IR 05000483/1980019
| ML19338E781 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 08/18/1980 |
| From: | Knop R, Naidu K, Wescott H NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19338E777 | List: |
| References | |
| 50-483-80-19, NUDOCS 8010060128 | |
| Download: ML19338E781 (15) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-483/80-19 Docket No. 50-483 License No. CPPR-139
Licensee: Union Electric Company P.O. Box 149 St. Louis, MO 63166 Facility Name: Callaway Unit 1 Inspection At: Reform, MO Inspection Conducted: July 15-18, 1980
- (m Inspectors:
H. M. Wescott
[- M-[O K. R. Naidu bt h/{
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/f /fo J. F. Schapke
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Approved By:
Projects Section 1 Observer:
R. L. Lee Inspection Summary Inspection on July 15-18, 1980 (Report No. 5050-483/80-19)
Areas Inspected: Routine, unannounced inspection: follow-up of previously identified items; follow-up of 10 CFR 50.55(e) reports; observation of electrical activities; review of battery installation records; observation of installed electrical cable. The inspection involved a total of 75 inspector hours by three NRC inspectors with one NRC observer.
Results: Of the three areas inspected, three items of noncompliance were
' identified (infractions - not establishing requirements for installation of battery racks, procurement of material that did not conform to purchase specifications, welding did not conform to applicable codes).
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DETAILS Persons Contacted Union Electric Company J. Baker, Supervising Engineer, Civil
- S. M. Hogan, QA Assistant Engineer
- M. R. Lane, QA Consultant
- J. Laux, QA Engineer
- J. L. Hardea, QA Consultant
- C. J. Plows, QA Consultant
- R. L. Powers, Superintendent, Site QA
- W. H. Weber, Manager, Nuclear Construction Daniels International Company J. Candrel, Piping Engineer
- J. R. Cook, QC Manager E. Curry, Electrical Craftsman P. Gernert, Electrical Craftsman
- J.
A. Holland,. Civil Engineering Manager D. Jasper, Project Civil Engineer D. Neal, Lead Civil Engineer J. O' Bannon, General Foreman, Electrical R. Papini, Piping Engineer
- W.
L. Petrie, QA Engineer
- A. Ray, QA Engineer
- M. K. Smith, Audit Response Coordinator
- H. J. Starr, Project Manager
- W. L. Sykora, Assistant Project Manager
- B. E. Wells, Group Vice President, Daniels Construction Company Colt Industries G. Gonzales, Field Engineer Hartford Steam Boiler Insurance Company
- H. J. Potter, Authorized Nuclear Inspector U.S. Nuclear Regulatory Commission
- W. Hansen, Resident Inspector
- Denotes those attending the exit meeting on July 18, 1980 at the Callaway site.
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Licensee Action on Previously Identified Items (Closed) Unresolved (483/78-07-04) It was previously reported that on some of the columns in the auxiliary building, the out-of-plumbness exceeded the tolerances permitted by the AISC Code.
Several NCRs were generated and the following was determined:
1.
Erection sequence allowed the tolerances to build up without adequate verification.
2.
An adequate program was not in place to verify the plumbness accurately.
3.
The dimensional errors in the fabrication of structural beams contributed to the out-of-plumbness. A flow chart was prepared for checking structural steel erection and dictated correct erection sequence.
Mr. R. L. Blumenkamp, President of St. Louis Steel Erection Company, was selected as an inde-pendent consultant by the licensee to work with DIC and review the dis-crepancies in survey readings. Nine columns in areas one and two of the
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auxiliary building were found to be outside the allowable plumbness
' tolerance if subjected to a worse case analysis based on some assumptions.
Bechtel, the AE recommended "use-as-is"; their evaluations indicate that the columns are not overstressed by eccentric loads resulting from the out of plumbness of the columns. The licensee's QA superintendent confirmed that these evaluations are available for review at Behetel's office in Gaithersburg.
(Closed) Unresolved Item (50-483/79-01-01) Use of G.E. Model CR105X auxiliary contacts in control circuitry in other than G.E. equipment, (Reference IE Bulletin 78-05). The inspector reviewed a letter, Bechtel to SNUPPS, BLSE 7103, dated April 17, 1979, which stated that a second check was made to verify that the auxiliary contactors are not installed in non-G.E. manufactured equipment. This item is considered closed.
(Closed) Unresolved 483/79-03-05 Additional information and interpretations to the relevant Specification M-204 were provided during this inspection on
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the installation of pipe and pipe hangers. This item is closed.
(Closed) Unresolved Item (79-06-01) All noncenformances not being factored
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into the trend analysis system. The inspector reviewed (1) Quality Memorandum Status Report, QM-186, dated June 28, 1979, " Tracking of Minor Concrete i
Defects", which states that trend analysis provided by DLCU-5391 is filed with Trend Analysis Report No. 14.
Such information will be part of future trend analysis report.
(2) Inter-Office Communication PQC-2433 dated May 19, 1980, " Concrete Repair Trend Analysis Comparison Report No. 13 to 14".
(3)
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UTD, QA-228b dated May 6, 1980, " Follow-up on DIC's Trend Analysis of Concrete Defects".
(4) UTD, QA-228, dated Spetember 26, 1979, " Tracking Minor Concrete Defects".
(5) Letter, Bechtel to SNUPPS BLS6-753, dated August 24, 1979, which discusses classification of concrete defects. This item is considered closed.
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(Closed) Noncompliance (483/79-06-02) Inadequate storage and protection of components. The inspector reviewed, (1) Nonconformance Report No. 2SN-0473-M, dated April 23, 1979 which discussed the rust problem in the reactor vessel and the disposition.
(2) DIC Construction Procedure, Interim Instruction No. 31, Revision 1, dated August 14, 1979, "Special Instructions for Storage Maintenance of NSSS Equipment During Site Installation". This item is considered closed.
(Closed) Unresolved Item (483/79-06-04) and Noncompliance (483/79-06-03)
Daniel International Procedure AP-723, " Material and Equipment Receiving Inspection", requires that subvendor data packages must be received within 60 days of receiving any material. The procedure further requires that if the data package is not received, a nonconformance is to be written to identify the data deficiency. A nonconformance had not been written for reactor coolant system piping, which had been received on site fourteen months earlier with incomplete documentation package.
(Radiographs missing).
The RIII inspector reviewed DIC Nonconformance Report (NCR) #2SN-0816-M dated July 16, 1979 which requests vendor to supply radiographs. The NCR was closed at the receipt of the radiographs. The inspector sampled the referenced radiographs and no deviations or items of noncompliance were noted.
In addition, the licensee conducted an audit of all data packages, (Reference: Surveillance Report No. 5/79-08) of approximately 400 furnished i
by Westinghouse suppliers and reviewed by Westinghouse. This review ascer-
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tained that all required documentation was present and was technically adequate. Technical adequacy was determined by a ten percent sample.
(Closed) Noncompliance 483/79-12-04.
It was previously reported that the manufacturer's recommendations for tightening the cable tray hardware were not translated into Work Procedure WP302. An alternate method of verifying the adeguacy of cable tray hardware connections was developed; this method eliminates the use of a torque wrench.
PW Industries, the cable tray vendor, in a letter dated November 29, 1979, suggested the alternate method.
Pro-cedure WP302 has been revised and paragraph 3.17 of Revision 8 dated February 29, 1980 incorporates this requirem-nt.
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(Closed) Noncompliance (483/80-04-01) A noncompliance for which a reply was
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not required was identified for taking inadequate correction on various i
pipespools with nonconforming conditions. Three samples of pipespools were I
cut and the defects were investigated. ~ Dravo, the manufacturer will replace the spools cut for samples.
(Closed)' Unresolved Item (483/80-06-01) Questionable clearance between liner stiffeners and bottom layer of reinforcement.
The inspector reviewed a letter, Bechtel to SNUPPS, BLSE-8153, dated March 24, 1980, which states tLat the bond is of little concern and that it is not a major concern of the strength developed. The inspector contacted NRR and they agreed with this position. This item is considered closed.
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j (Closed) Noncompliance (483/80-06-02) Improper use of vibrators. The
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inspector reviewed the licensee's response to NRC, ULNhC-348, dated April 17,
1980 and found that the action taken to comply to be adequate. Also, the inspector reviewed a letter, Daniels to U.E. dated March 24, 1980 discussing
action taken in response to this inspection finding. Daniels has revised WP-109, Revision 13, dated June 23, 1980, paragraph 4.1.4 to include minutes l
of pre-planning meetings to be included in data packages. This item is l
considered to be closed.
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(Closed) Unresolved Item (483/80-11-01) Poor placement practice. The i
inspector reviewed Inter-Office Communication, dated May 7, 1980, CM-1164
which stated that a training was held with vibrator operators on May 6, j
1980, instructing them to comply with criteria in Bechtel Specification i
10466-C103(Q) and ACI 309, with an attached liti of attendees. This item j
is considered closed.
(Closed) Unresolved Item (483/80-11-02) Upward sloping lip of a few inches
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on the outside face of construction joints. The inspector reviewed a letter, Bechtel to U.E., BLUE-691, dated May 27, 1980, explaining the purpose of the
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lip on the exterior face of the reactor building dome construction joints
to prevent feathered edges on the bottom of the next lift which are difficult i
to consolidate and susceptible to cracking. This item is considered closed.
l (0 pen) Unresolved Item (483/80-11-03) Ultimate E:at sink rip rap not
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classified as safety related. The inspector reviewed letter, Bechtel to
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U.E., BLUE-676, dated April 11, 1980. This item remains open pending further
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review.
(Closed ) Unresolved Item (483/80-11-05) No written instructions to perform
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moisture density tests. The inspector reviewed Inter-Office Communication PCE-2285, dated April 15, 1980, Reference item 2.c.:
response, the subject report form (exhibit D, QCP-102) specifL2s the elevation of the top of the j
fill being' tested. The depth of this lift can be determined by comparing this elevation to the elevation of the top of the last lift. The required depth of the moisture-density test is thus determined and is also recorded on the nuclear moisture-density test report form".
This item is considered closed.
- (Withdrawn) 10 CFR 50.55(e) report, concerning reactor coolant pump tie rod embeds dated December 22, 1977. Also reported under Part 21 by Teledyne i
Brown Engineering these tie rods have been stress relieved as required. The i
weld material has been found acceptable. Corrective action by Teledyne
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Brown Engineering to preclude recurrance was to add a fabrication routing supplement to the weldsent assembly route sheet for further detailed instructions in performing special processes. The inspector considers this report withdrawn.
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i-Functional or Program Areas Inspected
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Section I Prepared by J. Schapker Reviewed by D. H. Danielson, Chief Engineering Support Section 2 1.
Review of D.I.C. and Technical Services Laboratory NDE Activities Union Electric hired TSL, a subsidiary company of Daniels Inter-
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national to perform the NDE on field welds.
Daniel International welding inspectors also perform NDE to field
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welds according to their respective certifications.
The inspector made a tour of TSL Laboratory facilities.
The following are the inspector's findings.
a.
Radiography (RT)
The NRC license expires August 31, 1984, and covers IR-192 up to 100 curies and CO 60 up to 100 curies.
The Gamma ray sources are stored in a locked concrete building.
No x-ray machines are utilized on site.
An automatic film processor and a hand film processing tank is used to process film.
Survey meters are calibrated i*very 90 days.
Pocket dosimeters are read and recorded every day by radiographers when oerforming RT.
Film badges are processed by Radiation Detection Co. monthly and reported to TSL.
Decay-curves for Gamma Ray sources were posted in the lab.
The lab uses Kodak M, T, AA industrial film, and Dupont 45.
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outdated film was observed.
Film cassettes were in acceptable condition. Lead screens were in marginal condition, the TSL supervisor had new screens on order.
i Flourescent screens are not used nor are there any on site.
Unexposed film is stored in the dark room and NDE supply room in the lab.
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Exposed film is stored in air conditioned, heated, humidity and access controlled vault, i
i TSL uses lead numbers and flashers for identification of
radiographs.
A Macbeth TD 100A and Tech Ops 301 densitometers with radiographic film density step wedge traceable to the Bureau of Standards are utilized by the lab.
ASTM penetrameters are the only penetrameters used on site.
Those examined were in acceptable condition.
Shims were identified properly and in acceptable condition.
The inspector reviewed the following field weld and vendor radiographs:
DIC Field Welds System Weld No.
Thickness Diameter Date RT BN01 FW-37
.615 24" 1/11/80 BN01 FO-40
.525 14" 11/13/78
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BN01 F0-40 R-2
.525 14" 2/6/79 System Weld No.
Thickness Diameter Date RT
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EM03 F0-13
.839 6"
6/2/80 EP01 FO-17 1.270 10" 5/31/80 EFIS FO-12
.337 4"
1/7/80 EJ01 (Q) FW-041 2.615 2"
1/10/80 EJ02 (Q) F0-12A
.495 12" 4/3/79 Vendor Radiographs Dravco System Weld No.
Thickness Diameter Date RT 2-EJ-01 E-3002-34B
.415 10" 4/4/77 2-EJ-01 E-3002-34D
.415 10" 4/4/77 2-EJ-01 E-3002-32E
.415 10" 3/29/77 2-EJ-01 E-3002-33
.415 10" 3/31/77 Pullman Power Products System Weld No.
Thickness Diameter Date RT 2-EN-03-5-058/261 W-A
.280 65/8" 6/30/79 i
2-EN-03-5-058/261 W-B
.280 6 5/8" 6/30/79 2-EN-03-5-058/261 W-C
.280 6 5/8" 6/30/79 2-EN-03-5-058/261 W-D
.280 65/8 6/30/79-7-
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Southwest Fabrication and Weld Company System Weld No.
Thickness Diameter Date RT Loop 1 RCP-SCP W-2 2.436" 29" 6/23/78 Loop 1 RCP-SCP W-3 2.5-5.0" 12" nozzle 6/22/78 to 29" pipe Walworth Company Aloyee Foundry System Weld Thickness Diameter Date 12-HCB-CKS-QW casting 5/802 3/4" 12" 4/27/77 The above systems are:
BN = Borated Refueling Water EM = High pressure coolant injection EP = Accumulator safety injection EF = Essential service water EJ = Residual heat removal EN = Containment spray RCP = Reactor coolant piping b.
Liquid Penetrant Examination The inspector observed storage facilities and verified certifications of Penetrant materials, the inspector also verified qualification report for P.T. for temperature ranges 40 F to 160 F in accordance with ASME Section V, 1974 edition with summer 1975 addenda.
c.
Ultrasonic TSL has a Sonoray 3036 ultrasonic instrument and two Nortec thick-ness gauges in acceptable condition including various calibration blocks.
The lab uses Excsen 20 and 14 couplant and has UT transducers in various sizes, MHZ, and angles.
Certification for the couplant halogen and sulfur content was reviewed.
e.
Leak Test Bubble test equipment with vacuum box is the only leak test utilized by TSL on site. The utilization of this equipment has been limited to fuel pool liner welds only. The equipment condi-tion was satisfactory.
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Visual Examination TSL has 15 inspectors qualified Level II visual, five of which are certified for remote. Remote equipment consists of mirrors, borescopes, or fiber optics. Equirrent is stored in lab excepting some personnel mirrors, which are maintained by the inspectors.
Procedure Review The inspector reviewed TSL QC Procedure No. 7.1.Q Revision 3, April 7, 1980,
" Certification of NDE Personnel" to SNT-TC-1A 1975 edition and the certifica-tions for four personnel.
The inspector also reviewed the following NDE procedures and found them to be in compliance with the applicable ASME Code requirements:
1.
TSL Procedure 7.3C Revision 2 liquid penetrant examination of weldments
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(ASME Summer 1975 Section V, Article 6)
2.
TSL Procedure 7.4A magnetic particle examination of weldments (ASME Section III, V, VIII and ANSI B31.1 through Summer 1975 Addenda).
3.
TSL Procedure 7.5.C3 Revision 3 radiographic examination of weldments (ASME Section V, Article 3 through Summer 1975 Addenda).
4.
TSL Procedure 7.5.G Revision 3 radiography for x-ray and gamma ray examination of weldments.
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Section II Prepared by K. R. Naidu
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Reviewed by D. W. Hayes, Chief Engineering Support Section 1 1.
Observation of Electrical Installation Activities The inspectors observed the installation of the following electrical equipment:
a.
Emergency Diesel Generators Colt Industries supplied the Emergency Diesel Generators (EDG). The licensee personnel stated that the manufacturer's recommendations furnished in Drawing No. 11875612 was used to unload the EDGs and set them in place. Currently, the manufacturer's field engineer is leveling the EDG crankshaft to the requirements in Colt Industries Procedure No. 11875674 titled, " Field Alignment Procedure - Setting and Alignment Instructions". Records indicate that the readings of the levels at various crankshaft positions with the generator uncoupled were being documented and the deflection curves were being plotted. Several other checks include out board bearing alignment, alternator rotor / stator radial gap, coupling bolt final torque, crank-web deflection (cold coupled) and main bearing clear-ance (cold coupled). Af ter assuring that the unit is properly levelled, the main bearing check and deflection curves are satis-factory, a specified grout will be placed between the EDG beam bottom flanges and the foundation. The final alignment checks on the crank
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web deflection and main bearing will be made to verify that the instailation is satisfactory. A procedure for checking the " thrust-bearing clearances" Drawing No. P12 612 942 has been established to verify the conditions reported per 10 CFR Part 21 by Bechtel on May.14, 1980.
b.
Battery and Battery Racks Batteries Type NCX-1650 and Battery Racks were supplied by Gould.
Drawing E-050-0006-02 titled, " Layout for 60 cell NCX battery on 2-507-074530-816 Racks" furnishes the requirements for installing the racks. The inspectors informed the licensee of the following observations:
(1) Rust indications were observed on the angle iron supports welded to the embedded iron. Although the Specification E-050 (Q) for batteries and the racks in paragraphs 8.1.1
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O specifies a minimum of two coats of acid resistant paint, no requirements were established to either touch up the steel after installation or to paint the welds.
(2) Paragraph 3.3 of Appendix A.1 states, " Racks will be installed by means of plug welding". A note on the Drawing E-050-0006-02 states, " Plug weld locations 9/16" diameter". The inspectors pointed out to the licensee that the applicable welding Code AWS D1.1-75 specifies in paragraph 2.8.2 that the maximum diameter of the hole to be welded should not be greater than 2 1/4 times the metal thickness; the thickness of the angle is 1/8" in this case. The inspector informed the licensee that plug welding a 9/16" diameter hole on an 1/8" thick angle iron was not permitted by the AWS DI.1-75 code and was an item of noncompliance, contrary to Criteria IX of 10 CFR 50, Appendix B.
(483/80-19-01)
(3) Most of the hardware - (bolts, nuts, and washers) specified on the bill of materials in the drawing and actually used were not an acid resisting type; one size of hardware was stainless steel.
The inspector informed the licensee that the above examples b (1) and (3)) indicate that design requirements for Seismic Category 1 Class IE equipment were inadequately translated in the design specification and that this was contrary to Criterion III of 10 CFR, Appendix B.
(483/80-19-02)
c.
4.16 KV Switchgear - NB-01 and NB-02 The 4.16 KV switchgear supplied by General Electric (GE) is installed at 2000' elevation and is welded to four steel embedments.
A note on the drawing E-009 specifies plug welding a 0.7" diameter hole and 3/16" fillet weld. AWS D1.1-75 does not permit plug welding a 0.7" diameter hole. The inspectors informed the licensee that this was another example of incorrect specification identified in paragraph 1.b.
The inspectors selectively inspected the fillet welds and determined them acceptable. Rust has formed on some of the welds; there appears to be no requirement to paint the welds after they have been inspected.
d.
480 Volt Load Control Centers The Load Control Center (LCC) consists of a 4160/480 V transformer comparment and 480 volt circuit breaker assembly. The inspector
- observed the installation of LCCs identified as NG-02 and NG-01.
For the transformer compartment, NCR 2SN-0540-E was generated to identify that the holes on the transformer feet were a maximum 1/4" outwards and therefore could not be installed to the require-ments of drawing E-017; rework assignment RA-EQR-3109, dated I
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June 18, 1979 was issued to widea the holes and to weld 2" x 3/4" x 3" and 1/4" x 1 1/4" bars and use a 2 1/2" x 5/16" washer. The welds were acceptable.
1" x 5/8" slot welds were used to weld the switchgear to the embedded steel as indicated in the drawing E-017.
e.
480 Volt Motor Control Centers The requirements for installing the 480 volt Motor Control Centers (MCC) supplied by ITE/Gould are furnished on drawing E-017 and ITE Manual E-018-043; 1/4" size fillet welds 3" long are specified.
The inspectors observed that 480 volt MCC identified as NG-01A were attached to the embedded steel with 1/4" size fillets 3" long.
f.
Main Control Panels The main control panels are attached to the embeds with a 1/4"
size continuous fillet field weld as specified. The inspectors observed that the field welds are acceptable.
Two items of noncompliance were identified in the above area.
2.
Review of Battery Installation Records The inspectors reviewed the following records relative to the installation of the batteries and battery racks:
The Electrical Equipment Installation Checklists (EEICs) for the a.
batteries identified on NK 11, 12, 13, and 14 have been partially completed; the final review has not been completed. The following attributes are verified:
(1) Location of equipment meets the drawing requirements.
(2) Torque value of the bolts on the battery racks.
(3) Visual inspection of the installed equipment.
i (4) Equipment adequately protected from damage.
(5) Electrical connections are complete.
(6) Environmental protection equipment has been installed and is operable.
(7) Equipment properly identified.
(8) Equipment is levelled per Bechtel/ vendor drawing.
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b.
Battery Racks Welding Inspection Records (1) Welding Quality Control Surveillance Reports (WQCSR) dated Februa ry 21, 1980 indicates that 42 plug attaching each of the battery racks for battery NK11 to the embed were welded to Weld Procedure Specification (WPS) N-1-1-A-8; the welds were determined acceptable. The NRC inspector informed the licensee that this inspection record is considered unacceptable because plug welding 9/16" holes is not acceptable to paragraph 2.8.2 of the AWS D1.1-75 and therefore c nsidered another example of noncompliance with Criteria IX of 10 CFR 50, Appendix B, identified in paragraph Ib of Section II of this report.
(483/80-19-01)
(2) WQCSRs dated March 14 and 17, 1980 indicate that all welds attaching the North and South battery racks of Battery NK12 to the embeds met the drawing E-050-009-02 requirements.
(3) SWCSR dated February 22, 1980 indicates that all welds attaching the NK13 battery rack to the embed met the requirements of drawing E-050-009-02.
(4) WQCSR dated February 20, 1980 indicates that the welds (84)
attaching the two NK14 battery racks to the embed met the requirements of d iwing E-050-006.
(5) Review of the qualification records of the weldors identified in the above WQCSRs indicate that the weldors were qualified to the WPS used.
(6) WPS N-1-1-A-8 is prequalified to AWS DI.175. The inspector informed the licensee that inadequate information was available in above items (2) and (3) as to how many welds were inspected.
Further review is planned during followup of the item of noncompliance.
3.
Review of Receipt Inspection Records The inspectors reviewed the following receipt inspection records:
a.
Material Control Report (MCR) B-01701 dated July 25, 1977 indicates that one section of 4.16KV switchgear was received and the folleving were acceptable:
(1) No visual shipping damage (2) Name plate color coding and data in accordance with purchase order (3) Spaccheaters in each compartment
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(4) Provision to padlock breaker in both raised and lowered positions (5) Access to circuit breaker and rear compartments (6) Terminal blocks are of correct type and installed at acceptable
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locations (7) Wiring is type SIS 600 volt and splice free with not more than two wires on each terminal block.
(8) Bechtel's G321D Form indicates that 4.16KV switchgear supplied by General Electric met all the requirements specified.
Certified Test Reports on the 4.16KV switchgear were attached.
MCR B-04164 dated March 28, 1979 indicates that Load Center
l Unit Substations consisting of Transformers 2XNG01, 02 and Load Centers 2NG01, 02 were received with Bechtel's G321 D
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Forms.
The report indicates that the material was put on hold; however, no details such as NCR were provided as to why it was on hold. As such, it could not be determined how it was released for installation. The licensee's electrical QA engineer who identified this discrepancy during review, a
agreed to investigate this matter and provide additional information. This is considered unresolved.
(483/80-19-03)
Various " Supplier Deviation Disposition Requests" were attached.
One of the reports indicates that additional testing has to be performed to qualify the equipment to IEEE 323-1974. The
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switchgear is identified with a " Hold Tag".
Certified Test Reports indicate that the switchgear successfully completed the " Production Testing" requirements of paragraph 5.3 of I
c.
MCR B-02640 dated April 6, 1978 indicates that 7-MCCs including i
2NG01A and 2NG02A (safety related) supplied by ITE/Gould were received on site. The equipment was placed on " Hold" and NCR 2-2603E was generated; the NCR was closed on March 30, 1979.
Several SDDRs were enclosed; it is stated that the requirements of IEEE 323 and 344 were not completely met.
d.
Receiving Inspection Report (RIR) B-05-85 dated July 5, 1979 indicates that contrei patcls RL 025-028 were received.
Inspection requirements outlinea in Material 1:eceiving Instructions attached were completed.
Bechtel's G-321-D form indicates no adverse findings.
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Consip Customline Corporation (CCC), the supplier of the main control panels subcontracted the fabrication of the panels to Metal Fab. CCC's Receiving Inspection Report dated February 8,
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1979 indicates that the welds were acceptable. Reports indicats o
l that panel continuity tests and Hi-Pot tests were performed.
The inspectors reviewed the relevant specification J-200 (Q) and determined that no specific requirements were imposed that the structural welds should be performed and inspected to a recogniz-able welding code such as AWS D1.1.
The licensee acknowledged the absence of such requirement; however, the licensee produced a Weld Procedure Specification (WPS) from CCC and stated that the WPS was used to fabricate the Main Control Panel. The WPS reflects the AWS DI.1-76 requirements. The inspectors observed that many of the structural welds would not meet the AWS D1.1-76 requirements relative to sizes porosity, and slag; the licensee and contractor personnel concurred with the NRC inspector's finding.
Insufficient.
information was available at the site to determine what actual weld configurations were used to calculate the seismic design
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adequacy. The inspectors informed the licensee that *.he control of purchased equipment was inadequate and that this was contrary to the requirements of Criteria VII of 10 CFR 50, Appendix B.
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The licensee acknowledged the finding and initiated an inspection.
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A Deficiency Report was generated to document welding discrepancies.
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(483/80-19-04)
One item of noncompliance was identified in the above area.
4.
Observation of Installed Electrical Cable The inspectors observed the installed cable identified as INGYOIAA
connecting switchgear NG0101 and NGVARI. The inspectors along with the contractor's personnel, traced the cable through the various raceways with a cable detector and determined that the cable was routed as specified in the cable pull sheet.
No items of noncompliance were identified in the above area.
Unresolved Items t
Unresolved items _are matters about which more information is required in order to ascertain whether they are acceptable items or items of noncompliance or deviations. Unresolved items disclosed during this inspection are
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discussed in Section II, paragraph 4b.
!
Exit Interview
,
.
The inspectors met with licensee representatives (denoted under Persons
'
Contacted) at the conclusion of the inspection on July 18, 1980. The inspectors summarized the scope and findings of the inspection. The licensee acknowledged the icformation.
,
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