IR 05000456/1980004
| ML19321A220 | |
| Person / Time | |
|---|---|
| Site: | Braidwood |
| Issue date: | 06/09/1980 |
| From: | Gallagher E, Schweibinz E, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19321A208 | List: |
| References | |
| 50-456-80-04, 50-456-80-4, 50-457-80-04, 50-457-80-4, NUDOCS 8007230019 | |
| Preceding documents: |
|
| Download: ML19321A220 (9) | |
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U.S. NUCLEAR REGUALTORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Reports No. 50-456/80-04; 50-457/80-04 Docket Nos. 50-456; 50-457 Licenses No. CPPR-132; CPPR-133 Licensee:
Commonwealth Edison Company P.O. Box 767 Chicago, IL 60690 Facility Name:
Braidwood Nuclear Power Station, Units 1 and 2 Inspection At: Braidwood Site, Braidwood, IL Inspection Conducted: May 14-15, 1980 S.
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Inspectors:
E. R. Schweibinz (Ma, 15, 1980)
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Gqllaghe (May 15, 1980)
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O K. R. Naidu f W. 7,,
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Approved By:
C. C. K lliams, Chief
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Proj ect: Section 2 Inspection Summary Inspection on May 14-15, 1980 (Report Nos. 50-456/80-04; 50-457/80-04)
Areas Inspected: Site tour; quality of water for concrete and ground water control; electrical work activities; electrical cable tray hangers; and review of quality records. The inspection involved 20 inspector-hours
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on site by three NRC inspectors.
Results: Of the five areas inspected, no items of noncompliance or devia-tions were identified in four areas. One apparent item of noncompliance was identified in one area.
(Infraction - failure to assure design basis correctly translated into specifications - Section III, paragraph 2).
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DETAILS Persons Contacted Commonwealth Edison Company
- R. Cosaro, Project Super intendent
- R. Farr, Quality Assural.ce Engineer
- M. Gorski, Quality Assurance Engineer
- J. Merwin, Lead Mechani:a1 Supervisor
- C. Mennecke, Electrical Supervisor
- T. Sommerifeld, Quality Assurance Supervisor L. K. Comstock & Company (LKC)
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R. Brown, Quality Assurance / Quality Control Supervisor L. Facchina, Project Manager R. Yanketis, Quality Control Welding Inspector J. Neese, General Foreman The inspectors also contacted other contractor and licensee personnel during the course of the inspection.
- Denotes those present at the exit meeting.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (456/80-03-01; 457/80-03-01): The NRC inspector requested the licensee to obtain additional information from Sargent &
Lundy the AE on an evaluation of the following items:
(1) The unpainted spot welds on electrical cable tray hangers fab-ricated from back to back welded unistruts.
(2) Unpainted carbon steel plates used in the assembly of electrical cable tray hangers.
During the current inspection, the NRC inspector observed extensive use of unpainted tubular carbon steel and unpainted carbon steel plates in the installation of cable tray hangers. A review of the Braidwood PSAR indicates that the commitments have not been adequately translated into specifications which would have prevented the use of unpainted hardware.
The unresolved item is considered closed and this item is escalated to an item of noncompliance, contrary to the requirements of Criterion III of-10 CFR 50, Appendix B. (456/80-04-02; 457/80-04-02) See Section III, Paragraph 2 for further details.
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(0 pen) Unresolved Item (456/78-06-03; 457/78-06-03):
Chloride ion in concrete batching water reported as 325, 319, 318, 360, and 320 PPM ex-ceeding specification maximum of 250 PPM in S&L Specification L-2722, Section 3.307.1.
This item was reviewed and remains open as described in Section 11 paragraph 2.
Functional or Program Areas Inspected Details of functional or program areas inspected are discussed in Sections I, II, and III of this report.
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Section I Prepared by E. R. Schweibinz Reviewed by C. C. Williams, Chief, Projects Section 2
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Site Tour An extended site tcur was made to determine the status of construction and the storage and maintenance of equipment and materials.
No items of noncompliance or deviations were identified.
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Section II
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Prepared by E. J. Gallagher Reviewed by D. W. Hayes, Chief Engineering Support Section 1 1.
Tour of Braidwood Units 1 and 2 A tour of tne._aidwood facility was made on May 15, 1980 regarding the in place storage and handling of safety-related components and equipment. The batch plant facility used for production of concrete was inspected and found to be in acceptable condition with weight scales for materials with calibration tags.
Dcring the tour, the inspector observed concrete cracking on the dome of the refueling water storage tank structure and at slab elevation 346 (column line V.5-19).
These areas were pointed out to the licensee representatives and requested that an investigation into the causes and effects of the crack be made by the licensee.
2.
Qualify of Water for Concrete and Ground Water Control The inspector indicated to the licensee that the previously identified unresolved item (456/78-06-03; 457/78-06-03) remains open. The in-spector indicated that excessive amounts of chloride have been per-mitted to be used in the quality of water for concrete production.
The amounts of chloride exceed the limit set forth in ACI 318-71 (commentary section 3.4.1) and ASME Section III, Division 2, Section CC-2223.
In addition, the groundwater which also contains chloride was <? served to be continuously leaking into the Units 1 and 2 containments tendon access gallery at numerous areas in the walls and ceiling. The in-spector observed apparent effects of the groundwater in the form of corrosion of the embedded steel (reinforcing) and by the presence of deposits of iron oxide on the walls of the tendon gallery. Other undetermired deposits were also observed to be on the concrete surface.
Samples of the deposits have been taken and efforts made to have complete chemical analysis and concentrations made of the deposits.
4The licensee has failed to control groundwater seepage into the con-
<tainment building tendon gallery. The licensee has not acknowledged the significance of the condition with respect to corrosion of embedded safety-related structural steel.
This item remains unresolved.
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Section III
Prepared by K. R. Naidu Reviewed by D. W. Hayes, Chief Engineering Support Section 2 1.
Observation of Electrical Work Activities
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The inspector observed the installation of the following electrical components:
a.
480 Volt Motor Control Center (MCC) identified as bus 132X5, equipment No. IAP32E was installed at elevation 426' 0" columns L-Q, 15-21, as per S&L drawing 3352. The MCC was welded to the embedded steel with 1/8" size fillet weld, 1 1/2" long, staggered at 9" intervals as specified in the installation drawing 3391 sheet 2 in detail 21.
b.
Unit transformer section of switchgear identified as bus 134X equipment No. 1AP16E was installed at elevation 426' 0" L-Q, 10-15, according to drawing 3351. The installation details in drawing 3391E, sheet 3, detail 62 specify 1/8" size fillet weld, 4" long staggered at 12" intervals. The inspector observed that the welds were contrary to this requirement and were measured to be 1 1/2" long staggered at 9" intervals. The contractor could not determine whether the welds were inspected and accepted.
This subject is discussed further in paragraph e.
c, Direct Current MCC identified as IDC05E was installed at eleva-tion 451'-0", columns L-Q, 6-10.
The installation details in drawing 3391C, sheet 1, detail 38 specify 1/8" size fillet, 1 1/2" long staggred at 12" intervals. The inspector observed that the welds in place were 1 1/2" long staggered at random lengths between 13 1/2" to 14 1/2" in the front of the cabinet.
A check list dated September 12, 1979 indicates that the welds were inspected and determined acceptable. The licensee and the contractor personnel concurred with the NRC inspector that the welds were unacceptable. This subject is discussed further in paragraph e.
d.
Direct Current Inverter Power Supply identified as IP05E was observed to be install at elevation 451' 0" columns 6-10, L-0.
The installation details are provided in drawing 3391C detail 29; the cabinet is to be placed on four 5/8" foundation bolts which project 9" above the floor surface.
The inspector observed that the hole in the front right hand corner was widened-6-
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to accomodate the cabinet and the fastened' nut was not covering the entire widened hole. This subject is further discussed in the next paragraph.
e.
The inspector di'
_J the above findings with licensee personnel and principal personnel of L. K. Comstock (LKC), the electrical contractor and determined the following:
(1) Since 3KC cannot establish the inspection status of various installed equipment, (the construction was halted for a few months) a reinspection will be performed and documented.
(2) The NRC inspector stated that the current inspection check-list was not specific and therefore inadequate. The LKC QA manager stated that a revised checklist was in the process of being developed and will incorporate the exact acceptance criteria extracted from the installation drawings and will include both welded and bolted installations.
(3) The licensee QA cognizant engineer stated that a NCR would be generated to document the above inspection findings.
This unresolved item along with the corrective action taken to resolve the NCR will be reviewed during a subsequent inspection.
(456/80-04-01; 457/80-04-01)
No items of noncompliance were identified in the above area.
2.
Observation of Installed Electrical Cable Tray Hangers The inspector observed unpainted carbon steel tubular steel installed ar various places in the cable spreading room at elevation 439' 0".
Several unpainted carbon steel plate sections of various forms were welded to galvanized steel and installed in place. A similar situa-tion was identified inside the containment and identified as an un-resolved item 456/80-03-01; 457/80-03-01 pending an evaluation from S&L as to whether the rust would withstand 40 years of service without deleterious effects. The NRC inspector determined that the use of unpainted metal, which would be subject to corrosion during the normal plant operation, is contrary to the following requirements:
a.
10 CFR 50, Appendix A, Criterion 4 states in part, " Structures, systems, and components important to safety shall be designed to accomodate the effects of and to be compatible with environmental conditions associated with normal operation, maintenance, test-ing and postulated accidents, including loss of coolant accidents.
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In response to the above criteria, the Braidwood Preliminary Safety Analysis Report on page 3.1-3 states that safety related systems, components and structures in this plant are designed to accomodate all normal or routine environmental conditions as well as those associated with postulated accidents (where appropriate).
b.
Paragraph 6.2.1.6, titled, " Containment Coating Systems:, states that all containment coating systems will conform to the require-ments of ANSI N512, N101.2, and N101.4 and that each of these systems will provide corrosion protection for the exposed metal and cocrete surfaces and will facilitate the decontamination process.
It is apparent that this requirement was not trans-lated into design specifications which would require carbon steel material to receive shop prime coat prior to installation pending final coating.
c.
Paragraph 318.2.6.1 titled, " Applicable Construction Codes",
on page 3.8-61 in subsection 0 indicates that the AISC Manual of Steel Construction is one the codes of practice used to establish standards of construction procedure.
Section 1.24 titled, " Shop Painting" in paragraph 1.24.1 states in part, "Unless specifically exempted, all other steel work (which is not concealed by interior building finish or encased in concrete) shall be given one coat of shop paint, in
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accordance with he following paragraph, by brush, spray.
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at the election of the fabricator." No exemptions made, were available.
d.
Sargent & Lundy Specification 2831 titled, " Field Finish Coating Work" supplements the final coating of the installed equipment including hanger material specified in Specification 2815.
Table 302.4, Schedule 1, titled, "Specified Surfaces" indicates on page 3-6 that the structural, equipment supports, pipe sup-ports, gallery or miscellaneous steel should have received a
" shop prime paint".
On the assumption that all carbon steel received a " shop prime coat, surface preparation system" SL-SP3 and coating system SL-CS5 have been specified.
Since the mis-cellaneous steel used in the assembly of electrical hangers did not receive a prime shop coat, SL-SP3 may have to be revised to SL-SP1 or SL-SP2 which may include blast cleaning.
Furthermore, Specification 2815 in various standards, addresses touching up of stick welds with zinc rich paint but does not address the painting of spot welds on back to back welded
'U'-shaped pregalvanized channels.
The inspector informed the Braidwood Project Superintendent, on May 16, 1980, subsequent to the inspection, that the commit-ments in paragrpah 6.2.1.6 and 3.8.2.6.1 of the Braidwood PSAR-8-
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were inadequately translated into Specification 2815 and that this was an item of noncompliance contrary to the requirements of Criterion III of the 10 CFR 50, Appendix B.
(456/80-04-02; 457/80-04-02)
One item of noncompliance was identified.
3.
Review of Quality Records The inspector selectively reviewed records related to the installed equipment.
a.
MRR No. 10572 dated July 20, 1978 indicates that three Instrument Power Supply Control panels including panel identified as IP05E were received from Westinghouse without any apparent shipping damage.
Westinghouse Quality Release No. 36246 dated June 17, 1977 certifies that the equipment meets the applicable requirements.
b.
MRR No. 4441 dated April 30, 1979 indicates that Motor Control Center (MCC) for 125V D.C. service identifies as IDC05E was received from General Electric Company (GE) without any apparent shipping damage.
Certificate of conformance from GE states that the MCC's meet the requirements of IEEE 323, 344 ANSI N 45.2, and S&L Specifica-tion 2722 and IPCEA.
c.
MRR 4810 dated June 27, 1979 indicates that five Class 1E Motor Control Centers (MCC's) identified as IAP030E, IAP32E, 1AP25E, IAP27E, and 1AP4E were received from Westinghouse without any shipping damage.
Certificates of conformances from Westinghouse indicate that the MCC meet the requirements of ANSI N45.2 and Specification 2755.
d.
MRR 4150 dated March 13, 1979 indicates that three Transformer-Power Centers including equipment identified as IAP16E were received from Westinghouse without any shipping damage. Test certificates from Westinghouse indicate that the specification requirements were met.
No items of noncompliance were identified in the above area.
Exit " acting The 1:apectors met with site staff representatives (denoted in the Persons Contacted paragraph) at the conclusion of the inspection on May 15, 1980.
The inspectors summarized the scope and findings of the inspection.
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