items" dated August 1, 1!85.
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3.3 The inspector verified the mounting configurations of the instru-ments, flow direction of the instrument valves and the required l
instrument impulse line slope.
Within the scope of this inspection, no unacceptable conditions were identified.
4.0 Instrument Cable and Termination - Work Observation 4.1 The inspector observed work performance, partially completed work and completed work pertaining to the installation of instrument cables and terminations to determine whether the requirements of the appli-cable specifications, instruction and procedures are being met in areas relating cable type and size, routing, raceway identification and cable terminations.
4.2 Items examined for this determination include:
a.
Instrument cable routing and termination from level trans-mitters 2QSS*LT100A&B in the Safeguard Yard area to the secondary process racks RK*2SEC-PROC-A&B in the I&C room at Elevation 707'.
b.
Instrument cable routing's and termination from RK*2SEC-PROC-A&B to level indicators 2QSS* LI18DA&B in the Main Control Room.
Instrument-Loop Diagram for 2QSS*LT100A&B, Rev 7 dated c.
November 15, 1985.
d.
Test Loop Diagram for Quench Spray System, Refueling Water Storage Tank, 2QSS*TK21, No. 13B-001 and 002, dated June 1, 1984.
e.
Cable Pull tickets for:
2QSSARX001 (from RK*2SEC-PROA to 2QSS* LT100A) dated April 20, 1983 2QSSBWX001 (from RK*2SEC-PROCB to 2QSS*LT1008) dated August 20, 1982.
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Termination inspection reports for:
2QSSARX001 "From end" and "To end" dated September 9,1985.
2QSS BWX001 "From end" dated October 9, 1985 "To end" dated October 22 - 28, 1985.
g.
Cable pull inspection reports for:
2QSSARX001 dated August 6, 1985 and September 24, 1985 2QSSBWX001 dated October 3, 1985.
4.3 The inspector verified the corrections of the terminations, traced sections of the raceway and verified the raceway numbers.
Within the scope of this inspection no unacceptable conditions were identified.
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5.0 Nonconformance and Disposition Report The inspector selected the following nonconformance and Disposition Reports (N&DR) to determine if the engineering dispositions were adequate and if the deficiencies were resolved in a timely manner.
1.
Construction deficiency report (CDR) No I-005 " Negative slopes
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of 2QSS*LT1008 instrument testing" dated August 14, 1985.
Rework for this CDR was inspected and accepted on August 19, 1985.
2.
N&DR No. 32049 " Violation of Testing Mounting Configuration" for 2QSS*LT100B dated August 20, 1985.
3.
N&DR No. 35099 " Flex Hose Dimensions out of Tolerance" for RK-303AL-1, dated December 17, 1985.
4.
N&DR No. 35038 " Tubing length out of tolerance" for RK-3238-3 dated September 18, 1986. ~
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N&DR No. 30532 " Tubing Support Installed out of Tolerance" dated September 11, 1985.
6.
N&DR No. 35031 " Flex Hese Installed" Interference" dated August 13, 1985.
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N&DR No. 32331 "Hilti Dimension out of Tolerance (N-132)" dated October 29, 1985.
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N&DR No. 32333 " Tubing Support installed out of Tolerance (N-132)" dated October 29, 1985.
In the N&DR's selected, the inspector determined that the licensee's dispositions were adequate and timely in closing the items.
No violations were identified.
l 6.0 Review of Electrical Power Distribt Voltage Profile l
The inspector reviewed the electrical power distribution including the distribution of power to the class IE safety loads.
Voltage profile studies were conducted by Stone and Webster in which various combination of bus loads, grid voltages, motor starting and initial voltage conditions were simulated.
The voltage profile studies show that bus voltages to power class IE equipmer.ts remains within the range of 90 to 110% of design nominal voltage except for brief transients when starting, stopping or transferring major load increments.
In accordance with the requirements stated in paragraph 83 of the FSAR, class IE motors are not exposed to initial starting voltages of less than 80% of nominal nameplate rating.
A worst case voltage dip down to 82% of rated voltage occurs on bus 2N when starting the largest load (300 horsepower) on that bus.
Within the scope of this review, no unacceptable conditions were identified.
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7.0 Licensee Actions on Previous Inspection Findings (Closed) Inspection Bulletin Item 83-Bu-01 relating to failure of Westing-house supplied type DB50 reactor trip circuit breakers to open upon receipt of an automatic trip open signal.
The inspector verified that the licensee does not use the Westinghouse type DB50 circuit breaker in the reactor trip circuits.
This item is closed.
(Closed) I & E Bulletin Items 83-03 and 83-04 relating to a significant deficiency with the Westinghouse DS-416 reactor trip switchgear under-voltage trip mechanism.
This item was first reported to NRC by Westing-house on April 15 and by Duquesne Light Company on April 26, 1983 as a 50.55e Significant Deficiency.
The inspector reviewed the Westinghouse supplied modification to the DS-416 circuit breakers which included replacing the undervoltage trip
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mechanism with a new mechanism to overcome the deficiency.
l The inspector reviewed the Westinghouse installation quality assurance l
inspections, operations, and tests conducted in the evaluation and accep-j tance of this modification.
This work was completed and final acceptance
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made on January 26, 1986.
This item is closed.
(Closed) Inspection Item 85-22-01 relating to in place storage maintenance meggaring requirements for auxiliary electric motors which are a part of the emergency diesel generatt equipment.
The inspector confirmed that the vendors requirements for nmggering motors on a quarterly basis had been adopted and included as a part of Stone and Webster construction Maintenance / Storage Procedure 2BVS-981 effective July 18, 1985.
However this equipment as a part of the Emergency Diesel Generators was turned over from Stone and Webster Construction to Duquesne Light Company Start Up Group prior to implementation of the revised procedure. All motors have since been run thereby indicating that the in place storage conditions without the quarterly meggering has not resulted in degradation of the motor windings.
The equipment will now be subject to Duquesne Light Company storage, operation, and maintenance procedures.
This item is closed.
8.0 Westinghouse Solid State Protection System (SSPS) Trip Circuit The SSPS trip circuit was inspected to determine the location of the manual trip switch in relation to undervoltage (UV) output transistors Q3 and Q4 If the manual trip switch is upstream of the UV output transis-tors, failure of these transistors could result in loss of both automatic trip and manual trip capability of the UV circuit breaker.
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The inspector reviewed Westinghouse drawing 1083H85, Revision H and
" Beaver Valley Unit #2 Solid State Protection System Schematic Program".
This drawing is the current controlled drawing in use by the licensee for this system and it correctly shows the manual trip circuit downstream of the power output transistors Q3 and Q4 A visual inspection at the solid i
state reactor protection panels was made to confirm the circuit l
locations.
l This item is closed.
9.0 Unresolved Items Unresolved items are matters which more information is required in order to ascertain whether they are acceptable items, or violations.
Unresolved items identified during this inspection are discussed in Details, in paragraph 2.0.
10.0 Exit Meeting The inspector met with licensee and construction representatives (denoted in paragraph 1.0) at the conclusion of the inspection on February 7, 1986 l
at the construction site.
I The inspector summarized the scope of the inspection, the inspection findings and confirmed with the licensee that the documents reviewed by the team did not contain any proprietary information.
The licensee agreed that the inspection report may be placed in the Public Document Room with prior licensee review for proprietary information (10 CFR 2.790).
At no time during this inspection was written material provided to the
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