IR 05000395/1981006
| ML19352A760 | |
| Person / Time | |
|---|---|
| Site: | Summer  |
| Issue date: | 04/15/1981 |
| From: | Girard E, Herdt A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19352A756 | List: |
| References | |
| 50-395-81-06, 50-395-81-6, NUDOCS 8106020031 | |
| Download: ML19352A760 (7) | |
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UNITED STATES
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NUCLEAR REGULATORY COMMISSION e
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REGION 11 s
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101 MARIETTA ST., N.W., SUITE 3100
ATLANTA, GEORGIA 30303
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Report No. 50-395/81-06 Licensee:
South Carolina Electric and Gas Company Columbia, SC 29218
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Facility Name:
Summer Docket No. 50-395
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License No. CPPR-94 Inspection at Summer site near Columbia, South Carolina Inspector:
MdM N /6 8/
E. H.
irar 0' ate Signed
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Approved by:
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A. R. Herdt, Section Chief Wate ' Signed Engineering Inspection Branch Engineering and Technical Inspection Division SUMMARY Inspected on March 24-27, 1981 Areas Inspected This routine, unannounced inspection involved 28 inspector-hours on site in the areas of licensee action on previous inspection findings, IE Bulletins, licensee identified items (50.55(e)) and review of preservice inspection data.
Results No violations or deviations were identified.
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REPORT DETAILS
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1.
Persons Contacted Licensee Employees
- 0. S. Bradham, Station Manager
- D. R. Moore, Quality Assurance Manager
- S.- J. Smith, Maintenance Supervisor
- A. A. Smith, Site QA Coordinator
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- J. Turkett, Maintenance Engineer
- R. Clary, Senior Licensing Engineer G. Moffat, Engineer D. Lavigne, QA Surveillance Specialist
- T. A. McAlister, QA Surveillance Specialist Other Organizations W. L. West, Project Quality Manager, Daniel Construction Company R. Weber, Westinghouse Nuclear Products NRC Residant. Inspector
- J. L. Skolds
- Attended exit interview 2.
Exit Interview The inspection scope and findings were summarized on March 27, 1981, wi th those persons indicated in paragraph 1 above.
3.
Licensee Action on Previous Inspection Findings a.
(Closed) Unresolved Item (395/79-35-09): Pipe Not Properly Backed Out of Sockets On February 23, 1981, representatives of South Carolin'a Electric and Gas Company (SCE&G) met with NRC personnel in the NRC Reg' ion II offices
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to discuss the acceptability of alleged improperly withdrawn piping for socket welding perform 2d at the Summer site. Based on data and anal-yses presented by SCE&G, Region II considers the condition identified at the Summer site to be acceptable.
Summary information on this meeting is documented in a letter from R. C. Lewis (NRC Region II) to T. C. Nichols, Jr. (SCE&G) dated March 9,1981. This item is closed.
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b.
(Open) Unresolved Item (395/80-30-03): Magnetic Particle Examination Procedures The NRC inspector reviewed a documented response to this item provided by the Level -III NDE examiner responsible for.the subject magnetic particle examination procedure ISI-70. The inspector's concerns were discussed at length with the licensee. They are as follows:
(1)
ISI-70 (R.0, A.1, C.1 and 2) largely describes general require-ments rather than procedural steps. The need for detail is noted in Section 1.2 of SE-138 of ASME Section V (74S75).
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(2)
ISI-70 permits a wide variation of procedures to be used. There are no restrictions either in ISI-70 or the licensee's approval thereof to assure that the individual performing an examination is directed to the procedural variation appropriate to the product form (meterial, shape or size) that is required to be inspected.
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(3) ISI-70 allows deviations from ASME Section V requirements such as use of AC and not requiring use of the continuous method These variations could be determined acceptable in accordance th IWA-2240 of ASME Section XI. However, with no restrictions on product form an indeterminant number of demonstrations of proce-dural variations would be required for approval per IWA-2240.
NOTE: ASME Section V requires that the written procedure include the " materials, shapes or sizes" to be inspected.
The NRC inspector considers this analogous to the term " product form".
(4)
ISI-70 does not adequately identify the ferromagnetic particles to be used in accordance with T-751 of ASME Section V.
4.
Unresolved Items
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Unresolved items are matters about which more information is required to determine whether they are acceptable or may involve violations or devia-tions. A new unresolved item identified during this inspection is discussed in paragraph 7.a.
5.
Status of Inspection and Enforcement Bulletins (IEBs)
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(0 pen) IEB 395/80-BU-21: Valve Yokes Supplied by Malcolm Fcundary Company, Inc.
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The licensee responded to this bulletin in a letter dated February 16, 1981.
The inspector reviewed the response and determined that it was incomplete.
The licensee indicated that they had no valve yokes cast by Malcolm Foundry in their active valves, whereas the bulletin asked that they determine whether they had any valve parts cast by Malcolm Foundary in their active valves. The inspector requested that the licensee provide the NRC Region II a response addressing the question of active valve parts,
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6.
Licensee Identified Items (50.55(e))
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a.
(0 pen) Item 395/80-25-14: Incorrectly Specified and Installed Flange Material The inspector discussed the status of this item with the licensee. The licensee was informed that their report provided for this item remained incomplete. It did not describe the action to preclude recurrence and there was no indication of any checks to assure that the cause had been adequately identified and that the condition did not exter:d to other areas.
The report is required to include sufficient information to permit analysis and evaluation of the deficiency and of th9 corrective action. The inspector noted that the reporting inadequacy for this item had previously been identified ir IE Report 395/81-02, but that Region II had received no additional response.
The licensee stated that they were in the process of obtaining information to complete the response.
The inspector reviewed records and examined two randomly selected examples of installed flanges (DE-RH-03F13 and 5) to verify correction of improper flange materials as described in the report.
b.
(0 pen) Item 395/80-20-02: Piping Attachment Welds The NRC inspector reviewed the licensee's final report for this item dated March 17, 1981. The licensee was informed that the report was considered inadequate in that it failed to indicate any assurance that the condition identified did not extend to other areas, such as equip-ment and piping supports. The licensee was requested to provide a supplemental report response addressing this concern.
c.
(0 pen) Item 395/80-39-01:
Craft Doing Unauthorized Work on Pipe Hangers The inspector discussed the final report dated January 13, 1981,
.provided for this item with the licensee. The ins'pector noted that an '
additional response was required, as indicated in IE Report 395/81-02, and that the response should include a basis. for assurance that the condition does not extend to other areas.
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d.
(0 pen) Item 395/80-30-01: Pipe Hanger Material Traceabi.11ty The licensee's final report on this iten (dated January 13, 1981)
indicates that additioaal information may be forthcoming as a result of planned actions and investigations. This item will remain open until
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NRC Region II determines that the actions and investigations have been
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sufficiently accomplished to assure that the item mry be closed.
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Within the areas examined, no violations of deviations were identified.
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7.
Preservice Inspection Data Review and Evaluation
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The inspector reviewed records for preservice inspection _(PSI) records for compliance with regulatory requirements and FSAR commitments. The applic-able code for preservice inspection, as -identified in the FSAR, is ASME Section XI (74S75).
ASME Section V (74S75) is also applicable through reference from ASME Section XI.
The records reviewed by the inspector included the following:
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a.
Records for three examination areas (as defined in ASME Section XI).
The inspector reviewed the records of. selected examinations in three areas:
(1) Area: B-B Examinations:
Reactor Pressure Vessel (RPV) weld 4 on sketch CGE-1-1100, Pressurizer weld 7 on sketch CGE-1-2100, and Steam Generator weld 1 on sketch CGE-1-3100.
(2) Area: B-N-1 Examinations:
RPV internals identified 1-21 on sketches CGE-1-1200 and 1-1200A.
(3) Area: B-F Examination:
Pressurizer dissimilar metal weld 1 DM on sketch CGE-1-4502.
The records were reviewed to determine whether they contain or provide reference to (where applicable):
Examination results and data sheets
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Examination equipment data
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Calibration data sheets
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Examination evaluation data
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Records on extent of examination
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Records on deviation from program and procedures including justi-
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fication for deviation l
Records on disposition of findings
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Identification of NDE material such as penetrant, penetrant ~
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cleaner, couplant, films, tapes, etc.
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In reviewing the records for areas B-N-1, as described above, the NRC'
inspector. found: that.the listing 'of internals inspected did not entirely match the items depicted on the sketch of the internals (sketch CGE-1-1200). The inspector identified this as unresolved item 395/81-06-01, Inadequate Identification of RPV Internals.
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Records of Pressur_e Retaining RPV Welds
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The ~ inspector reviewed the. records of RPV welds' 4 and 9 (sketch CGE-
-1-1100) to ascertain whether the following requirements were met:
The method, extent and technique of examination comply with
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licensee's PSI program and applicable NDE procedura.
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The examination data are within the acceptance criteria as out-
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lined in applicable NDE procedure and applicable code require-ments.
.The : recoraing, evaluation and disposition of findings are in
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compliance with the applicable NDE procedure and applicable code requirements.
The method used for NDE was sufficient to determine the full
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extent of indication of acceptance.
c.
Records of Pressure Retaining Pipe Welds The inspector reviewed the rec 0* JS for pressure retaining pipe welds identified:
(1) 2 and 8 (Reactor Coolant System piping sketch CGE-1-4502)
(2)
12 and 17 (Reactor Spray System piping sketch CGE-1-4302)
t (3) 3 (Reactor Building Spray System piping sketch CGE-2-0001)
(4) 3-13 (Main Steam System piping sketch CGE-2-2301).
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The records were reviewed to determine whether the following requirements were met:
Collected examination data and any recordable indications are properly
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recorded to permit accurate evaluation and documentation.
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Evaluation of examination data performed by a Level II or Level III
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examiner.
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Evaluation of examination data complies with the procedure.
Within the areas examined, no violations or deviations were identified.
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