IR 05000424/1986051
| ML20212A489 | |
| Person / Time | |
|---|---|
| Site: | Vogtle  |
| Issue date: | 07/22/1986 |
| From: | Livermore H, Rogge J, Schepens R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20212A483 | List: |
| References | |
| RTR-NUREG-0578, RTR-NUREG-0660, RTR-NUREG-0737, RTR-NUREG-578, RTR-NUREG-660, RTR-NUREG-737, TASK-1.A.1.2, TASK-1.C.3, TASK-1.C.4, TASK-2.K.3.01, TASK-TM 50-424-86-51, 50-425-86-23, NUDOCS 8607290006 | |
| Download: ML20212A489 (31) | |
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38 Eth UNITED STATES
q'o NUCLEAR REGULATORY COMMISSION
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REGION 18 o
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j 101 MARIETTA STREET, N.W.
- ATLANTA, GEORGI A 30323
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Report Nos.:
50-424/86-51 and 50-425/86-23 Licensee: Georgia Power Company P.O. 8cx 4545 Atlanta, GA 30302 Docket Nos.:
50-424 and 50-425 License Nos.: CPPR-108 and CPPR-109 Facility Name: Vogtle 1 and 2 Inspection Cond ted: jMay 4 - June 0, 1986 Inspectors: h/AW FTAM L
b H. H. L&ermore, Senior Resident
06te S4gned Insp ctor, C ns ction
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LA 6-74 >la J. F. Rddge, Senior Resident f
O'ats Sifgned Inspe tor, Op atioris L
i%A F-74 v/K
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R. J. S hkpens, Resident D6te Si@ned Inspect r, Ope ations & Constr ction Approved By: {kN
/ VmNL & GV
EN M.'V. Sifkule, Section Chief Ofte Sfgned
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Division of Reactor Projects
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SUMMARY Scope: This routine, unannounced inspection entailed Resident Inspection in the following areas: containment and safety related structures, piping systems and supports, safety related components, auxiliary systems, electrical equipment and j
cables, instrumentation, preoperational test program, quality programs and administrative controls affecting quality, and follow-up on previous inspection identified items. Readiness Review Module 7 was examined.
Results: No violations or deviations were identified.
8607290006 860723 PDR ADOCK 05000424 G
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REPORT DETAILS 1.
Persons Contacted-
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Licensee Employees R. E. Conway, Senior Vice-President, Vogtle Project Director
- 0. O. Foster, Vice-President, Project Support
- H. Pinson, Vice-President, Project Construction W. T. Nickerson, Assistant to the Project Director
- W. McManus, Readiness Review
- H. Googe, Project Construction Manager
- G. Bockhold, Jr., General Manager Nuclear Operations
- H. P. Walker, Manager Unit Operations
- M. Bellamy, Manager Test & Outage
- C. W. Hayes, Vogtle Quality Assurance Manager C. E. Belflower, Quality Assurance Site Manager - Operations E. D. Groover, Quality Assurance Site Manager - Construction
- S. D. Haltom, Quality Assurance Audit Supervisor D. M. Fiquett, Project Construction Manager - Unit 2
- C. Harbin, Manager Quality Control
- J. N. Fugate, Project Compliance Coordinator
- C Gabbard, Regulatory Specialist C. F. Meyer, Operations Superintendent T. Dannemiller, Test Engineer R. M. Odom, Plant Engineering Supervisor
- L. Coursey, Maintenance Superintendent
- M. A. Griffis, Superintendent - Maintenance N. R. Harris, Quality Control Assistant Manager W. R. Duncan, Readiness Review D. McCary, Engineering Supervisor, GPC/PKF
- G. E. Spell, Quality Assurance Engineer / Support Supervisor S. A. Bradley, NSEG Member
- V. J. Agro, Superintendent Administration Other licensee employees contacted included craftsmen, technicians, supervision, engineers, inspectors, and office personnel.
Other Organizations i
H. M. Handfinger, Preoperational Test Superintendent - Bechtel i
D. L. Kinnsch, Project Engineering - Bechtel
- Attended Exit Interview
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2.
Exit Interview (30703C)
The inspection scope and findings were summarized on June 30, 1986 with those persons indicated in paragraph 1 above. The inspector described the areas inspected and discussed in detail the inspection finding listed below.
No dissenting comments were received from the licensee. The licensee did not identify as proprietary any of the materials provided to or reviewed by the inspector during this inspection, 86-09-02 (Closed) Inspector Followup Item (IFI) " Review Licensee Action Pertaining to the Restoration of Safety Related Equipment" - Paragraph 4.
85-21-01 (0 pen) IFI " Review Revision to Class 1E Battery Maintenance Procedures" - Paragraph 4.
86-51-01 (0 pen) IFI " Review Licensee Action for TMI Item I.C.3"
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Paragraph 22.
86-51-02 (0 pen) IFI " Review Licensee Action for TMI Item I.C 4"
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Paragraph 22.
86-51-03 (0 pen) IFI " Review Management Directive Pertaining to TMI Item I.A.1.2" - Paragraph 22.
86-51-04 (0 pen) IFI " Review Licensee Procedure Changes to 10000-C and 1006-C" - Paragraph 23.
86-51-05 (0 pen) IFI " Posting of NRC-3 and Part 21 Forms" - Paragraph 9.
I.C.3 (0 pen) IFI " Shift Supervisor Responsibilities" - Paragraph 22.
I.C.4 (0 pen) IFI " Control-Room Access" - Paragraph 22.
I.A.1.2 (0 pen) IFI " Shift Supervisor Administrative Outies" - Paragraph 22.
II.K.3.1 (Closed) IFI " Installation and Testing of Automatic Power-0perated Relief Valve Isolation System" - Paragraph 22.
The following NRC exit interviews were attended during the inspection period by a resident inspector:
Date Name-May 16 R. W. Wright, R. D. Gibbs R. A. Moore May 23 T. D. Gibbons J. J. Lenahan June 5 S. J. Vias
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Date Name June 6 G. L. Troup L. E. Nicholson R. W. Wright J. B. Macdonald June 13 C. Connell June 20 J. R. Harris W. Kleinsorge L. H. Jackson, R. D. Gibbs June 27 L. E. Nicholson G. R. Wiseman 3.
Licensee Action on Previous Enforcement Matters (92702)
Not inspected.
4.
Followup on Previous Inspection Items (92701)
(0 pen) 50-424/85-21-02 IF1, " Review Revision to Class 1E Battery Maintenance Procedures".
This item was reviewed while pursuing selected readiness review procedures.
Discussions were held with maintenance engineering pertaining to incorporation of all requirements of IEEE 450-1975.
The inspector noted that the procedures had improved since the first identifica-tion of this item, however the licensee is still continuing to revise these procedures.
(Closed) 50-424/86-09-02 IFI, " Review Licensee Action Pertaining to the Restoration of Safety Related Equipment". The Resident Inspector met with the licensee's Maintenance Superintendent and was informed of the following action taken by the licensee. Maintenance Procedure No. 20004-C, Rev. 2
" Control of In-Process Materials" has been revised to add a section on entitled equipment integrity (Section 4.4).
This section places administra-tive controls on equipment restoration for work in progress when left unattended for more than one shift. The inspector has reviewed the revised procedure and verified that valves 1HV-88048, 1HV-8812A, 1HV-8812B, and 1HV-2138 have been restored properly after maintenance.
5.
Allegations Allegation RII 85-0016-031, Installation of Bottom Mounted Instrumentation Tubing (BMI) through concrete.
The inspector performed a surveillance of the BMI tunnel area located under and adjacent to the Unit 1 Reactor Vessel.
The BMI tubes (58) exit the bottom of the Reactor Vessel, travel in an arc laterally at elevation 143 (approx.), go diagonally upwards in the BMI tunnel, and are installed in the bottom of the BMI Seal Table (steel) at elevation 193 (approx.). The BMI
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tubes are supported by rack supports in numerous places under the vessel and in the vertical BMI shaft.
The shaft is a continuous horizontal and vertical concrete tunnel some 85 feet long, with no walls or other parti-
tions that would block tubing installations. The BMI tubes do not penetrate any concrete walls; they exit the Reactor Vessel and enter (are installed in) the Seal Table some 85 feet away. Through personal observation, the inspector could not find any BMI penetrations through concrete or any other anomalies in the tunnel area.
The inspector also reviewed civil and
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mechanical construction drawings, and did not find any cases of BMI tubing j-penetrating concrete.
The allegation is considered unfounded and is closed.
Allegation RII-86-A-0026:
Employees performed work on a Limitorque Motor Operated Valve [MOV] without a data sheet, performed electrical cable conductor continuity checks without using the specified instrumentation, and these two items were indicative of deficiencies on the part of employees j
that may have gone undetected.
This allegation was initially received by the Vogtle Quality Concerns group through their taped telephone system and the US-NRC was also be contacted.
A review of plant records indicated that a limit switch in M0V 1HV-8471A was being removed, cleaned and greased without adequate documentation.
As a result of this part of the allegation work was stopped, a Maintenance work Order (MWO), was initiated and Vogtle Electric Generating Plant
[VEGP] Quality Control Inspection Report [QCIR] was prepared for the valve.
The MWO was closed out on February 13, 1986 and the QCIR, was signed out on February 10, 1986. Additional review of plant records indicated that plant personnel identified MOV 1HV-8809B as having been worked without adequate documentation. An MW0, was initiated and Nuclear Operations Quality Control Hold Point Sheet (N0QCHPS) was prepared.
The MWO was closed out in April 11, 1986 and the N0QCHPS was signed out on April 8,1986.
The plant
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personnel indicated that the work performed on the MOV without adequate documentation did occur. The plant personnel's action of stopping the work, initiating adequate documentation and identifying an addition MOV shows that corrective action was taken.
Statements made by plant personnel and comments by plant management indicated that cable conductor continuity checks were being performed without using the specified instrumentation. A review of procedure E-20, Revision 9, indicated that a cable conductor continuity check is to be i
performed. However, a review of Revision 10 of E-20, dated April 9,1986, indicated that an additional comment was added, which states, in part, that telephones were not to be used for continuity checks.
Revising the proce-dure to clarify instrumentation usage also indicated corrective action, however, identifying where the use of nonspecified instrumentation occurred could not be determined.
The plant management stated all systems would receive operability tests and if the condition for which the check is performed exists it would be identified during these tests.
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The plant personnel indicated and plant management stated that prior practices in this area did occur as stated.
It was noted that activities covered by the Construction Acceptance Testing (CAT) program are formally proceduralized, but do require clarification at times. Although the alleged activities did occur, they were adequately analized and corrective action was initiated.
The allegation as to the MOV and instrumentation was substantiated in that the events did occur as stated. It was valid in that corrective action was taken as a result of the allegation. The corrective action taken by plant personnel. appears to be adequate, therefore this allegation is considered closed.
6.
General Construction Inspection - Units 1 & 2 Periodic random surveillance inspections were made throughout this reporting period in the form of general type inspections in different areas of both facilities. The areas were selected on the basis of the scheduled activi-
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ties and were varied to provide wide coverage.
Observations were made of activities in progress to note defective items or items of noncompliance with the required codes and regulatory requirements. On these inspections, particular note was made of the presence of quality control inspectors, supervisors, and quality control evidence in the form of available process sheets, drawings, material identification, material protection, performance of tests, and housekeeping. Interviews were conducted with craft personnel, supervisors, coordinators, quality control inspectors, and others as they were available in the work areas. The inspector reviewed numerous construc-tion deviation reports to determine if requirements were met in the areas of documentation, action to resolve, justification, and approval signatures in accordance with GPC Field Procedure No. GD-T-01.
The inspector attended the following GPC meetings as an observer for informational purposes:
Finalization Program Presentations of May 19, June 2, and June 20,
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1986.
Authorized Nuclear. Inspector Supervisien Entrance and Exit Meetings of
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June 12, 1986.
Project Management Board Meeting on June 6, 1986,
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i Pipe Break Analysis Enforcement Conference (Region II) on June 23,
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Monthly Drug Program Administration Meeting on June 30, 1986.
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The inspector participated in an inspection of the Limitorque Motor Valves (M0V's) with a representative from NRC Inspection and Enforcement Vendor Program Branch and licensee representatives. This inspection was a followup to the licensee's construction deficiency report No. M87 concerning burn
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damage to internal AC wiring from energized space heaters.
The following Limitorque M0V's were inspected on Unit No. 2:
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Model No.
Condition
2HV-2135 SMB000 Wires Burned Against Space Heater 2HV-2139 SMB000 No Wires Burned 2HV-1807 SMB000 Wires Burned Against Space Heater 2HV-1831 SMB000 Wires Burned Against Space Heater No violations or deviations were identified.
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7.
Fire Prevention / Protection and Housekeeping Measures - Units 1 & 2 (42051C)
The inspector observed fire prevention / protection measures throughout the inspection period. Welders were using welding permits with fire watches and extinguishers.
Post indicator valves were being maintained in the open
position. Fire fighting equipment is in its designated areas throughout the
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plant.
The inspector reviewed and examined portions of the following procedures
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pertaining to the fire prevention / protection measures and housekeeping measures to determine whether they comply with applicable codes, standards, NRC Regulatory Guides and licensee commitments.
-SD-T-05, Rev 6 Fire-Protection Equipment Inspection and Testing-GD-T-15, Rev. 5 Welding and Cutting-GD-T-17, Rev. 3 Housekeeping The inspector observed fire prevention / protection measures in work areas containing safety related equipment during the inspection period to verify the following:
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Combustible waste material and rubbish was removed from the work areas
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as rapidly as practicable to avoid unnecessary accumulation of combustibles.
Flammable liquids are stored in appropriate containers and in desig-
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nated areas throughout the plant.
Cutting and welding operations in progress have been authorized by an
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appropriate permit, combustibles have been moved away or safely
covered, and a fire watch and extinguisher was posted as required.
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accordance with applicable requirements.
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No violations or deviations were identified.
8.
Structural Concrete - Units 1 & 2 (47053C)
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Procedure and Document Review The inspector re' viewed and examined portions of the following proce-dures pertaining to the placement of concrete to determine whether they comply with applicable codes, standards, NRC Regulatory Guides and licensee commitments.
-CO-T-02, Rev. 17 Concrete Quality Control-CD-T-06, Rev. 9 Rebar and Cadweld Quality Control-CD-T-07, Rev. 8 Embed Installation and Inspection-CD-T-20, Rev. 6 Installation and Inspection of Trumpets, Rigid Extensions, and Duct Sheathing b.
Installation Activities The inspector witnessed portions of the concrete placement indicated below to verify the following:
(1)
Forms, Embedment, and Reinforcing Steel Installation
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Forms were properly placed, secure, leak tight and clean.
Rebar and other embedment installation was installed in
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accordance with construction specifications and drawings, secured, free of concrete and excessive rust, specified distance from forms, proper on-site rebar bending (where applicable) and clearances consistent with aggregate size.
(2) Delivery, Placement and Curing Preplacement inspection was completed and approved prior to
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placement utilizing a
Pour Card (Procedure Exhibit
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CD-T-02*18).
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Construction joints were prepared as specified.
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Proper mix was specified and delivered.
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Temperature control of the mix, mating surfaces, and ambient
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were monitored.
Consolidation was performed correctly.
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Testing at placement location was properly performed in
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accordance with the acceptance criteria and recorded on a Concrete Placement Pour Log (Procedure Exhibit CD-T-02*20).
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Adequate crew, equipment and techniques were utilized.
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Inspections during placements were conducted effectively by a sufficient number of qualified personnel.
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Curingmethodsandtempc$a'turewasmonitored.
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(3) Rebar Splicing g
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j The inspector witnessed cadwelding operations to veri fy the i
following:
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Inspections are performed during and after splicing by
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qualified QC inspection personnel.
Each splice was defined by a unique number consisting of the
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bar size, splice type, the position,'the operator's symbol, and a sequential number.
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Process and crews are qualified.
.The sequential number and the operator's symbol are marked on
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call completed cadwelds.
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The inspector also conducted randem '1nspections of completed cadwelds to verify the following:
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Tap hole does not contain slag, blow out, or porous metal.
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Filler metal was visible at both ends of the splice sleeve
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and at the tap hole in the center of the sleeve. No voids i
were detected at the ends of the, sleeves.
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The sequential number and the operator's symbol are marked on all completed cadwelds.
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No violations or deviations were identified.
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Title 10 Posting Requirements - Units 1 & 2 (913000)'
Title 10 Regulations state in part that the NRC Form 3 and Part 21 Defect
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Reporting Requirements shall be posted in sufficient locations to permit employees to observe a copy on the way to and from their place of work.
The inspector performed a walkdown surveillance of all posted locations on site. The walkdown was in conjunction with the monthly checklist walkdown review performed by Operations and Construction personnel. Seven main areas
of personnel entry and exit on the constructicn side of the site were j
posted, as were additional engineering and administrative areas. The main building areas of administration, service, maintenance, warehouse, and
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training on the operations side of the site were posted. All areas were visible to employees.
In order to insure that postings are present and visibit to all site employees, the following areas are recommended for additional postings:
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Construction Vault Area of Field Office Bldg.
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GPC Receiving Inspection Warehouse south entrance to parking lot.
Auxiliary Building Main Tool Room
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New Hire Tool Issue Building
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Weld Rod Issue Buildings (WMDC)
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Main Contractor Office Buildings (e.g.-Pullman, PKF, Cleveland,
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Walsh,etc.)
Containment #2 Equipment Hatch area
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Operations
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Trailer City in southeast site parking lot WISCO and Crane Valve trailers north of Maintenance Bldg.
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Maintenance Planning Trailer complex
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Startup Support Group fabrication shop and office area (CBI)
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Any other Contractor offices
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l These areas were discussed with the appropriate Operations and Construction Licensee personnel.
This item is identified as Inspector Followup Item 50-424/86-51-05, " Posting of.NRC-3 and Part 21 Forms".
No violations or deviations were identified.
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10. Containment (Steel Structures and Supports) - Units 1 & 2 (48053C)
Periodic inspections were conducted to observe containment steel and support installation activities in progress, to verify the following:
Components were being properly handled (included bending or straight-
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Specified clearances were being maintained.
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Edge finishes and hole sizes were within tolerances.
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Control, marking, protection and segregation were maintained during
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storage.
Fit-up/ alignment meets the tolerances in the specifications and
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drawings.
No violations or deviations were identified.
11. Safety-Related Structures (Structural Steel and Supports) - Units 1 & 2 (48063C)
Periodic inspections were conducted to observe construction activities of
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Materials and components were being properly handled to prevent damage.
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Fit-up/ alignment were within tolerances in specifications and drawing
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requirements.
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Bolting was in accordance with specifications and procedures.
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Specified clearances from adjacent components were being met.
No violations or deviations were identified.
12. Reactor Coolant Pressure Boundary and Safety Related Piping - Unit 1 & 2 (49053C) (49063C) (37301)
Periodic inspections were conducted to observe construction activities of
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the Reactor Coolant Boundary and other safety-related piping installations inside and outside Containments.
Verifications included but were not limited to the following:
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Material and components were being properly handled and stored in order
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to prevent damage.
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Fit-ups and alignments were within tolerances per specifications and drawings.
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Specified clearances from pipe to pipe and adjacent components were met.
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Piping was installed and inspected in accordance with applicable drawings, specifications, and procedures'.
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Those people engaged in the activity are qualified to perform the
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applicable function.
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Drawing and specification changes (revisions) are being handled and used correctly.
During the inspection period, system walkdowns were performed to determine whether installations were as shown on approved drawings and in accordance with applicable construction specifications.
Specific system walkdowns included a walkdown of the following ASME Section III, Class I, II & III Piping as listed below:
P&ID REVISION PIPE RUN INSPECTED 1X4DB114, Rev. 20 Chemical & Volume Control System IX4DB115, Rev. 18 (CVCS) Letdown Through the Regenerative and Letdown Heat Exchanger 1X408116-1, Rev. 13 CVCS Positive Displacement Pump 1X4DB114, Rev. 20 Charging Through the Regenerative Heat Exchanger IX4DB116-2, Rev. 11 CVCS Centrifugal Charging Pumps Train A&B Suction & Discharge Piping 1X4DB117, Rev. 16 CVCS Boron Thermal Regeneration System Letdown Through Letdown Reheat Heat Exchanger Inspections were performed on a random daily basis. Specific areas examined during the pipe run walkdown for compliance with the applicable piping &
instrumentation drawings and the Plant Design and Instrumentation Construc-tion Specification No. X4AZ01 were as follows:
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Vent and Drain Connections and Locations
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Instrumentation Connections and Locations Valve Installation and Orientation
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Line Size and Location Fittings Type and Location
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Pipa/ Valva / Fitting par Piping Material Spacification 3'
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Hanger Locations and Types The inspector conducted a review of the documentation (fabrication sheets)
for the following spools:
1-1208-099-S-02 1-1208-144-S-01 1-1208-144-S-02
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1-1208-144-S-03 1-1208-144-S-05 1-1208-146-S-02 1-1208-146-S-05 No violations or deviations or deviations were identified.
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13.
Reactor Coolant Pressure Boundary and Safety Related Piping Welding - Unit 1
& 2 (55073C) (55083C)
Periodic inspections were conducted during daily plant surveillances on safety-related pipe welding at various stages of weld completion.
The purpose of the inspection was to determine whether the requirements of applicable specifications, codes, standards, work performance procedures and QC procedures are being met as follows:
Work was conducted in accordance with a process sheet which identifies
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the weld and its location by system, references procedures or instruc-tions, and provides for production and QC signoffs.
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Welding procedures, detailed drawings and instructions, were readily available in the immediate work area and technically adequate for the welds being made.
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Welding procedure specification (WPS) were in accordance with the applicable Code requirements and that a Procedure Qualification Record (PQR) is referenced and exists for the type of weld being made.
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Base metals, welding filler materials, fluxes, gases, and insert materials were of the specified type and grade, have been properly inspected, tested and were traceable to test reports or certifications.
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Purge and/or shielding gas flow and composition were as specified in the welding procedure specification and that protection was provided to shield the welding operation from adverse environmental conditions.
Weld joint geometry including pipe wall thickness was specified and
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that surfaces to be welded have been prepared, cleaned and inspected in accordance with applicable procedures or instructions.
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A sufficient number of adequately qualified QA and QC inspection personnel were present at the work site, commensurate with the work in progrecs.
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The weld area cleanliness was maintained and that pipe alignment and fit-up tolerances were within specified limits.
Weld filler material being used was in accordance with welding speci-
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fications, unused filler material was separated from other types of material and was stored properly and that weld rod stubs were properly removed from the work location.
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That there were no evident signs of cracks, excessive heat input, sugaring, or excessive crown on weids.
Welders were qualified to the applicable process and thickness, and
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that necessary controls and records were in place.
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No violations or deviations were identified.
14.
Reactor Vessel, Integrated Head Package, and Internals - Unit 1 & 2 (50053C and 50063C)
Periodic Unit 1 inspections consisted of examinations of the Reactor Vessel and the installed integrated head package. The Unit 2 inspections consisted of examinations of the Reactor Vessel installed in containment, the Reactor Vessel head with the installed control rod drive mechanisms that are located on the refueling floor, and the upper lower internals in its designated laydown area.
Inspections also determined that proper storage protection practices were in place and that entry of foreign objects and debris was prevented.
Periodic inspections were conducted during the Unit II trial fit-up of the core barrel to the Reactor Vessel. This operation consisted of lowering the core barrel (CB) for the first time on site into the Reactor Vessel (RV) to
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i record the following measurements:
t Clearance dimensions of the lower radial core support key
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Hot leg nozzle cap measurements between the CB and RV, and
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Secondary core support base line
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i The inspection also included witnessing and review of the following Nuclear Installation Services Company (NISCO) work packages:
NISCO Process Sheet No. 2-105-17, Rev. O Installation of the Reactor
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Head and Vessel Alignment Pins
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NISCO Process Sheet No. 2-185-25-1, Rev. O Modify Fuel Transfer Bellows Assembly No violations or deviations were identified.
15.
Safety Related Components - Units 1 & 2 (50073C)
The inspection consisted of plant tours to observe storage, handling, and protection; installation; and preventive maintenance after installation of safety-related components to determine that work is being performed 'in i
accordance with applicable codes, NRC Regulatory Guides, and licensee commitments.
During the inspection the below listed areas were inspected at various times during the inspection period to verify the following as applicable:
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Storage, environment, and protection of components were in accordance with manufacturer's instructions and/or established procedures.
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Implementation of special storage and maintenance requirements such as:
rotation of motors, pumps, lubrication, insulation testing (elec-trical), cleanliness,etc.
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Performance of licensee / contractor surveillance activities and
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documentation thereof was being accomplished.
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Installation requirements were met such as: proper location, placement, orientation, alignment, mounting (torquing of bolts and expansion anchors), flow direction, tolerances, and expansion clearance.
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Appropriate stamps, tags, markings, etc. were in use to prevent oversight of required inspections, completion of tests, acceptance, and the prevention of inadvertent operation.
Safety-Related piping, valves, pumps, heat exchangers, and instrumentation were inspected in the following Unit 1 and 2 areas on a random sampling basis throughout the inspection period:
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Residual Heat Removal Pump Rooms
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Diesel Generator Building
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Auxiliary Feedwater Pumphouse
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Containment Spray Pump Rooms
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Pressurizer Rooms Main Coolant Pump Areas
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Steam Generator Areas
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Safety Injection Pump Rooms
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RHR and CS Containment Penetration Encapsulation Vessel Rooms
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Component Cooling Water (CCW) Heat Exchangers, Surge Tanks & Pump Rooms
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Cable Spreading Rooms
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Accumulator Tank Areas
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Chemical and Volume Control System (CVCS) Letdown Heat Exchanger Pump Room
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Battery & Charger Rooms
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Nuclear Grade Piping, Valves & Fittings Storage Areas
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Spent Fuel Puvi Heat Eactienger Rooms
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Pressurizer Relief Tank Area
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CVCS Centrifugal Charging Pumps & Positive Displacement Pump Rooms
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Bottom Mounted Instrumentation (BMI) Tunnel and Seal Table Area i
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BMI and Supports Under Reactor Vessel
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NSCW Tower Pump Rooms and Pipe Tunnels
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Containment, Auxiliary Building, Control Building, and Fuel Handling Building auxiliary (secondary) areas No violations or deviations were identified.
16.
Safety Related Pipe Support and Restraint Systems - Units 1 & 2 (50090C)
Periodic random inspections were conducted during the inspection period to I
observe construction activities during installation of safety-related pipe j
supports to determine that the following work was performed in accordance i
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with applicable codes, NRC Regulatory Guides, and licensee commitments:
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Spring hangers were provided with indicators to show the approximate
" hot" or " cold" position, as appropriate.
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No deformation or forced bending was evident.
Where pipe clamps are used to support vertical lines, shear lugs were
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welded to the pipe (if required by Installation Drawings) to prevent slippage.
Sliding or rolling supports were provided with material and/or
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lubricants suitable for the environment and compatible with sliding contact surfaces.
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Supports are located and installed as specified.
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The surface of welds meet applicable code requirements and are free from unacceptable grooves, abrupt ridges, valleys, undercuts, cracks, discontinuities, or other indications which can be observed on the welded surface.
No violations or deviations were identified.
17.
Electrical and Instrumentation Components and Systems - Units 1 & 2 (51053C)
(52153C)
Periodic inspections were conducted during the inspection period to observe safety-related electrical equipment in order to verify that the storage, installation, and preventive maintenance was accomplished in accordance with applicable codes, NRC Regulatory Guides, and licensee commitments.
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During the inspection period inspections were performed on various pieces of electrical equipment during storage, installation, and cable terminating phase in order to verify the following as applicable:
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Location and alignment
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Type and size of anchor bolts
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Identification
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Segregation and identification of nonconforming items
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Location, separation and redundancy requirements l
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Equipment space heating
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Cable identification
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Proper lugs used
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Condition of wire (not nicked, etc.), tightness of connection
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Bending radius not exceeded
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Cable entry to terminal point
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Separation l
The inspector conducted a walkdown of the following instrumentation tubing to verify proper installation per Pullman Power Procedure No. 1X-40.
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Pressurizer Pressur Transmitters-PT0457 and PT0458 Pressurizer Level Transmitters-LT0461 and LT0462 Reactor Coolant System Loop 1 Flow Transmitters-FT0414, FT0415, and FT0416 The inspector also conducted an inspection of the following Reactor Coolant System (RCS) Loops 2,' 3 & 4 Flow Transmitter (FT) Root Valve Installation per Reactor Coolant Loop Piping Composite Drawing 1X4DL4A17, Rev.18, DCN
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RCS Loop No. 2 FT's 0424, 0425, and 0426
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RCS Loop No. 3 FT's 0434, 0435, and 0436
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RCS Loop No. 4 FT's 0444, 0445, and 0446 The inspector noted that the composite drawing does not reflect the correct as-installed location for RCS Loop #2 FT's 0424 & 0426 & RCP Loop #3 FT0434
& 0436.
The licensee's response was not complete at the end of this inspection; therefore this matter will be followed up in the next inspection report.
No violations or deviations were identified.
~18.
Electrical and Instrumentation Cables and Terminations - Unit 1 (51063C)
(52063C)
a.
Raceway / Cable Installation The inspector reviewed and examined portions of the following proce-dures pertaining to raceway / cable installation to determine whether they comply with applicable codes, NRC Regulatory Guides and licensee commitments.
ED-T-02, Rev. 8 Raceway Installation
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ED-T-07, Rev. 9 Cable Installation Periodic inspections were conducted to observe construction activltles of Safety Related Raceway / Cable Installation.
In reference to the raceway installation, the following areas were inspected to verify compliance with the applicable requirements:
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Identification
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Alignment
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Bushing (Conduit)
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Grounding
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Supports and Anchorages In reference to the cable installation the following areas were inspected to verify compliance with the applicable requirements:
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Protection from adjacent construction activities (welding, etc.)
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Coiled cable ends properly secured
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Non-terminated cable ends taped Cable trays, junctico boxes, etc., reasonably free of debris
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Conduit capped, if no cable installed
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Cable supported
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Bend radius'not exceeded
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Separation As a result of an overhead inspection, the inspector pointed out to the Licensee the abundance of trash, metal objects, lamps, cable pulleys, chain, tools, etc. present in cable trays in Rooms 65, 62, 59 and 58, Level A, Control Building. The inspector noted that immediate action was taken to clean up these and surrounding cable tray areas.
b.
Cable Terminations The inspector reviewed and examined portions of the following procedures pertaining to cable termination to determine whether they comply with applicable codes, NRC Regulatory Guides and licensee commitments.
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ED-T-08,.Rev. 7 Cable Termination In reference to cable terminations the following areas were inspected to verify compliance with the applicable requirements.
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Cable identification
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Plugs used Condition of wire (not nicked, etc.)
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Tightness of connection
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Bending radius not exceeded
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Cable entry to terminal point
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Separation No v1olations or dev1ations were identitled.
19.
Containment and Safety Related Structural Steel Welding - Units 1 (55053C)
(55063C)
Periodic inspections were conducted during daily plant surveillances on safety-related steel welding at various stages of weld completion.
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The purpose of the inspection was to determine whether the requirements of applicable specifications, codes, standards, work performance procedures and QC procedures are being met as follows:
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Work was conducted in accordance with a process sheet or drawing which identifies the veld and its location by system, references, procedures or instructions, and provides for production and/or QC signoffs.
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Welding procedures, detailed drawings and instructions, were readily
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available in the immediate work area and technically adequate for the
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welds being made.
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Welding procedure specification (WPS) were-in accordance with the applicable Code requirements and that a Procedure Qualification Record
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(PQR) is referenced and exists for the type of weld being made, f
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Base metals and welding filler materials were of the specified type and grade, were properly inspected, tested, and were traceable.
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Protection was provided to shield the welding operation from adverse environmental conditions.
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Weld joint geometry including thickness was specified and that surfaces to be welded were prepared, cleaned and inspected in accordance with applicable procedures or instructions.
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A sufficient number.;f adequately qualified QA and QC inspection personnel commensurate with the work in progress were present at the work site.
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Weld area cleanliness was maintained and that alignment and fit-up tolerances were within specified limits.
Weld filler material being used was in accordance with welding
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specifications, unused filler material was separated from other types of material and was stored and controlled properly, and stubs were properly removed from the work location.
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There were no visual signs of cracks, excessive heat input, or
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excessive crown on welds.
Welders were qualified to the particular process and thickness; and
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that necessary controls and records were in place.
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No violations or deviations were identified, f
20. Preoperational Test Program Implementation / Verification - Unit 1 (70302)
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(71302)
The inspector reviewed the present implementation of the preoperational test program.
Test program attributes inspected included review of administra-tive requirements, document control, documentation of major test events and deviations to procedures, operating practices, instrumentation calibrations, and correction of problems revealed by testing.
Periodic inspections were conducted of Control Room Operations to assess plant condition and conduct of shift personnel. The inspector observed that Control Room operations were being conducted in an orderly and professional manner.
Shift personnel were knowledgeable of plant conditions, i.e.,
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ongoing testing, systems / equipment in or out of service, and alarm /
annunciator status.
In addition, the inspector observed shift turnovers on various occasions to verify the continuity of plant testing, operational problems and other pertinent plant information during the turnovers.
Control Room logs were reviewed and various entries were discussed with operations personnel.
Periodic facility tours were made to assess equipment and plant conditions,
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maintenance and preoperational activities in progress.
Schedules for program completion and progress reports were routinely monitored. Discus-sions were held with responsible personnel, as they were available, to determine their knowledge of the preoperational program.
The Inspector reviewed numerous operation deviation reports to determine if requirements were met in the areas of documentation, action to resolve, justification, corrective action and approvals. Specific inspections conducted are listed below:
a.
Preoperational Tests (1) Test Procedure Review (70300)
The inspector reviewed the following listed preoperational test procedures. Each test was reviewed for administrative format and technical adequacy.
The procedures were compared with licensee commitments from the applicable FSAR Chapters, Regulatory Guide 1.68 and the Safety Evaluation Report (NUREG-1137). This included verifying that pertinent prerequisites were identified, initial test conditions and system status were specified, acceptance criteria were specified and management approval indicated:
NRC Procedure Insp.
Test Title No.
No.
1-3AB-01, Rev.0 70337 Main Steam System 1-3BB-08, Rev.0 70331 Reactor Vessel and Internals 1-38B-02, Rev.0 70347 Pressurizer Relief Tank Cold 1-3EC-01, Rev.0 92706 Spent Fuel Pool Cooling and Cleanup (2) Test Witnessing (70312)
The inspector witnessed selected portions of the following preoperational test procedures as they were conducted.
The inspection included attendance at briefings held by the test supervisor to observe the coordination and general knowledge of the procedure with the test participants.
Overall crew perform-ance was evaluated during testing. A preliminary review of the test results was compared to the inspector's own observations.
Problems encountered during performance of the test were verified to be adequately documented, evaluated and dispositioned.
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Procedure NRC Insp.
Test Title Activity Observed No.
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1-3GD-01 70446 Auxiliary Feed-
-Train "A" 1-TIS-water Pumphouse Set High/ Low HVAC System Temperature Setpoints -
l 1-38G-01 70433 Boric Acid Blender Operational i'
Verification of the Reactor Makeup Control System in the Automatic Mode -
1-3BB-02 70347 Pressurizer 1HV8031 PRT Relief Tank Recirc Isol Viv (PRT) Cold Control Circuit
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Checkout -
1HV8033 PRT N2 Su ply Isolation
r Valve Control
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Circuit Checkout -
HV8047 PRT N2 Supply Isolation Valve Control Circuit Checkout -
PRT Filling and Draining Capability Demonstration and Level Alarm Check (3) Test Results Evaluation (70400)
l The inspector reviewed the following listed preoperational test
results. This review was performed to ascertain if an adequate
evaluation of the test results has been oerformed: test data was
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within the established acceptance criteria, or that deviations are properly dispositioned; appropriate retesting was performed where necessary; administrative practices were adhered to; and that
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appropriate review, evaluation and acceptance of the test results
have been performed.
Procedure NRC Insp.
Test Title No.
No.
1-3KJ-03 70447 Train A Diesel Generator Switchgear, Controls and Auxiliaries i
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The inspector noted that the appendixes No's. I & II entitled
" Incomplete Cat Sheet" and "Punchlist Item Sheet" had listed two CAT's and three MWO's which affected steps within the test, however the applicable block, i.e.
authorization to proceed or Cat /Punchlist Item approved / cleared had not been signed off while the affected steps had been completed. Meetings were held with the licensee's preoperational superintendent and test supervisor to discuss this matter. The licensee informed the inspector that the CAT's & MWO's had been completed prior to the start of the applicable test steps and that it was just an oversight on the Test Supervisor to sign off the appropriate block in Appendix No's. I & II.
The licensee's preoperational test superintendent commi tted. to
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re-emphasizing the proper method of completing Appendix I & II to all test supervisors at the next test supervisor's meeting. The inspector reviewed the maintenance work orders and construction acceptance tests to verify work ccmpletion and has no further questions at this time, b.
Construction Acceptance Testing (CAT)
The inspector conducted a review of the following completed construc-tion acceptance tests:
Cat. No.
Description CAT-85-3056 Diesel Generator (DG) IB CAT-E-20 Redline / Functional Test
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CAT-85-3057 DG-1B CAT-E-20 Redline / Functional Test CAT-85-3060 DG-1A CAT-E-20 Redline / Functional Test
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CAT-85-3061 DG-1A CAT-E-20 Redline / Functional Test The inspector witnessed portions of the following CAT's to verify imnlamentation nor Startun Manual Procedura No. SUM-12A:
Cat No.
Description CAT-86-158 Atmospheric Relief 1PV3020 CAT-E-08 Loop Calibration CAT-86-1312 Atmospheric Relief 1PV3020 CAT-E-20 Functional Test CAT-85-4009 1HV0190A CAT-E-08 Instrumentation Loop Calibration CAT-85-4010 1HV0190B CAT-E-08 Instrumentation Loop Calibration c.
Followup of Event Occurring During Testing The inspectors reviewed the following events which occurred as a result of testing:
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(1) Pressurizer Relief Tank (PRT) Disc Rupture - This event resulted when the PRT was overfilled.
The overfill was due to a level instrument error which mislead the test supervisor that level was at 62% when actual was at 100%.
(2) Reserve Auxiliary Transformer (RAT) Trip - This event consisted of a trip of both RAT's. This event resulted when an AC power signal was placed on the DC control power bus causing a current loop thru metal oxide varistors (MOV). The MOV's were installed to protect i
electrical contacts in the trip circuit. The licensee has removed the MOV's to remove susceptibility to this fault.
The AC signal was traced to a vendor wiring error in the CVCS system.
(3) NSCW Water Hammer - This event occurred during the performance of Special Test 11 when an operator restarted the NSCW pump prior to the pump discharge valve being shut. This placed the system in an actual water-hammer.
Walkdowns and checkout of susceptible components was performed with no damage noted.
No violations or deviations were identified.
21.
Plant Procedures - Unit I and 2 (42400B)
This inspection consisted of a procedural review to verify that administra-tive controls are established and implemented to control safety related operations.
Procedures are selected at random and reviewed for technical adequacy and incorporation of requirements as appropriate for the proper operation of a nuclear facility in the startup and operational phase. The following requirements, guidance and licensee commitment were utilized as appropriate:
- 10 CFR 50.59 Change, Tests, and Experiments
- 20 CFR 50 Appendix B Instructions, Procedures and Drawings Criteria V
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- ANST N18.7-1976 Administrative Controls and Qualitv Assurance for the Operationai Phas'e
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- Regulatory Guide 1.33 Quality Assurance Requirements for the Rev 2, 1978 Operational Phase of Nuclear Power Plants
- FSAR Section 13 Conduct of Operations
- NUREG 0737, et al TMI Task Action Plan Procedures reviewed were:
a.
Administrative Number Rev Title 00051-C
Procedure Review and Approval 00054-C
Rules for Performing Procedures 00300-C
Authority to Startup and Shutdown the Reactor
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Main Control Room Access and Personnel Conduct 00411-C
Preservice and Inservice Inspection Program
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Operations Number Rev Title 10000-C
Conduct of Operations
10005-C
Operability Status Indication for Plant Safety Systems
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c.
Maintenance Number Rev Title 20015-C
Planned Maintenance 20407-C
Maintenance Conduct of Operations 2G408-C
Control of Grinding Wheels, Discs &
Wire Brushes 28805-C
Control Building Battery Inspection 28810-C
Control Building Class 1E Battery Service Test 28815-C
Class IE Battery Performance Test 28911-C
Class 1E Seven-Day Battery Inspection No violations or deviations were identified.
22.
Three Mile Island Task Action Plan Followup - Unit 1 (425401B)
This inspection consists of verification that the licensee has implemented
the requirements of NUREG 0737, " Clarification of TMI Action Plan Require-ments" as committed to in the facility FSAR or other appropriate documents.
Verification consisted nf one ne mnre nf tha fnlinyinn attrihntoc, as
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appropriate, to determine acceptability for each listed action item:
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Program or procedure established
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Personnel training or qualification Completion of item
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Installation of equipment
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Drawings reflect the as-built configuration
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Component tested and in service or integrated into the preoperational
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test program The following documents were utilized in performing the review, as appropriate:
NUREG 0578 TMI-2 Lessons Learned Task Force Status Report NUREG 0660 NRC Action Plan Developed as a Result of the TMI-2 Accident
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NUREG 0694 TMI-Related Requirements for New Operating Licenses NUREG 0737 and Clarification of TMI Action Plan Requirements Supplement 1 FSAR thru Final Safety Analysis Report Amendment 23 NUREG 1137 and Safety Evaluation Report Supplements (0 pen) I. A.1.2 Shift Supervisor Administrative Duties - This item is a requirement to review and relieve the shift supervisor of non-safety
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administrative duties by delegating them to operations personnel on duty in the control room. The official title for this position at Vogtle is the On-Shift Operations Supervisor.
FSAR Section 13.1.2.2.2 references Item I.A.I.2 and states that the Operations Supervisors principal responsibility is ensuring safe plant operation during his assigned shif t.
FSAR Section 13.5.1.E describes the procedure provisions to ensure that the Operations Supervisor is not routinely performing administrative functions.
This FSAR section also commits to an annual review of the administrative duties by the General Manager-Vogtle Nuclear Operations. Procedure 10000-C Rev 1 " Conduct of Operations" was reviewed as the basic implementation document and was found to be consistent with the FSAR description for responsibilities.
It was noted that in the FSAR two of three items mentioned as attributes for this item are items delegated to personnel on duty. Also, no credit was taken for the existence of a shift clerk who can perform typical administra-tive duties. Clarification of this item was provided in a Nov. 9, 1979 NRC letter to the licensee which indicates that an annual review of administra-tive duties would be required in conjunction with TMI I.C.3 reinforcement of the shift supervisor's responsibilities.
This item remains open pending:
A review of a corporate management directive or other appropriate directive.
Trac' ting of this item will be by Inspection Followup Item 86-15-03 " Review Manajement Directive Pertaining to TMI Item I.A.1.2".
(0 pen) I.C.3 Shift Superviser Responsibi!! ties - This item is a requirement
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to issue a corporate management directive that clearly establishes the command duties of the shift supervisor and emphasizes the primary management responsibility for safe operation of the plant and to revise plant proce-dures to clearly define the duties, responsibilities and authority of the shif t supervisor and the control room operators.
FSAR Section 13.1.2.2.2 references Item I.A.1.2 and states that the Operations Supervisor principal responsibility is ensuring safe plant operation during his assigned shift.
This FSAR section also delineates the succession to responsibility for overall operation at the plant. FSAR section 13.5.1.E further describes the procedures which implement the requirements and commits to an annual reissue of a directive that emphasizes the primary responsibility of the On Shift
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Operations Supervisor by the General Manager Vogtle Nuclear Operations.
Administrative Procedure 00001-C Rev 0 " Plant Organization and Managerial Staff Responsibilities and Authority" and Operations Procedure 10000-C Rev 1
" Conduct of Operations" implement the FSAR with the exception of the
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succession of responsibilities.
FSAR 13.1.2.2.2 describes seven positions in the succession chain which includes a Deputy General Manager position that no longer exists. Procedure 00001-C Rev 0 also has seven positions but appears to replace the Deputy General Manager with the Initial Test Program Manager below the Manager, Unit Operations.
At the close of this inspection period this item was still under review and will be completed at a later inspection.
This item remains open pending:
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A review of a corporate management directive or other appropriate directive
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Resolution of the succession of responsibility chain between FSAR and Procedure 00001-C
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Completion of NRC Resident review Tracking of this item will be by Inspector Followup Item 86-51-01 " Review Licensee Action for TMI item I.C.3" (0 pen) I.C.4 Control-Room Access - This item requires the licensee to establish procedures to assure that instructions covering the authority and responsibilities of the person in charge of access and that clear lines of authority and responsibility in the control room in the event of an emergency are established. FSAR section 13.5.1.1.0 describes the procedures for control room access which assigns this responsibility to the Shift Supervisor.
Administrative Procedure, 00301-C Rev 0 " Main Control Room Access and Personnel Conduct" implements the commitments as described in the FSAR. A review of this instruction indicates that the Shift Supervisor has the authority to permit and/or restrict access to the control room. The Operations Superintendent, On-Shift Operations Supervisor, or Shift Supervisor may give permission to enter the restricted area. The restricted area centained in the precedure is different from that shown in FSAR Figure 13.5.1.1 and different from those being controlled in actual practice. The licensee plans to revise the FSAR and Plant Procedure to reflect the current practice of control.
This will require a revision of the figure in Procedure 00301-C, 10000-C, and 10003-C.
It was also noted that Procedure 00301-C does not include any predesignated NRC personnel as required.
Typically a statement to clarify that the NRC resident inspectors would have access commensurate with the Operations chain-of-command would be appro-priate.
This item remains open pending:
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Clarification of predesignated NRC personnel
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Revision of FSAR and Procedure 00301-C, 10000-C and 10003-C figures which describe the At-the Controls area _ _ - - -
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Tracking of this item will be by Inspector Followup Item 86-51-02 " Review Licensee Action for TMI Item I.C.4" (Closed)
II.K.3.1 Installation and Testing of Automatic Power-Operated Relief Valve (PORV) Isolation System This TMI-2 Action Plan item requires that the licensee provide a system that uses the PORV Block Valve to protect against a small-break loss-of-coolant accident. This system will automatically cause the block valve to close when the reactor coolant system pressure decays after the PORV has opened.
FSAR Section 5.4.11 describes that pressurizer pressure is interlocked with
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the PORV block valves, which provides automatic closure of the block valves upon low pressurizer pressure.
This item is also addressed in Section 7.6.2.2 of the Safety Evaluation Report.
The inspector conducted a review of the following logic and elementary drawings to verify the pressurizer low pressure interlock on the PORV block valves (No's. 1HV-8000A and 1HV-80008) as described in the FSAR.
Drawing No.
Valve No.
Title 1X6AA02-414-3 1HV-8000A Pressurizer Pressure Relief System-Train A 1X6AA02-415-3 1HV-80008 Pressurizer Pressure Relief System-Train B 1X3D-BD-802A, 1HV-8000A Elementary Diagram Reactor Coolant System Rev. 4 1X3D-BD-B02B, 1HV-8000B Elementary Diagram Reactor Coolant System i
Rev. 6 The inspector conducted a review of the completed Sections 6.1.1 and 6.1.2 in the Reactor Coolant System Preoperational Test Procedure (1-3BB-01, Rev.0). These sections functionally tested the operation of the PORV block valves (1HV-8000A & 1HV-8000B).
This included a logic test of the pressurizer low pressure interlock to verify automatic valve closure. The inspector also conducted a review of the applicable portions (Steps 5.3.3.38.8 cnd 5.3.3.54.0) cf the Prc :urizer Prc::ure & Lc.c! Centrol System Preoperational Test Procedure (-3BB-05, Rev. 0) to verify that the pressurizer low pressure interlock on the PORV block valves will be tested during hot functional testing.
Based on this review the inspector finds that the licensee has properly implemented the requirement of NUREG-0737, Item II.K.3.1, therefore this item is considered closed.
23.
Readiness Review Module 7 During the inspection period the inspectors reviewed the following commitments as part of Readiness Review Module 7 " Plant Operations and Support.
The commitments were reviewed for accuracy between the source document, Readiness Review Module and the implementing document.
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Operations Reviewer Commitment Implementing Number Source Document 789.01 FSAR 1.9.45 14905-1 Rev 1 790.00 FSAR 1.9.47 10005-C Rev 1 1119.00 FSAR 7.5.5.1 10005-C Rev 1 FSAR 10.4.9.5 827.00 FSAR 1.9.93 Draft Technical Specification 14230-C Rev 0 14235-C Rev 1 840.00 FSAR 1.9.114 10000-C Rev 1
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00301-C Rev 0 1025.00 FSAR 6.2.5.1.2.0 11130-1 Rev 0 986.00 FSAR 4.3.2.7 Procedure in Draft
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19001-1 Rev 0
1011.00 FSAR 5.4.10.3.1 19010-1 Rev 1 19011-1 Rev 0 19012-1 Rev 0 19013-1 Rev 0 19030-1 Rev 1 1071.00 FSAR 13.1.2.2.2 10000-C Rev 1 1573.00 FSAR 13.1.2.2.2 10000-C Rev 1 1574.00 FSAR 13.1.2.2.2 10000-C Rev 1 1575.00 FSAR 13.1.2.2.2 10000-C Rev 1 1591.00 FSAR 13.1.2.3 Draft Tech. Specification 1729.00 FSAR 13.5.1.A 00051-C Rev 3 10012-C Rev 2 For commitments 1574 and 1575 comments see Paragraph 22 regarding TMI item I.A.1.2.
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This inspection period also included reviews of selected portions of Sectica 4 cf the Mcdule.
The descriptive peregrcph:,cre ccmpered against the applicable plant procedures and the following discrepancies i
were noted.
The licensee stated that the appropriate procedures would be modified as follows:
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Readiness Review Section 4.1.1.1. Authorization to Startup and Shutdown.
This section lists four conditions by which any licensed operator is authorized to shut down the reactor without prior approval. Procedure 10000-C, however, omitted one condition for the Reactor Operator and Balance of Plant Operator. This item is considered an oversight in Procedure 10000-C.
It was noted that Procedure 00300-C did convey the correct requirements.
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Readiness Review Section 4.1.1.7, Reactor Trip Review. This section states that following a safety limit violation, NRC approval for startup is required.
The inspector questioned why the safety limits were not called out specifically in (rocedure d
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10006-C nor was mention made of the NRC approval. The licensee stated that Procedure 10006-C was the appropriate location and the
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procedure would be revised.
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The above items will be tracked as Inspection Followup Item 86-51-04
" Review Licensee Procedure Changes to 10000-C and 10006-C.
Maintenance Area Reviewer Commitment Implementing
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Number Source Document 775.01 FSAR 1.9.37 00350-C, Rev. 1 20408-C, Rev. 0 20427-C, Rev. 0 775.03 FSAR 1.9.37 20427-C, Rev. 0
775.04 FSAR 1.9.37 20427-C. Rev. 0 775.05 FSAR 1.9.37 20427-C, Rev. 0 775.07 FSAR 1.9.37 20427-C, Rev. 0 775.09 FSAR 1.9.37 20004-C, Rev. 1 20427-C, Rev. 0
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775.10 FSAR 1.9.37 20408-C, Rev. 0 20427-C, Rev. 0 775.12 FSAR 1.9.37 20427-C, Rev. 0 775.16 FSAR 1.9.37 20<27-C, Rev. 0 775.17 FSAR 1.9.37 20427-C, Rev. 0 845.00 FSAR 1.9.116 846.01 FSAR 1.9.116 00350-C, Rev. 1
846.02 FSAR 1.9.116 00050-C, Rev. 4 846.03 FSAR 1.9.116 00350-C, Rev. 1
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20015-C, Rev. 3 846.04 FSAR 1.9.116 00350-C, Rev. 1 846.05 FSAR 1.9.116 00050-C, Rev. 4 20407-C, Rev. 2 845.06 FSAR 1.9.115 20407-C, Rev. 2 846.07 FSAR 1.9.116 00850-C, Rev. 2 846.08 FSAR 1.9.116 00254-C, Rev. 1 846.09 FSAR 1.9.116 00350-C, Rev. 1 846.10 FSAR 1.9.116 00850-C, Rev. 2 00853-C, Rev. 4 846.11 FSAR 1.9.116 00350-C, Rev. 1
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846.12 FSAR 1.9.116 00350-C, Rev. 1 846.13 FSAR 1.9.116 00350-C, Rev. 1 846.14 FSAR 1.9.116 20407-C, Rev. 2 00350-C, Rev. 1 846.15 FSAR 1.9.116 00054-C, Rev. 0 20407-C, Rev. 2 846.16 FSAR 1.9.116 00350-C, Rev. 1 846.17 FSAR 1.9.116 00350-C, Rev. 1 846.19 FSAR 1.9.116 00350-C, Rev. 1 l
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846.20 FSAR 1.9.116 00350-C, Rev. 1 846.21 FSAR 1.9.116 00350-C, Rev. 1 846.22 FSAR 1.9.116 20407-C, Rev. 2 846.23 FSAR 1.9.116 00100-C, Rev.
20407-C, Rev. 2 849.00 FSAR 1.9.118 850.02 FSAR 1.9.118 00404-C, Rev. 0 00350-C, Rev. 1 840.03 FSAR 1.9.118 00050-C, Rev. 4 10011-C, Rev. 7 14000 (Series)
24000 (Series)
852 FSAR 1.9.121 859 FSAR 1.9.129 860.01 FSAR 1.9.129 28805-C, Rev. 0 860.02 FSAR 1.9.129 28805-C, Rev. 0 860.03 FSAR 1.9.129 28805-C, Rev. 0 860.04 FSAR 1.9.129 28815-C, Rev. 1 860.05 FSAR 1.9.129 28810-C, Rev. 0 860.06 FSAR 1.9.129 28815-C, Rev. 1 860.07 FSAR 1.9.129 28815-C, Rev. 1 860.08 FSAR 1.9.129 28815-C, Rev. 1 860.09 FSAR 1.9.129 28815-C, Rev. 1 860.10 FSAR 1.9.129 28815-C, Rev. 1 860.11 FSAR 1.9.129 28810-C, Rev. 0 860.12 FSAR 1.9.129 28815-C, Rev. 1 28810-C, Rev. 0 860.13 FSAR 1.9.129 28815-C, Rev. 1 877.00 FSAR 1.9.147 878.00 FSAR 1.9.147 00411-C, Rev. 1 881.00 FSAR 1.9.150 00411-C, Rev. 1 The inspector conducted surveillance inspections throughout the plant during the inspection period of maintenance activities for compliance with administrativa controls par Startup tianual Procadura No. 0Ul.i -- 22.
The following maintenance activities were observed:
MWO No.
Description 18608536 Turbine Driven Auxiliary Feedwater Pump Preparation for Lube Oil Flush 18609553 ACCW Pump No. 2-1217-P4-002 Pump Alignment per Procedure No. 25215-C 18609538 MSIV 1 HV-3006B Valve Stroke Testing 18610074 MSIV 1HV-3006B Replace Pump Solenoid The inspector conducted a review of the following completed MWO's for compliance with administrative controls per Startup Manual Procedure No.
SUM-22.
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MWO No.
Description 18607443 OG-1A Engine Control Panel Modification 18609613 DG-1A and DG-1B Engine Control Panel 18609472 DG-1A and DG-1B Instrument Calibration Check 18610045 1PT-0469 and ILT-0470 Perform Calibration per i
Maintenance Procedure 24465-1 24.
Technical Specification Review (71301) Unit 1 On May 28-30, 1986 the inspector participated in a meeting between NRC and the licensee concerning the Technical Specifications (TS). This meeting was held to develop a common basis for the technical applicability of the various Limiting Conditions for Operability (LCO) Action Statements and Surveillances.
25. Management Meetings-Unit 1 (307028)
The following meetings / audits were attended by one or more resident inspectors:
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May 16, 1986 - Meeting with QA and Test Management. Increased QA involve-ment and more timely action on the part of Operational QA was the subject of discussion.
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May 30, 1986 - Pre-review of Fuel Load, Criticality, Physics Testing, and Power Ascension Test Plans.
j June 5,1986 - Hot Functional Test (HFT) Milestones and Objectives.
June 18, 1986 - Project Completion Status Meeting. This meeting was held to
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review the current completion status and schedule for fuel load. Messrs.
Sinkule and Brownlee, NRC.
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June 23,198G - Enfun.ement. Cunfer ence field in At.lanta, Geurgia.
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June 23-26, 1986 - Seismic Qualification and Pump and Valve Operability Review Team Audits.
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