IR 05000334/1980023
| ML19351D804 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/29/1980 |
| From: | Bettenhausen L, Caphton D, Troskoski W, Wiggins J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML19351D792 | List: |
| References | |
| 50-334-80-23, NUDOCS 8011200056 | |
| Download: ML19351D804 (10) | |
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U.S. NUCLEAR REGULATORY COMMISSION G
OFFICE OF INSPECTICN AND ENFORCEMENT Region I
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Report No. 80-23 Cocket No. 50-334
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Category C
License No. DPR-66 Priority
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Licensee:
Duquesne Light Company 435 Sixth Avenue Pittsburgh, Pennsylvania 15219 Facility Name:
Seaver Valley Unit 1 Inspection at:
Shippingport, Pennsylvania Inspection conducted:
August 4-7, 1980 jd/ 52d;tfE--.
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Inspectors:
Dr. L. Bettenhausen, Reactor Inspector date signed Sh S S
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W. Troskoski, Reactor Inspector cate signed
$&$ WYL 8/2G/22 ty)ns" ctor cate signed J. " gi P
Approved by:
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D. Caphto C Chief, Nuclear Support
'date signed Section #1, RO&NS Branch Inspection Summary:
Inspection on Aucust 4-7. 1980 (Recort No. 50-334/80-23)
Areas Inscected:
Routine, unannounced inspection oy regionally based inspectors of tne overall preoperational and startup test restart program; overall training program including general employee training, licensed operator requalification training, radiation worker training, craftsman and technician training; licensee action on previous inspection findings; and, tours of the facility.
The inspection involved 80 inspector-hours on-site by three regionally based NRC inspectors.
Results : Of the nine areas inspected, no apparent items of noncompliance or deviations were identified in eight areas; one apparent item of noncompliance (deficiency - failure to document the review of all abnormal procedures by all licensed operators - paragraph 3) was identified in one area.
I Region I Form 12 (Rev. April 77)
8013200 056
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DETAILS 1.
Persons Contacted
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V. Albert, DLC-CDN
- T. Burns, DLC Training Department R. Druga, Nuclear Shift Supervisor
- J. Griffin, DLC-CDN
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R. Hanson, Station Maintenance Supervisor
- 0. Hunkele, Senior QA F,gineer
- F. Lipchick, Senior Compliance Engineer J
J. Matsko, Nuclear Shift Operations Foreman
- A. Miria, Senior QA Engineer
- G. Sovick, Compliance Engineer
i P. Valenti, Station Engineering Group J. Vassello, Station Training Superviser
- J. Werling, Station Superintendent H. Williams, Chief Engineer R. Zabowski, Technical Supervisor J. Zwy:ack, NSC Consultant The inspectors also interviewed other licensee personnel during the course a
of the inspection. They included licensed operators, nuclear operators, temporary and permanent maintenance personnel, chemists and repairmen.
- Denotes those present during the exit inte^ view.
2.
Licensee Aciion on Previous Inscection Findinos (Closed) 334/79-23-01 Deficiency:
Six Licensed Operators Delinquent in Individual Study. The inspector reviewed individual training records, internal memoranda between the Training and Operations departments and interviewed the Station Training Supervisor concerning this matter. The Training Supervisor maintains a status board to track outstanding Individual
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Study Guides.
He informs the immediate supervisors of the completion status of delinquent personnel by internal memoranda. The inspector had no further
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questions in this area. The deficiency is considered closed.
3.
Nuclear Operator Training References:
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Beaver Valley Power Station Training Manual Section 2, Issue 2,
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Revision 1, dated August 30, 1979.
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a.
Initial Training
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Training of Nuclear Operators is conducted in accordance with the program specified in either Section 2.1 or 2.2 of the Beaver Valley Power Station Training Manual (TM). The program consists of a combin-ation of in-plant and classroom study.
Completion of training on a plant system qualifies the trainees to operate that system during nonnal, abnormal and emergency conditions.
The program culminates in a final review prior to the NRC licensing examination. The inspector interviewed two non-licensed personnel to ascertain the quality of training.
No items of noncompliance were identified.
b.
Licensed Operator Requalification Training The inspector reviewed the Requalification Training program to assure compliance with 10 CFR 55 Appendix A requirements.
Beaver Valley
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Power Station Training Manual, Section 2.2 establishes the program.
It consists of:
A series of preplanned lectures taught in 6 yearly modules.
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Simulated / walk-through performance training.
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On-the-jcb training including reactivity control manipulations.
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Individual study.
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The inspector reviewed lesson plans for adequacy of content, interviewed licensed operators and senior cperator to determine the quality of instruction, and reviewed the individual training records for each licensed operator and senior operator.
10 CFR 55 Appendix A requires that all licensed operators and senior operators review all abnormal and emergency procedures on a regularly scheduled basis. Operators review emergency procedures at Beaver Valley once a year during Module 5 of the Requalification Training Program. The operators individually review these emergency procedures
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and their knowledge is tested on a randem basis utilizing a control room mock-up maintained by the Training Department.
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Abnonnal procedures are covered in lectures conducted during each module. The inspector reviewed training schedules for thd previous
two years. There was no direct evidence available that all. abnormal procedures were reviewed with all licensed operators and senior operators. This failure constitutes an item of noncompliance at the deficiency level (334/80-23-01).
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The inspector also noted that a number of individual records indicated that the May 1980 Annual Examination results were not reviewed by the Station Chief Engineer and the Station Superintendent as required by Section 12.2.2.6.1 of the Beaver Valley Station FSAR. The inspector informed the licensee that it was expected that all reviews would be completed prior to the start of the next training cycle.
The licensee agreed to complete the reviews. The completion of the examination reviews will be verified during a future inspection.
(334/80-23-02)
c.
Program Review The inspector noted that a revision to Section 2 of the Training Manual has been prepared and is being reviewed.
This new revision incorporates the additional program requirements specified in the March 28, 1980 letter from Mr. Denton of NRR to all licensees. The licensee agreed to have the revision implemented before startup of Unit 1.
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implementation of the revised training program will be verified during a future inspection.
(334/80-23-03)
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4.
General Emoloyee Training References:
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BVPS TM Section 1.2, Station Orientation Training Issue 2. February
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i 15, 1976 All personnel assigned to BVPS, including temporary and service personnel, are required to attend Station Orientation Training.
The program consists of instruction in the following areas:
General Description of Plant and Facilities
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Job-Related Procedures and Instructions
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Radiological Health and Safety Program
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Station Emergency Plan
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Industrial Safety Program
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Security Program
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Quality Assurance Program
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.All personnel are appraised of the information contained in Regulatory
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i Guide 8.13 Instructions Concerning Prenatal Radiation Exposure.
Female employees subsequently receive additional instruction in this area while
attending t separate course.
No items of. noncompliance were identified.
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Radiation Worker.Traininq
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Reference:
BVPS Training Manual, Issue 2. dated February 15, 1976, Section 3.3
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All unescorted personnel who perform work within radiation areas are
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required to receive Radiation Worker Training. The program consists of l
a series of lectures, video tapes and slides, and practical demonstrations.
Satisfactory completion of this training qualifies personnel to wear respira-j tory devices. The inspector reviewed the respiratory qualification of opera-l ting personnel.
It was noted that all operating personne' were not oualified
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to wear all types of respirator devices. This finding was identified to representatives of the licensee and the completion of qualifications by(334/80-i necessary personnel.4111 be followed during a subsequent inspection.
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No items of noncompliance were identified.
6.
Craftsmen and Technician Training References:
r BVPS Training Manual, Issue 2, Section 4.1
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BVPS Training Manual Issue 2, Revision 2, Section 6
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The inspector reviewed training programs and records and conducted inter-
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i views with selected individuals in the following areas: maintenance mechanics, meter and control repairmen and chemistry technicians.
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following paragraphs briefly describe these programs and the inspection findings.
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Maintenance Craftsmen The training program for mechanics, machinists, welders and electricians
is specified in Section 6 of the Training Manual.
It consists of a
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maintenance orientation follcwed by craft-specific training. At the time of-the inspection, the program had not been implemented due to
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manpower shortages.
Implementation of the program will be reviewed
in a-future inspection. -(334/80-23-05)
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No items of noncompliance were noted, b.
Meter and Control Repair-nen (MCR)
In addition to the program specified in Section 6 of the Training Manual, MCR's receive a basic training course conducted by the corporate organization. They receive basic skills required to fulfill a position in either the Beaver Valley Power Station or any of the fossil fuel stations operated by the licensee.
Implementation of Section 6 of
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I the Training Manual will result in the MCR's receiving more plant-specific training designed to improve their capabilities in the area of nuclear plant instrumentation and. controls.
No items of noncompliance were identified.
c.
Chemist Training All station chemists are eligible to participate in the Chemists'
Training Program. The program consists of video tape courses, informal lecutures, laboratory work and individual study. A qualification card is used to track the status of program completion for each individual.
No items of noncompliancs w:ee identified.
7.
Precoerational and Startuo Test Restart Procram Status The inspectors met with licensee representatives frem Construction Department Nuclear (CDN), Station Engineering, and Beaver Valley Power Station Opera-tions, and held discussions on the follcwing items and areas:
Construction schedule;
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Testing schedule;
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. Critical flow path;
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System turnover; and,
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Interface between construction and preoperational testing.
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Preccerational and Startuo Test Restart Procram a.
Test Program Imolementation i
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Discussion:
The inspectors met with members of construction, operations, &nd management and held discussions on the preoperational and startup test restart program implementation; including the following areas:
Test program description and conduct;
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Test organization;
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Test program administration;
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Test document control; and,
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Design changes and modifications.
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The items and concerns discussed and subsequently examined in those areas included:
Jurisdictional controls over the system, component, or structure
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modification during construction, testing, and turnover to operations;
Organizational interface between the construction, testing, and
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station operaticns groups; Methods to assure that the test procedure is current prior to
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use; Methods to change a tist procedure Curing the conduct of a
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test; Criteria for interruption of a test and continuation of an
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interrupted test; Methods to document significant events, unusual conditions,
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or interruptions to testing; Methods for identifying deficiencies, documenting their resolu-
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tions, and documenting retesting; Document control of engineering drawings;
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Methods for initiating, reviewing, and approving requests for
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design changes and modifications; Review of proposed design changes for potential FSAR and
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Unreviewed Safety Question impact; and,
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2 Administrative controls to assure that necessary FSAR and/or
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j technical specification changes will be made.
References:
Construction Department Nuclear Power Plant Procedures Manual;-
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Design Change Status List;
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Joint Planning / Scheduling Group;
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Regulatory Guide 1.68, Initial Test Program for Water-Cooled
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Nuclear Power Plants; Station Engineering Procedures; and
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Test Program Administration.
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Design Change Packages reviewed while in various stages of work completion were:
OCP-94, Automatic Transfer frem SI Mode to Recirculation Mode
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Following an SIS Signal Test Specifications MSP 13.01-13.04, Calibrate RWST Level Loop Instrumentation IO1-SSPS-3. Functional Test of SSPS (Solid State Protection System)
GTP-ET-1, 2, Verify Valve Contiols BVT 1.2-2.11.1, SIS Automatic Switchover to Recirculation DCP-130, Auxiliary Feed Pump Recire Piping Modifications
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MWP (Modification Work Package) 130-1, Pipe Supports ER (Equipment Release) 130-1, with open items duly listed.
CDN Test Package, with cpen items duly listed.
MWP 130-10, with open items duly listed.
SVT 1.2-2.24.1, Motor Driven Pumps
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BVT 1.2-2.24.2, Turbine Driven Pumps Test Specifications OCP-188, LHSI-Flow Eliminator and Material Changes
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Test Specification 188-1 DCP-189, Rearc Containment Spray, LHSI Pumps NPSH Modifications
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Test Specification 189-1 OCP-190, Steamline Break Protection (WRAPS)
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Test Specifications Acceptance Criteria ER 190-1, Computer Demultiplexer Rack
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ER 190-2, Control Board Demultiplexer Rack ER 190-3, Primary Process Racks, No. 13, 16, 17 ER 190-4, Primary Process Racks No. 18, 25, 26 ER 190-5, New Primary Process Rack and Wiring Test Packages:
ER 190-1, Wiring Test ER 190-2, Computer Wiring Checkout ER 190-3, Loop Functional Checks ER 190-4, Loop Functional Checks ER 190-5, Occuments DCP-249, 4610V Bus Undervoltage Relay
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Test Specification DCP-293, Subcooled Margin Meter (NUREG-0578)
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Test Specifications The inspectors examined the administrative controls on seven Design Change Packages in differing status of completion.
Particular emphasis was placed upon program implemertation from the design inception phase through the construction-operations turnover interface.
As a result of reviews of references, interviews and discussions with cognizant personnel, no discrepancies were noted at this time.
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Plant Tour The inspector toured areas inside the turbine building, toured the control room and exterior areas inside the protected area fenceline.
During a tour of the turbine bufiding the inspector discovered that the 150 pour...
wheeled fire extinguisher numbered 236A did not display evidence that the routine surveillance test, OST 1.33.15 had been conducted in July.
A review of the completed OST showed that the proper inspection had, in fact, been made of all fire extinguisher units on the 639 foot level of the
turbine building.
A representative of the licensee stated that during his review of the matter, two extinguisher units were found to bear the same equipment number on their OST tag.
The licensee agreed to correct the problems identified. The inspector had no further questions regarding this matter.
10.
Exit Interview
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The inspectors met with licensee representatives (denoted in Paragraph 1)
at the conclusion of the inspection on August 7, 1980.
The inspectors summarized the scope and findings of the inspection and discussed the apparent item of noncompliance (denoted in Paragraph 3).
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