IR 05000327/1979070
| ML19305B117 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 01/09/1980 |
| From: | Belisle G, Dance H, Donat T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19305B105 | List: |
| References | |
| 50-327-79-70, NUDOCS 8003190193 | |
| Download: ML19305B117 (8) | |
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t UNITED STATES
8 NUCLEAR REGULATORY COMMISSION o
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E REGION 11
o 101 MARIETTA ST N.W., SUITE 3100 Y
ATLANTA, GEORGIA 30303
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Report No. 50-327/79-70 Licensee: Tennessee Valley Authority 500A Chestnut Street Chettanooga, Tennessee 37401 Facility Name: dequoyah Nuclear Plant Docket No. 50-327 License No. CPPR-72 Inspection at Sequoyah Site near Chattanooga, Tennessee
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Inspected by:
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G. A. Belisle
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Date/ Signed j-e 5 brn V/ffd
.T.dl. Donat
/ Date $igned Approved by:
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H. C. Dance, Section Chief, RONS Branch Date Signed SUMMARY Inspected on November 28 - December 1, 1979 and December 3-7, 1979 Areas Inspected This routine, unannounced inspection involved 105 inspector-hours onsite in the areas of safety system walkdown, electrical distribution inspection, preoperational test record review, verification of test results evaluation, offsite review board review and followup of previously identified inspector and licensee items.
Results l
Of the 6 areas inspected, no apparent items of noncompliance or deviations were l
identified in 5 areas; one apparent item of noncompliacce was found in one area j
(infraction - failure to follow procedure for making temporary alterations on a safety-related system paragraph 6).
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DETAILS 1.
Persons Contacted Licensee Employees
- W. F. Popp, Assistant Plant Superintendent
- W. E. Andrews, Quality Assurance Supervisor
- D. O. McCloud, Quality Assurance Engineer
- J. M. McGriff, Maintenance Supervisor, Instrumentation
- W. A. Watson, Electrical Supervisor
- J. W. Doty, Supervisor, Mechanical Maintenance
- W. J. Glassen, Operations QAAS S. West, Electrical Engineer R. Gladney, Instrumentation Engineer E. C. Pendergrass, Engineer, QC Records Unit F. A. Szczenpanski, Chairman, Nuclear Safety Review Board
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B. Patterson, Instrumentation Engineer Other licensee employees contacted included three operators and three security force members.
NRC Resident Inspector
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W. T. Cottle
- Attended exit interview 2.
Exit Interview
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The inspection scope and findings were summarized on 12/7/79 with those persons indicated in Paragraph I above.
3.
Licensee Action on Previous Inspection Findings Not inspected.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Safety System Walkdown The inspector physically walked down the Containment Purge Supply and Exhaust System and verified by direct observation that the system was lined up as required for existing plant conditions. The system is currently being tested by construction plant personnel. The test in progess is the setting of the flow balance parameters. During the walkdown of the system the inspector noticed many piping instrumentation penetrations without
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-O g-2-caps. These caps were removed for ease of installation of flow instrumenta-tion during testing. The inspector reviewed work plan No. 3663 for the installation of exhaust dampers, balancing of the system and the installation of filters. The inspector also reviewed General Construction Specification G-37, Testing and Balancing of Heating, Ventilating and Air Conditioning
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' Systems.
During this review it was noticed that upon completion of testing there are no provisions to insure that all piping instrumentation penetration caps are replaced. The Resident Inspector met with cognizant construction personnel and was shown the construction engineer's reactor building punch list. This list establishes provisions to insure the replacement of'all piping instrumentation penetrations caps.
No items of noncompliance or deivation were identified.
6.
Electrical Distribution Inspection
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The inspector looked at one hundred and eighty seven (187) electrical distribution and controls panels to determine their readiness for operation.
The panels included those in the control room, auxiliary control room, auxiliary distribution room and the diesel generator building. The review included the 6900V AC shutdown loads, normal distribution boards, 480V AC distribution boards, 120V AC instrument distribution panels, 125V DC distri-bution boards, pressurizer heater and control rod drive panels, reactor coolant pump under voltage and under frequency relay cabinets and instrument power inverters. A comprehensive list of findings and concerns was made.
A meeting was held with cognizant plant personnel and the Resident Inspector on December 5,1979 to present to the licensee the inspector findings and concerns. The areas of concern are:
a.
Cleanliness of panels and distribution boards b.
Loose, identified and unidentified wiring in panels and controls Status of construction pull orders c.
d.
Status of pull ropes in panels Loose fuses in panels.
e.
The licensee acknowledged these inspector concerns and stated that they would investigate.
During the inspection of the panels the inspector found that in two panels, jumpers were installed with improper controls.
In panel R14, on terminal board 14B, between terminal points 9 and 10 and in panel R17, terminal board 17B, between terminal points 9 and 10, jumpers were installed. The inspector reviewed work plan No. 5006 that was issued on September 29, 1979
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-3-with an estimated completion date of October 12, 1979 for the rerouting of conduit IPM917 and IPM925. These jumpers were installed by the instrument shop to protect equipment affected by the rerouting of the conduits.
The installation of these jumpers constitutes a temporary alteration and is subject to the controls established by Administrative Instruction AI-9, Temporary Alterations. The installation of these jumpers was not approved or documented as required by AI-9.
Failure to control these temporary alterations is an apparent item of noncompliance (327/79-70-01).
In panel IR73 a jumper was installed under Jumper Inhibit and Wire Removal (JIWR) order 79-641-3.
One end of this jumper was attached to terminal point 4BA3 but the other end was not attached. The inspector reviewed J1WR 79-641-3 and ascertained that both ends of the jumper had been attached upon installation and verified by two plant personnel. The licensee is investigating this problem. This item will be reinspected.
No other items of noncompliance or deviation were identified.
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7.
Preoperational Test Record Review The inspector reviewed the licensee's program for temporary and permanent storage of vital plant records. The review included the following documents:
Sequoyah Operational Quality Assurance Manual
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Part III Sec 4.1, " Plant Quality Assurance Documents" Part II Sec 4.2, " Transfer of Quality Assurance Records"
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Sequoyah Nuclear Plant Procedures
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Administrative Instruction AI-7, " Record Retention, Recorder Charts and Quality Assurance Records" Surveillance Instruction SI-1, " Surveillance Program"
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Preoperational Test Section Instruction Letter, SIL-1,
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Sequoyah Standard Practice - Maintenance, SQM1, "Sequoyah Nuclear Plant Maintenance Program" Administrative Section Instruction Letter, SIL-75, "Use of the
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Permanent Records Storage Facility" The inspector also included a tour of the Permanent Record Storage vault in the control building and an ex' amination of the fireproof cabinets in the central files area.
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4 The present program, as defined in AI-7 allows each plant to either maintain their records in a temporary storage location in their section or to transfer them to central files for both temporary and permanent storage. Administra-tive section instruction letter, SIL-75, defines the process for documenting the receipt of material into the central files (temporary storage) and the transfer of material to the permanent storage facility. Plant procedures, Preop SIL-1, SI-1, SQM-1, define how completed preoperational test packages, completed surveillance instructions and completed equipment history cards are transmitted to central files for temporary and permanent storage. Two items of the Quality Assurance records retention program as defined in OQAM Part III Sect 4.1 and AI-7 have not been fully implemented. These are:
Use of the duplicate record option for permanent storage records (0QAM a.
Part III Sect 4.1 para 4.2, AI-7 para 8.0).
The licensee has been microfiliming all material except for recorder charts designated for the permanent storage facility and storing the processed film cartridges
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in the control file area.
In accordance with the OQAM and AI-7, this is an acceptable option provided a duplicate copy is maintanined at a
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separate location and that this location is specifically identified in the varicus appendices to AI-7.
The licensee stated that duplicate copies are being maintained at TVA corporate offices and that they would get confirmation of this and revise AI-7 to specify the location.
Until confirmation of the duplicate storage location and revision to AI-7 this item remains open and will be reinspected later (0 pen item 327/79-70-02).
b.
In accordance with 0QAM Part III, Sect 4.1, para 1.2 and AI-7, Para-graph 6.0, written instructions are needed to establish how operations and maintenance quality assurance documents such as SOI's, GOI's, MI's are to be reviewed and transmitted to central files. This will be followed as open item (327/79-70-03) until reviewed on a subsequent inspection.
In all other aspects the temporary storage facility (plant central files)
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and the permanent storage facility programs are in agreement with the program as defined in ANSI 45.2.9, OQAM Part III, Sect 4.1 and 4.2, and i
AI-7.
8.
Verification of Test Results Evaluation The inspector reviewed one hunderd and fifty-four completed preoperational test packages to verify that reviews of the packages had been made prior to forwarding the packages for storage in plant files.
Sixty-one TVA written tests were, reviewed to verify that the licensee's engineering department had performed an independent review and had found the test acceptable or that outstanding deficiencies had been identified and what event (fuel loading, initial criticality, etc) they had to be resolved by and that the package had been signed by the plant superin-tenden *
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-5-Forty-four test packages for noncontrolling systems (NCS) were similarly reviewed.
Fourteen Westinghouse test packages which had been reviewed by both TVA Engineering Design and Westinghouse Engineering departments and signed by the plant superintendent were examined. Thirty-five test packages which had been reviewed by TVA's engineering design department but which were awaiting Westinghouse review were also examined.
The total number of test packages examined represents about 90% of the total number of test packages needed to be completed by the licensee in order to support fuel loading. The inspector had no comments on the completed test packages reviewed.
9.
Offsite Review Board Review The inspector reviewed the operation of the Nuclear Safety Review Board (NSRB) as stated in the NSRB charter for conformance with the proposed Technical Specifications section 6.5.2.
Several discrepancies between the NSRB charter and the proposed Technical Specifications were noted.
The proposed Technical Specifications requires expertise in the area a.
of Quality Assurance for a member of the NSRB. The NSRB charter does not address expertise in the area of Quality Assurance.
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b.
The proposed Technical Specifications require members of the NSRB to have a degree or equivalent and five (5) years of technical experience.
The NSRB charter does not address the need for five (5) years of technical experience.
The proposed Technical Specifications requires one half the membership c.
of the NSRB or at least five (5) members present, whichever is greater, to represent a quorum.
The NSRB Charter requires only four members to be present to represent a quorum, d.
The proposed Technical Specifications requires certain audits to be performed under the cognizance of the NSRB. The NSRB charter does not specify the audits that the NSRB has cognizance over.
The proposed Technical Specifications requires records to be prepared, e.
approved and distributed within a certain time frame. The NSRB charter does not address this.
The inspector talked with MR. F. A. Szczepanski, Chairman of the NSRB, and expressed these concerns on November 30 and December 7,1979. The s
inspector was informed that a new NSRB charter had been drafted to fully meet the requirements of the proposed Technical Specifications. Until this new NSRB Charter can be reviewed, these discrepancies between the existing NSRB charter and the proposed technical specifications will be considered an open item (327/79-70-04).
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10.
Followup on Inspector Identified Items (Closed) Open Item (327/77-33-11) Completion of preoperational test a.
TVA-31-C, 31D, 32A and 32B. The inspector reviewed the completed test.
This item is closed.
b.
(Closed) Open Item (327/77-10-01) Resolve errors in valve / switch positions of GOI ID ECCS master checklist. The inspector reviewed G0I ID valve switch positions to ensure correct labeling. This item is closed.
c.
(Closed) Open Item (327/77-20-01). Resolve comments on W-6.1A2 and W-6.1A3.
The inspector reviewed changes to W-6.1A2 and W-6.1A3.
This item is closed.
d.
(Closed) Open Item (327/77-33-08) Review preoperational test TVA 11A, 11B, 31C and 31D. The inspector reviewed the test in question. This item is closed.
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(0 pen) Open Item (327/79-25-01) Reactor Coolant System Flow Rate. The e.
inspector needs to review additional information that was not readily avaliable. This item remains open.
f.
(Closed) Open. Item (327/79-18-01) Indoctrination of Contractor &
Offsite Licensee Personnel in Fire Protection & Fire Prevention Procedures. The inspector reviewed changes to Physical Security Instruction PHYSI-2, Access Control of Personnel, implements which training in these areas for personnel. This item is closed.
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Followup on Licensee Identified Items (Closed) Item (327/79-20-06, 328/79-11-06) Control Loop Bistable a.
Failures, NCR/MEB 79-10.
The inspector reviewed completed workplan 3206 and 3206 RI.
This item is closed.
b.
(Closed) Item (327/79-36-11, 328/79-21-11) Design deficiency of vendor supplied discharge accumulator, NCR CEB 79-22.
The inspector reviewed completed MR 23110 and construction purchase order 24720. This item is closed.
(Closed) Item (327/79-36-10, 328/79-21-10) Seal Water Injection Flow c.
Elements Orifice Size, NCR MEB 79-21.
The inspector reviewed completed MR 31512, 33774, 33775, 33776 and 33773 and recalibrations documented in completed SIL-375 data sheets. This item is closed.
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d.
(Closed) Item NCR 8P Pressurizer level Instrumentation manifolds rated below system pressure. The inspector reviewed completed work package 8088 which replaced manifold 1-PDT-70-126 with one rated for system pressure and temperature. This item is close _-.-
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(Closed) Item (327/79-36-13, 328/79-21-13) Failed Barton Steam e.
Generator Level Transmitters. NCR HEB 79-24.
The inspector reviewed the following completed MR's 21144, 48834, 11965, 31257, 51403, 48835, 14176, 11964, 48837, 48839, 51402 and 48838 for the removal and replace-ment of the failed level transmitters. This item is closed.
f.
-(Closed) Item (327/79-36-09, 328/79-21-09) Steam Generator Reference Column Water Level Error NCR MEB 79-32.
The inspector reviewed completed workplan 8020 and 8020 R1, ECN 2634 and FCR No. IPP-297.
This item is closed.
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(0 pen) Item (327/79-29-03, 328/79-16-03) Improper Coils in AFW and EGTS Systems, NCR 7P. The inspector reviewed work plan 3270 for the installation and verification of proper coils in the AFW system. The inspector reviewed work plan 3269 for installation & verification of coils in the EGTS system. One coil in the EGTS system 1-PSV-65-8 has not been installed. This item remains open.
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h.
(Closed) Item (327/79-36-03, 328/79-21-03) ERCW valve Positioning, MEB 79-22.
The inspector reviewed completed ECN 2476 and workplan 4682.
This item is closed.
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(Closed) Item (327/79-36-05, 328/79-21-05) Deficiencies in Penn Ventilator Company QA Program, MEB 79-2.
The inspector reviewed the results of the TVA inspection of the ventilation equipment in question for seismic and environmental qualification. This item is closed.
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(Closed) Item (327/79-43-05) Chattering of Underfrequency Relay Contacts, EEB 79-13.
The inspector reviewed completed ECN 2631 and work plan 5185. This item is closed.
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