IR 05000327/1981013
| ML19347E548 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 04/08/1981 |
| From: | Herdt A, Zajac L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19347E543 | List: |
| References | |
| 50-327-81-13, 50-328-81-10, NUDOCS 8105120591 | |
| Download: ML19347E548 (6) | |
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UNITED ST TES
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NUCLEAR REGULATORY COMMISSION o
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REGION 11
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101 MARIETTA ST., N.W., SulTE 3100 ATLANTA, GEORGIA 30303
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Report Nos. 50-327/81-13 and 50-328/81-10 Licensee:
Tennessee Valley Authority 500A Chestnut Street Chattanooga, TN 37401 Facility Name. Sequoyah Docket Nos. 50-327 and 50-328 License Nos. DPR-77 and DPR-73 Inspection at Se oyah ite near Chattanooga, TN Inspect
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L. D. Z~a ac Dat'e Signed Approved by:
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A. R. Herdt, Section Chief Dat'e Signed Engineering Inspection Branch Engineering and Technical Inspection Division SUMMAP.Y Inspected on March 23-26, 1981
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Areas Inspected
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This routine, unannounced inspection involved 34 inspector-hours onsite in the areas of Preservice Inspection - review of nondestructive examination procedures; containment penetrations review of QA records and review of implementing
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procedures; review of licensee actions on previous licensee identified items; and review of licensee actions on previous unresolved and inspector identified items.
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Results
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Of the 4 areas inspected, no violations or deviaticns were identified.
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REPORT DETAILS
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1.
Persons Contacted Licensee Employees
- G G Stack, Project Manager
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- 0. W. Mack, Assistant Construction Engineer
- T. B. Northern, Jr., Construction Engineer
- A. H. Gelston, Nuclear Power Engineer
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- W. J. Glasser, Nuclear Power QA Coordinator
- V. A. Bianco, Engineering Design Licensing
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- K. G. Galloway, Supervisor, Mechanical and Welding Inspection
- M. E. Gothard, PSI /ISI Engineer R. Daniel, Supervisor PSI /ISI M. Skarzinski, Preoperational Test Engineer
,*D. W. Kelley, Supervisor QC NRC Resident Inspector
- E. Ford
- Attended exit interview
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2.
Exit Interview The inspection scope and findings were summarized on March 26, 1981,with those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings
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a.
(C1osed)UnresolvedItem 328/80-08-02, Potentially incorrect ultrasonic examination of pipe welds. The licensee revoked the certification of the ultrasonic examiner involved in the incorrect pipe weld examina-tion. The pipe welds previously examined only by this individual at both the Sequoyah and Watts Bar Nuclear Plants were re-examined and
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were found to be acceptable. The individual was also required to take
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the complete ultrasonic Level II examination and has been recertified.
These actions satisfy NRC's concerns and -are therefore closed.
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b.
(Closed) Unresolved Item. 328/81-03-04, Incorrect / inadequate fasteners used in flange connections on safety injection pumps. The licensee
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stated that one purp was returned to the vendor for repair work and tha' the bolts may have been installed on the flange by the vendor.
The licensee replaced the bolts with studs and nuts and also replaced the studs where full engagement with the nuts was questionable.
Completion of this= work was verified by the inspector, thus, this item
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is closed.
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c.
(0 pen) Unresolved Item 328/81-03-03, Missing records for penetrations
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The licensee re-measured the bellows for those penetrations with missing records. The re-measurement for penetrations X-12A, X-12B, X-12C, X-12D, X-13A, X-138, X-13D, X-14A, X-148, X-14C, X-140, X-20A, X-21, X-32 and X-33, showed that the bellows section was misaligned beyond the maximum permissible risalignment. The licensee's design engineers are currently evaluating the measurement data and will determine what action is needed, if any. Accordingly, this item will remain open.
d.
(Closed) Unresolved Item 328/80-07-01, Use of flame heat for pipe bending.
The inspector was provided with a copy of the corrective action report which delineates the controls that were exercised in bending the subject pipe. The report states that the bending process was in compliance with the requirements of G-29 P.S.4.M.2.1.(d).
This item is closed.
e.
(Closed) Violation 328/31-03-02, Scaffold placed on 1 inch stainless steel pipe. Tne inspector sighted the above area where the subject scaffold had been installed and noted that it had been removed. The inspector observed two other scaffolds that had been installed which were resting on stainless steel pipe that were larger than 3-Inch diameter and each had pads installed between the scaffold and the pipe for protection. In view of the above, this item is closed.
f.
(0 pen) Deficier.cy No. 328/80-08-03, Failure of records to adequately define practical examination criteria.
The inspector was provided a
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copy of a " Practical Examination" checkoff sheet for a Level I examinar.
No checkoff sheet has been developed for a Level II exambler, nor was there evidence provided that described the type of test specimen that the examiner tested for qualification. This item remains open pending completion of corrective actions.
4.
Unresolved Items Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve noncompliance or devia-tions. New unresolved item identified during this inspection is discussed
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in paragraph 6.b 5.
Preservice Inspection - Review of Nondestructivo Examination Procedures The inspector reviewed the written procedures, listed below, that were developed for preservice examinations to determine whether they met the ASME Code 1974, edition with summer 1975 addenda.
Radiographic Examination Procedure N-RT-1 Rev. O Liquid Penetrant Examination Procedure N-PT-1 Rev. 3 Liquid Penetrant Examination Procedure N-PT-2 Rev. 1
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Magnetic Particle Examination Procedure N-MT-1 Rev. O Eddy Current E:: amination Procedure N-ET-1 Rev. 2 *
Ultrasonic Examination Procedure N-UT-6 Rev. 1 The following discrepancies were noted.
a.
Radiographic (RT) Procedure The RT procedure is merely a general dissertation of RT functions and provides no details. The minimum information required to be specified by Article 2 of Section V of the ASME Code is not included, such as:
(1) the type of material to be radiographed (2) the material thickness range to be radiographed (3) the focal spot size of the source (4) the minimum source-to-film distance (5) thickness of intensifying screens (6) blocking and masking techniques In addition, the required surface condition for welds is not specified, nor is a description of how the location markers are to be placed with respect to a landmark.
The licensee advised the inspector that the RT procedure has not been used since radiography was performed by an independent activity using their own RT procedure. The licensee considers that the RT procedure could be deleted.
The licensee agreed to either revise the RT procedure to comply with Code requirements or to delete it from the PSI /ISI program.
This will be carried as Inspector Followup Item 328/31-10-01, " Inadequate radiographic procedure".
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Liquid Penetrant (PT) Procedure Liquid penetrant procedure N-PT-1 is the solvent removable method and M-PT-2 is the water-washable method.
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(1) N-PT-1 - the following discrepancies were noted:
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(a) Paragraph 4.5.1 states that the developer shall be applied by spraying on the examination surface within 10 minutes after removal of excess penetrant. The intent of this paragraph is to ensure developer is applied within the time period established during procedure qualification.
However, the wording of the paragraph appears to permit considerable time to remove excess penetrant and only controls the time period after excess penetrant is finally removed which could result in developer being applied well beyond 10 minutes from the time excess penetrant removal commenced.
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(b) Paragraph 4.6.5 specifies that sufficient illumination shall be provided. To ensure uniformity in evaluations, a minimum lighting level should be specified that. is considered sufficient.
(2) N-PT-2 - The following discrepancies were noted:
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(a) Paragraph 4.5.5. specifies that sufficient illumination chall be provided. To ensure uniformity in evaluations, a minimum lighting level should be specified that is considered sufficient.
(b) Paragraph 5.1.2 indicates that surface conditioning may preclude the need for re-examination of indications believed to be nonrelevant. Since nonrelevant indications could mask relevent indications, the exar..iner should not have the option to merely condition the surface without also re-examining after condittoring.
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l The licensee agreed to review the above comments and to make changes as necessary. This will be carried as Inspector Followup
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Item 328/81-10-03, "Inadequant liquid penetrant procedure".
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c.
Magnetic Particle (MT) Proceudre The MT procedure is general without data 11ed information to ensure i
uniform examination metnods. The following are examples of what should be included in the procedere:
(1) equipment type (2) application of powder (3) removal of excess powder
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(4) amount of illumination (5)
for weld coverage, the width of the flux field should be defined (6) use of a field indicator (7) personnel qualifications (8) maximum surface temperature for examination (9) maximum MT current for the prod method
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The licensee advised that the MT procedure was already betng revised and most of the examples cited above had been included. The licensee agreed to review the examples identified above and ensure the revised procedure included the information necessary to provide uniform examination methods.
This will be carried as Inspector Followup Item 328/81-10-02, "Inadeauate l
Magnetic Particle Procedure".
No violations or deviations were noted in the areas reviewed.
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4 6.
Containment Penetrations
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a.
Review of implementing procedures The inspector reviewed the Leak Testing Procedure, "Preoperational Test TVA-2B Testable Penetrations", Rev. O, to determine whether it met pragraphs 6.2.1.4.1 and 6.2.4 of the FSAR.
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No violations or deviations were noted.
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b.
Review of Quality Records
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The inspector reviewed the records for Unit 2 containment penetrations X-32, X-20B and 123E to determine whether leak testing had been satisfactorfly accomplished. The following discrepancies were noted.
(1) The wrong date was entered for penetration X-32; the date entered was December 1981 versus December 1980.
(2) All data entered on the record forms was of the same handwriting including the initials of different persons who conducted the tests.
Numerous records for other penetrations were given a cursory review and most were found to have the data entered in the same handwriting, even though different persons had conducted the tests.
In each case the different initials appeared to be in the same printed handwriting. There was no explanation on the records to indicate what had taken place.
The licensee agreed to investigate this situation and resolve accordingly.
This is Unresolved Item 328/81-10-04, " Record Discrepancies on Containment Penetrations".
No violations or deviations were noted.
7.
Inspector Followup Items
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a.
(0 pen) Inspector Followup Item 328/80-22-02, Inadequate visual inspection record card. The licensee is taking action to revise the record card as suggested, but revision to the cards has not been
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completed.
This item will remain open until the revised cards are issued and implemented.
b.
(0 pen) Inspector Followup Item 328/81-03-05, Amount of base metal to be penetrant examined is not specified in the penetrant procedure. The licensee is taking action to revise the penetrant procedure, but has not completed the revision.
It should be noted that the NRC report incorrectly indicated that Section III of the ASME Code applied to the pipe joint in question.
Since the pipe joint was being examined for baseline data,Section XI of the ASME Code applies.
The licensee agreed that Table IWB-2500 of Section XI would ba used in establishing l
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the amount of base metal requiring to be penetrant examined. This item will remain open until the revised penetrant procedure incorporates Table IWB-2500 base metal requirements and is implemented.
c.
(Closed) Inspector Followup Item 327/80-15-02, Extra Support on 6" line on Auxiliary Feedwater Line at Elevation 714 feet not identified in stress isometric.
The inspector was provided with copies of SNP Construction Procedure No. P-47, " Pipe and Pipe Hanger Analysis Drawing Walkdown Inspection" and SNP Inspection Instruction No. DS, " Piping and Supports Walkdown Procedure", which have been implemented to ensure, such items as additional supports are detected and reported. Procedure D5, paragraphs 8.B and 8.D require identification of additional or missing supports. The inspector also reviewed the corrective action report and the walkdown report which verified that the subject " extra support" had been removed. This item is closed.
d.
(Closed) Inspector Followup Item 328/81-03-01, Inadequate protection for penetration bellows. The inspector sighted the penetration bellows that were previously unprotected and several other penetration bellows and found all to be adequately protected. This item is closed.
8.
Licensee Identified Items (10 CFR 50.55(e)
a.
(Closed) Licensee Identified Item 328/81-02-23, Thermon Heat Transfer Cement - CEB 8036.
Licensee's final report is dated March 5,1981.
The inspector obtained a copy of the proposed design change, which was verbally approved, and sighted two hangers of the Safety Injection System wherein the cement had been removed and the proposed design changes had been implemented. Formal design drawing changes have yet to be completed, but the hardware changes have been completed. This item is closed.
b.
(Closed) Licensee Identified Item 328/81-02-08, Seismic supports for auxiliary feedwater control valves - EEB 8017. Licensee's final report is dated August 20, 1980.
The inspector sighted the installation of
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the required struts and the altered supports for steam generator level control valves 2-LCV-3-148 and 2-LCV-3-156. The specified corrective action was accomplished, thus this item is closed.
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c.
(Closed) Licensee Identified Item 328/81-02-05, Design criteria for secondary side pipe breaks - CEB 8012.
Licensee's final report is dated October 29, 1980. The inspector sighted all of the installed supports, sleeve and barriers, and the drawing revisions.
The corrective action was accomplished as specified except that the supports identified as PD-173 will not be completel:r installed until 3/27/81.
The supports ooserved by the inspector are identified as PD-200, PD-201, PD-154, PD-172, OD-181A and PD-181B. This item is closed.
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