IR 05000334/1979025
| ML19290D952 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 12/19/1979 |
| From: | Baunack W, Blumberg N NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19290D943 | List: |
| References | |
| 50-334-79-25, NUDOCS 8002290555 | |
| Download: ML19290D952 (8) | |
Text
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U. S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION I
Report No.
50-334/79-25 Docket No.
50-334 License No.
DPR-66 Priority
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Category C
Licensee:
Duquesne Light Company 435 Sixth Avenue Pittsburgh, Pennsylvania 1521 9 Facility Name:
Beaver Valley Power Statidn, Unit No. 1 Insnection At:
Shippinoport, Pennsylvania Inspection Conducted:
November 13-16, 1979 b
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Inspectors:
N. Blumberg,/ Reactor Insp4ctor date date date Approved by:
Rm
/h/9h9 W. Baunack, Acting Chief, Nuclear Support
' date'
Section 2, RO&NS Branch Inspection Summary:
Inspection on November 13-16, 1979 (Report No. 50-334/79-25)
Areas Inspected:
Routine, unannounced inspection by a regional based inspector of administrative controls for surveillance procedures; surveillance testing; inspector witnessing of surveillance testing; technician qualification; and control room observations.
The inspection involved 30 inspector hours onsite by one NRC inspector.
Results:
Of the five areas inspected, no items of noncompliances were found in four areas; and one item of noncompliance was found in one area (Deficiency -
Failure to maintain controlled copies of surveillance procedures current -
paragraph 3.c(1)).
Region I Form 167 (August 1979)
g
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DETAILS 1.
Persons Contacted E. Conrad, Senior Engineer Maintenance
- R. Druga, Shift Operations Foreman
- W. Glidden, Station Quality Assurance Engineer
- K. Grada, Shift Supervisor
- C. Hill, Station Quality Assurance Engineer
- F. Lipchick, Station Quality Assurance Engineer J. Vassello, Training Supervisor J. Werling, Station Superintendent The inspector also interviewed several other licensee employees during the inspection, including reactor operators, technicians, technical support and office personnel.
- Denotes those present at the exit interview.
2.
Administrative Controls for Surveillance Procedures The inspector performed an audit of the licensee's administrative controls by conducting a review on a sampling basis of the below listed administra-tive procedures with respect to the requirements of the Technical Specifica-tions, Section 6, " Administrative Controls", ANSI N18.7 " Administrative Controls for Nuclear Power Plants" and Regulatory Guide 1.33 " Quality Assur-ance Program Requirements".
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BVPS-0M 1.48.3C.b, Set Points, Revision 1, May 8, 1975;
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BVP-S-0M 1.48.E, Review, Revision and Approval of Procedures, Revision 5, September 22, 1976;
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BVPS-0M 1.48.3G, Adherence to Operating Procedures, Revision 12, May 3, 1979;
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BVPS-0M 1.48.4, Qualifications of Operating Personnel, Revision 3, March 14, 1977;
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BVPS-0M 1.48.5, Administrative Controls, Revision 5, July 13, 1979;
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BVPS-0M 1.48.7, Operating Schedules and Coordination Procedures, Revision 7, July 13, 1979;
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8VPS-0M 1.55A.1, Periodic Checks - Operating Surveillance, Revision 3, July 7, 1977.
No items of noncompliance were identifie.
3.
Surveillance Testing a.
The inspector reviewed surveillance tests on a sampling basis to verify the following:
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Tests required by lechnical Specifications are covered by properly approved procedures; Test format and technical content are adequate and provide satis-
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factory testing of related systems or components
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Test frequency is in conformance with Technical Specification requirements;
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Test results of selected tests are in conformance with Technical Specifications and procedural requirements and have been reviewed by someone other than the tester or individual directing the test.
b.
The following surveillance tests were reviewed to verify the items identified above:
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OST 1.11.10, Boron Injection Flow Path Power Operated Valve Exer-cise, Revision 18, October 25, 1978; Dates Performed:
October 23, 1979; October 16, 1979; October 9, 1979; October 2, 1979; September 29, 1979; and September 18, 1979.
OST 1.11.13, Boron Injection Flow Path Valve Position Verifica-
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tion, Revision 18, October 29, 1978; Dates Performed:
September 17, 1979; August 20, 1979; July 30, 1979; June 29, 1979; May 29, 1979; and May 2, 1979.
MSP 6.19, Pressurizer Safety Valve Setpoint Verification, Revi-
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sion 2, October 22, 1976; Dates Performed:
October 12, 1978.
OST 1.6.5, RCS Loop Stop Valves Breaker Alignment Verification,
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Revision 5, February 23, 1977; Dates Performed:
September 23, 1979; August 26, 1979; August 14, 1979; April 8, 1979; and March 11, 1979.
Surveillance Verification Log LS-8, (1) Safety Injection Pumps
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Valve Position Verification Each Shift; Dates Performed:
Three times daily October 22-31, 1979.
(2) Boron Injection Tank Daily Temperature Verification;
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Dates Performed:
Once daily October 22-31, 1979.
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OST 1.11.13, Boron Injection Surge Tank Level Verification, Revi-sion 13, June 27, 1977; Dates Performed:
October 23, 1979; October 16, 1979; October 9, 1979; October 2, 1979; September 25, 1979; and September 8, 1979.
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OST 1.11.6, ECCS Flow Path and Valve Position Check (L.H.S.I.
Loop A), Revision 16, November 23, 1977; Dates Performed:
September 17, 1979; September 3, 1979; August 16, 1979; and March 9, 1979.
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OST 1.11.1, Safety Injection Pump Test (1SI-P1A), Revision 18, October 29, 1978; Dates Performed:
October 22, 1979; October 15, 1979; September 19, 1979; and September 13, 1979.
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OST 1.47.3A, Three Month Containment Isolation Test, Revision 19, March 31, 1979; Dates Performed:
August 10, 1979; April 21, 1979; and January 30, 1979.
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OST 1.13.1, lA Quench Pump Flow Test, Revision 11, October 18, 1978; Dates Performed:
September 14, 1979; August 11, 1979; March 30, 1979; and February 2, 1979.
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OST 1.47.2, Containment Integrity Verification, Revision 21, September 5, 1979; Dates Performed:
Seotember 28, 1979; August 31, 1979; and August 13, 1979.
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Surveillance Verification Log, LS-16, Weekly Verification of Quadrant Power Tilt (Alarm Operational) and Verification Each Shift of Quadrant Power Tilt ' Alarm Not Operational);
Dates Performed:
Daily or three times a day August 18-31, 1979.
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OST 1.24.2, Motor Dirven Auxiliary Feed Pump Test (1FW-P-3A),
Revision No. 11, September 24, 1979; Dates Performed:
September 28, 1979; August 31, 1979; August 7, 1979; and March 23, 197.
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OST 1.21.1, Main Steam Trip Valve (TV-1MS-101A) Partial Closure, 70% Flow, Revision No. 2, September 7, 1977; Date Performed:
April 2, 1978 OST 1.21.4, Main Steam Trip Valve (TV-1MS-101A), Revision No. 2,
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September 7, 1977; Dates Performed:
August 14, 1979; February 27, 1979; and January 14, 1979.
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OST 1.33.9, (0 Fire Protection System Inspection Test, Revision 9,
January 6, 1978; Dates Performed:
October 20, 1979; October 13, 1979; October 6, 1979; and September 30, 1979.
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OST 1.33.8, Weekly Diesel Engine Driven Fire Pump Operational Test, Revision 11, April 11, 1979; Dates Performed:
October 22, 1979; October 15, 1979; and October 8, 1979.
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OST 1.7.11, CHS and SIS Operability Test, Revision No. 4, June 15, 1976; Dates Performed:
October 21, 1977; February 19, 1978; and August 12, 1979.
c.
Findings (1) The licensee maintains a set of control copies of operating and surveillance procedures in the Control Room.
To ensure that the latest revision is used when performing a surveillance, a copy is made of the applicable surveillance procedure from the proce-dure maintained in the Controlled Copy book just prior to per-forming the surveillance.
The inspector noted that there were two books for one group of procedures located in the shift super-visors office and that in some cases, revisions posted to the same procedures in each book were different.
As a result of the above problem, OST 1.47.1, Containment Air Lock Test, was pe formed on November 15, 1979 using Revision 18 when Revision 2" Revision 19-21 not applicable to this proce-dure) had alree.:y been issued.
A previously issued Operations Manual Change Notice (OMCN) was posted to OST 1.47.1 Revision 18 covering a portion but not all of the change subsequently made by Revision 2 A licensee representative stated the problem was caused by the original Control Copy book being noted as missing and replaced by a second book.
Subsequently the missing book was returned to the shelf causing the two books to be used concurrently.
At the conclusion of the inspection, the licensee was in the process of ensuring that only one book was being maintained with the latest revisions.
The improper control of procedure revisions and control copies of procedures, and the performance of a surveillance test using a superseded procedure is contrary to Technical Specification 6.8.1 and BVPS-0M 1.48.3.E.5 and constitutes a deficiency level item of noncompliance (334/79-25-01).
(2) The record copy for performance of OST 1.11.3, Boron Injection Flow Path Valve Position Verification, for the month of February 1979 could not be located.
Log records indicate this surveil-lance was performed on February 5, 1979.
Data and procedures missing from plant files was identified as an item of noncompli-ance in Inspection Report No. 50-334/79-04 (334/79-04-01).
The misplacing of the above procedure apparently occurred before issuance of this noncompliance.
Since the licensee has stated in reply to the noncompliance, corrective action has been taken, the inspector considers no further action is required as a result of the identification of this missing procedure.
(3) For OST 1.13.1, 1A Quench Pump Flow Test (Monthly) performed on November 24, 1978, the pump bearing temperature readings did not stabilize for three consecutive tests to within 3 percent as required by the procedure.
Final procedure review noted the incomplete data and the procedure cover street was annotated that bearing temperatures should be reaccomplished.
However, through an apparent oversight, the pump bearing temperatures were not remeasured.
Based on review of other procedures and the fact that the recorded temperatures appeared to be well within specification, the inspector considered this an isolated case an no further action is required.
(4) OST's 1.21.1, 1.21.2, and 1.21.3 Main Steam Trip Valve...Partical Closure, 70% Flow, specifies as an initial condition that main-steam flow be 70% or less.
This steam flow restriction is per-missible by the Technical Specifications but is not required.
The inspector expressed a concern that if the plant were operat-ing a steam flows greater than 70% at the time this surveillance were due, it could be bypassed.
The licensee stated that this surveillance would be performed within its required frequency even if reductions in power level were necessary.
The inspector had no further questions concerning this matte.
4.
Inspector's Witnessing of Surveillance Testing a.
The inspector witnessed the performance of surveillance testing of selected components to verify the following:
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Surveillance test procedure was available and in use Special test equipment required by procedure was calibrated
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and in use Test prerequisites were met
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The procedure was adequately detailed to assure performance of a satisfactory surveillance
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Surveillance test was performed in acccrdance with proce-dural requirements b.
The inspector witnessed the performance of the following surveil-lance tests on November 14 and 15, 1979:
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MSP 12.02, P-LM-1008 Containment Pressure Protection Channel II Test
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OST 1.7.2, Boric Acid Transfer Pump (ICH-P-2B) Operational Test
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OST 1.7.8, Boric Acid Storage Tanks and RWST Level and Temperature Verification No items of noncompliance were identified.
5.
Technician Qualification The inspector reviewed the qualification records of four personnel having responsibility for surveillance testing of safety related components and equipment to verify that the individuals' experience level and training were in accordance with the guidelines of ANSI N18.1-1971, Selection and Training of Nuclear Power Plant Personnel.
No items of noncompliance were identified.
6.
Control Room Observations The inspector observed Control Room Operations on both day and evening shifts for facility operation in accordance with administrative and Technical Specification requirements.
No items of noncompliance were observe.
Unresolved Items An item about which more information is required to determine accept-ability is considered unresolved.
No unresolved items were identified in this report.
8.
Exit Interview The inspectors met with licensee representatives (denoted in para-graph 1) at conclusion of the inspection on November 16, 1979.
The inspection purpose, scope and findings were summarized.