IR 05000373/1979021
| ML19248D693 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/22/1979 |
| From: | Barrett P, Neisler J, Williams C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19248D688 | List: |
| References | |
| 50-373-79-21, 50-374-79-15, NUDOCS 7908170179 | |
| Download: ML19248D693 (14) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND EhTORCEMENT
REGION III
Report No. 50-373/79-21; 50-374/79-15 Docket No. 50-373; 50-374 License No. CPPR-99; CPPR-100 Licensee:
Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name:
La Salle County Station Inspection At:
La Salle Site, Marseilles, Illinois Inspection Conducted: May 29-31, 1979
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Inspectors:
P. A. Barrett ( - J / ' 7 7,
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C. Eu Jones 6 - 44 a
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J. J. Harrison
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Approved By:
C. C. Williams, Acting Chief
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Projects Section 2 Inspection Summary Inspection on May 29-31, 1979 (Report No. 50-373/79-21; 50-374/79-15)
Areas Inspected:
Observation and review of procedures and records relative to suppression pool modifications on Units 1 and 2; verification of licensee's response to IE Bulletins; observation of activities relative to safety related HVAC systems (Units 1 and 2); records and activities relative to weld bead straightening CRD housings in Unit 1; observation of electrical work activities; and licensee actions on previous findings.
The inspection involved a total of 50 inspector-hours onsite by four NRC inspectors.
Results:
In the five areas inspected, no items of noncompliance or deviations were identified.
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DETAILS
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Persons Contacted Principal Licensee Employees
- L. J. Burke, Site Project Superintendent
- R. T. Rose, Project Structural Engineer
- T. E. Quaka, Site QA Supervisor
- W. J. Shewski, QA Manager
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J. McAndrew, Statior. Construction
- D. L. Jentz, SNED
- L. Tapella, QA Engineer
- K.
W. Steele, Station Construction kT. R. Sommerfield, QA Engineer
- R. A. Braun, QA Engineer
- M. E. Lohman, Field Engineer D. Spencer, QA Engineer
- J. D. Diebeck, Field Engineer
- R.
C. Lescinski, QA Engineer
- W.
J. Groszko, Field Engineer
- E. Wendorf, Field Engineer
- J. E. Steinmetz, Field Engineer
- J. Harchut, Field Engineer Contractor Personnel
- M. R. Dougherty, QA Supervisor, Walsh Construction Company
- R. E. Spencer, Site Superintendent, General Electric
- C. T. Brinson, QA Supervisor, General Electric
- R. C. Schulz, QC Supervisor, Morrison Construction Company
- R. Ouzts, QA Manager, H. P. Foley Company J. Courtney, Site Manager, Reactor Controls Incorporated
- Denotes those present at the exit interview.
License.e Action on Previously Identified Items (Closed) Noncon.pliance (373/79-11-03):
Failure to identify burned cables.
The RIII inspector and the site QA manager reinspected the cited cables during the IE inspection period dated April 3-6, 1979.
The area around the cables had been cleaned of the charred debris. The reinspection-2-l,h
revealed that only three (3) cables - No. ILP022, No. 1RH150, and No.
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1RF010, had questionable damage. These three cables have been identified on CECO Nonconformance Report No. 287 datcd March 3, 1979, and either have been or will be replaced.
(0 pen) Noncompliance (373/79-11-05):
Failure to maintain cable bend radius as specified in instruction HPFCo-WI-400, Rev. 4.
During this inspection, the licensee indicated that the bend radius requirements specified in WI-400 were for cables in tension (during installation).
Additional information obtained from the manufacturer (Okonite) of the cited cables revealed that the bend radius requirements for cables after installation (not in tension) were more lenient. The cable bend radius violations, identified by a complete walkdown and documented on HPFCo.
Nonconformance Reports No. 122 and No. 123 and CECO Nonconformance Report, NCR, No. 290, were compared to the new bend radius criteria. Only two cables - No. 1RH190 and No. IVD023, did not comply with the new criteria.
Per NCR No. 290, these cables will oe replaced.
Instruction No. HPFCo-WI-500, Rev. 6, for cable terminations, ha.s been revised to identify the additional cable bend radius requirements for Okonite cables, not in tension. The licensee is reviewing options to be taken to control the bend radius of cables not in tension and supplied by other pertinent manufacturers.
(0 pen) Noncompliance (373/79-11-06): Failure to assure that maximum cable pull tensions were not being exceeded.
During this inspection, the RIII inspector reviewed and discussed the engineering analysis and calcu-lations for 84 questionable cases in which maximum cable pull tensions may have been exceeded. The calculations were made using both the postu-lated coefficient of friction (0.4) and the actual tested coefficient friction (worst case--0.55).
The analysis and calculations for worst case identified 2 out of 30 conduit situations including 8 out of 140 safety related cables in which the maximum pull tensions could have been exceeded. These eight cables have been identified on a Nonconformance Report and placed on hold. Disposition for these eight cables has not been obtained.
The engineering analysis and calculations indicated that conduit runs which included composite bends of less that 270 provided no cable pull tension problems.
Therefore, the licensee stated that the appropriate H. P. Foley Company instructions would be revised to require measurements to be taken for cables pulled through conduits of composite bends over 270.
(Closed) Unresolved Item (373/79-11-08):
QC inspection of cable installation activities in a timely manner.
Instruction No. HPFCo-WI-400 for Cable Pulling has been revised (Rev. 5, dated April 13, 1979) to include a QC Cable Pulling Inspection Checklist (Form HPFCo-009, Rev. 0) to assure that all cable installation criteria are verified by QC in a timely manner and documented. During this inspection, the RIII inspector observed the in process installation of two cables (pulled simultaneously). A QC inspector was present during the installation activities.
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(0 pen) Noncompliance (373/79-13-02):
Failure to specify bolting materials to be used for cable terminations. The licensee located two conflicting standards which specify bolting materials to be used for the cited terminations.
Sargent and Lundy Standard No. STD-EA-111 specifies cadmium plated materials and CECO System Standard No. C849 dated March 15, 1973, specifies stainless steel materials.
S&L Specification J-2559, Paragraph 304, states that CECO Standards take president.
CECO Nonconformance Report No. 312, dated May 17, 1979, has been written to identify that incorrect cadmium plated materials were used to make the cited connections.
Disposition for Nonconformance Report No. 312 has not been received.
(Closed) Open Item (373/79-13-04):
Corrective action required for depres-surized electrical penetration No. IC51-S303.
Instructions to restore the integrity of penetration No. IC51-S303 were telecopied to the licensee on March 26, 1979.
These instructions have been identified as the disposition to Nonconformance Report No. 295 dated March 27, 1979, which addressed the depressurized penetration.
(Closed) Open item (373/79-13-08):
Incomplete electrical penetration installation records. During this inspection, the RIII inspector reviewed the penetration installation records and found them complete.
The defi-ciencies concerning the flange bolt size and the corresponding torque requirements were documented to be correct.
(0 pen) Open Item (373/79-13-11):
Separation of instrument cable ground wires. Engineering Change Notice No. EE-12, dated August 14, 1978, was written to require the ground (drain) wires to be insulated in accordance to S&L Standard STD-EA-216.
CECO Nonconformance aeport, NCR, No. 311, dated April 27, 1979, identifies various cables installed prior to Notice EE-12 which do not comply with standard STD-EA-216.
Disposition for NCR No. 311 has not been received.
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Section I
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Prepared by J. H. Neisler Reviewed by C. C. Williams, Acting Chief Projects Section 2 1.
Licensee Actions and Responses to Inspection and Enforcement bulletins The inspector reviewed the licensee's responses and actions taken relative to the following Inspection and Enforcement Bulletins:
a.
IE Bulletin 77-07:
Licensee's response that the Amphenol Sams electrical penetrations would not be used in Unit I was verified by the inspector. Penetrations manufactured by Conax Corporation are installed in Unit 1.
These penetrations are designed with a pressure fitting which does not use epoxy seals as described in the bulletin.
Unit 2 penetrations have seals manufactured as described in the bulletin. These penetrations are equipped for pressurization with nitrogen and will be installed with an automatic pressure system to insure that no moisture enters the penetration.
Action relative to this bulletin is considered complete.
b.
IE Bulletin 78-01:
Licensee's response that GE's CR120A relays were not used in safety related systems was verified by the inspector.
The inspector did not find these relays specified on drawings on instructions for any safety related system inspected.
Licensee's response and action is considered adequate.
c.
IE Bulletin 78-02:
Licensee's response that unprotected terminal blocks are not used in safety related systems was verified by the inspector. No unprotected terminal blocks were noted during tour of containment and reactor building.
Action is considered complete for this bulletin.
d.
IE Bulletin 78-10:
Licensee's response that hydraulic snubbers are not used in safety related systems was verified by the inspector. Only mechanical snubbers are installed in La Salle safety related systems.
Action relative to this bulletin is considered complete.
e.
IE Bulletin 79-03:
Licensee's response that SA312 stainless steel pipe welded without filler metal (manufactured by Youngstown Welding and Engineering Company) is not used at La Salle was verified by the inspect Review of purchase dccuments,
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installation records and code data reports available at the site indicate that SA312 pipe welded without filler metal and manufactured by Youngstown Welding and Engineering Company is not used at La Salle.
This bulletin is considered closed.
f.
IE Bulletin 78-04: The licensee committed to replace the Namco type EA-700 switches on the MSIVs eith Namco type EA-740.
The inspector observed that the type EA-700 switches are presently installed on the MSIVs.
Licensee representative at the exit interview reiterated the commitment to replace the EA-700 switches with EA-740 switches.
Action regarding this bull.etin is incomplete.
g.
IE Bulletin 79-04:
Licensee's response that Velan swing check valves are not installed in any Seismic Category I piping system was verified by the inspector. Review of valve schedules, drawings, specifications, code reports, and a walk through of three systems indicate that no Velan swing check valves are installed in Units 1 and 2 Seismic Category I piping systems.
Action relative to this bulletin is complete.
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Section II Prepared by P. A. Barrett Reviewed by D. W. Hayes, Chief Engineering Support Section 1 1.
Observation of Electrical Work Activities a.
The RIII inspector observed the par in process installation of control cables No. ILC038 and Nt 1LC039. The cables were installed simultaneously and coiled after approximately 350 feet.
The cables were installed in accordance with instruction No. HPFCo-WI-400, Revision 5.
The raceway internals were free of hazardous debris and sharp edges. The cables were routed as specified on the installation card. No separation problems were identified. The cables were undamaged.
The raceways were properly identified.
The cable types were as specified on the installation records. The cables were installed in cable trays, during the observed activities. Therefore, no special attention had to be given to the maximum pulling tensions and pulling compound was not needed.
The minimum bend radii of the cables were maintained. A QC inspector was present during installation activities.
b.
The RIII inspector observed and discussed the current status of the following four 4160 volt motors:
RHR Pump Motor No. 1E12-C002A RHR Pump Motor No. 1E12-C002B RHR Pump Motor No. 1E12-C002L Low Pressure Core Spray Pump Motor No. 1E21-C001 The motors either have been or will be removed from installa-tion to allow rework and/or testing of their corresponding pumps.
The licensee stated that the status of the motors and pumps has been documented and is controlled. The motor instal lations will be reviewed during a subsequent inspection.
(373/79-21-01)
No items of noncompliance were identified.
2.
Review of Electrical Installation Records The RIII inspector reviewed the installation records (Morrison Construction Company Equipment Assembly Control) for two of the standby diesel generators (No. ODG01K and No. 1DG01K) and the High
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Pressure Core Spray diesel generator (ho. 1E22-S001).
The records
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identified that the installation criteria had been checked by the craft superintendent, partially checked by CECO Station Construction, and essentially not checked by Morrison Construction QC.
The Morrison Construction QC Manager indicated that the supplier (Stewart &
Stevenson) of the generators was responsible for the QC inspection activities.
During a phone conversation with the licensee and the RIII inspector, the Stewart & Stevenson representative indicated that QC inspection documentation would be forwarded tr the site.
The documentation would substantiate that the CECO and Stewart &
Stevenson installation requirements have been fulfilled.
This matter is unresolved.
(373/79-21-02)
No items of noncompliance were identified.
3.
Plant Design The licensee stated that there were no safety r21ated D. C. Distribution Cabinets / Panels separate from the main load control centers.
The licensee stated that all motor operated valve actuators have been supplied and installed with the corresponding valves.
Therefore, there is no need for additional or special installation requirements for local mounted D. C. Distribution Cabinets or for motor operated valve actuatore.
No items of noncompliance were identified.
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Section III Prepared by J. J. Harrison C. C. Williams Reviewed by D. H. Danielson, Chief Engineering Support Section 2
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Suppression Pool Modification (KWU Quencher Installation)
The inspectors reviewed procedures, drawings, records, and observed work activities relative to the suppression pool modification as follows:
CB&I welding procedure WPS E309-83670, Rev. O, dated May 5 a.
1978. The procedure was qualified on Procedure Qualification Record 3668.
The WPS does not specify backing material to be used when making carbon steel to stainless steel welds or stainless steel to stainless steel welds. The welding procedure application table references procedure E-309 and includes a sketch showing stainless steel to stainless steel and stainless steel to carbon steel using a carbon steel backing bar.
b.
Material certifications for welding electrodes were verified.
(1)
309-15, 1/8 inch, manufactured by Chemtron, Control No.
JJJ-041, accepted by CB&I May 7, 1979.
(2)
209-16, 3/16 inch, manufactured by Stoody, Lot No. 3086720, accepted by CB&I May 7, 1979.
(3)
309-16, 5/32 inch, manufactured by Teledyne McKay, Lot No.
6918, accepted by CB&I May 8, 1979.
c.
The inspectors reviewed welder performance qualifications for three welders who were welding on the suppression prol modifi-cation at the time of the inspection.
The welder's qualifications were current, and had been verified by the CB&I site QA supervisor in May, 1979.
d.
The inspectors reviewed nondestructive examination procedure PT-5, Revision 1, " Liquid Penetrant Examination Procedure, Color Contrast, Water Washable, Wet Developer for Nuclear Component Supports," and material certifications for materials used for liquid penetrant examinations.
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Review of drawing No. R-3 for the KWU embeds shows records of
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welder identification and material location and makes identifi-cation reference to the drawing table which denotes joint identification, welding process utilized, fit up inspection, final visual inspection, liquid penetrant examination, vacuum box test, and nonconformances.
f.
Material certifications on site for the KWU quencher base plates were reviewed.
Material receipts and QA acceptance were in accordance with procedure.
NDE requirements for the ASTM A-588-77 steel plate or the embed bolts were not specified by the architect / engineer, Sargent and Lundy.
The inspectors questioned why Sargent and Lundy did not specify NDE requirement on the plate and bolts for La Salle when they had specified ultrasonic examination of plate and magentic particle examination of bolts for the same modification at other facilities and it appears that such requirements are appropriate.
This matter is unresolved.
(373/79-21-03; 374/79-15-01)
No items of noncompliance or deviations were identified in this area.
2.
Control Rod Drive Housing Alignment, Unit 1 Inspection of weld bead straightening of CRD housings records and activities indicates that 155 of a total of 185 CRD housings were at one time out of alignment. These 155 housings were brought into alignment by placing weld beads on the sides of the housings to draw the into the correct position.
The inspector determined that welding was performed using approved procedures, that the welding procedure was properly qualified in accordance with Section IX of the ASME code. Welders performing the work were properly qualified to weld to the procedure and that the welder's qualifications were verified bi-weekly per the contractor's QA manual.
NDE materials were certified and that NDE personnel were properly qualified to the level required for them to perform the examinations.
No items of noncompliance or deviations were identified in this area.
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Section IV Prepared by C. E. Jones Reviewed by C. C. Williams, Acting Chief Projects Sectitu 2 Heating, ' ventilating and Air Conditioning 1.
General Fabr_.ation and installation of the heating, ventilating and air conditioning (HVAC) system was awarded by contract to The.'.ack Company. This work is to be done at the La Salle County Station under Sargent and Lundy Sepcification No. J-2590 This specification included Addendum 2, dated September 29, 1975.
The plant HVAC system consists of several units that have been designed to provide specific requiremente. All air from potentially radioactively contaminated areas is exhausted through the station vent stack; examples include the HVAC systems for the reactor, turbine and radwaste buildings and the local exhaust hoods for the radioactive laboratories, the machine shop and the laundry.
Exhaust air from air conditioning that serves the following non-radioactive areas is not routed to the station vent stack:
Service building office and storage areas.
a.
b.
Auxiliary building office area.
c.
Lake and river screen houses.
d.
Diesel generator rooms.
e.
HVAC equipment rooms.
2.
Safety Related HVAC Systems Specification J-2590, HVAC Work, La Salle County Station, Division 1, General Requirements specifies the following systems as safety related:
a.
Control room HVAC System Identification Code (VC).
b.
Auxiliary electrical equipment room HV.\\C, System Code (VE).
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Diecel generator room ventilation system, Code (VD).
c.
d.
Reactor Building ventilation system, code (VR). The following parts of the reactor building ventilation system are safety related and the related ductwork and accessories shall be seismic:
(1) Supply air duct between and including the secondar containment isolation dampers and the duct penetration of the secondary containment isolation dampers pr.o the duct penetration of the secondary containment soundary.
(2) Exhaust air duct between and ir..iuding secondary containment isolation dampers, and the duct penetration of the secondary containment boundary.
(3) Fuel pool exhaust duct from elevation 843' to elevation 736'-6" inside the reactor building.
e.
CSCS Equipment Area Cooling System, code (VY).
f.
Switchgear rooms ventilation system, code (VX) except for the recirculation duct in the Auxiliary Building HVAC Equipment Room.
3.
Seismic Components The following components are specified to be Seismic Category 1 equipment:
a.
All dampers utilized in seismic ducts.
b.
Duct silencers used in the following HVAC systems:
(1)
Control room.
(2) Auxiliary electric equipment room.
(3) Essential switchgear heat removal.
(4) Diesel room.
c.
Grill registers and diffusers (including pressure reducing valve) utilized on seismic ducts.
d.
Duct access doors on seismic ducts.
Air filter systems listed in Table 1, page 1-22 of specification e.
J-2590.
f.
A1) components listed under (a) and (b) are active while those under (c), (d) and (e) are passive.
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(1) S&L Form 350-A, Seismic Criteria for the Design of Essential
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Equipment Installed in Nuclear Power Plants.
(2) Electrical equipment and instruments shall in addition, meet the requirements of IEEE Standard 344-1971, Draft Revision 5, Seismic Qualification of Class IE Equipment for Nuclear Power Generating Stations.
4.
Drawing Review The inspector reviewed Mechanical Drawings and P. and I.D. Drawings of the control room, electrical equipment room, auxiliary building, and reactor building to gain information of the ventilation system.
The drawings listed below were among those reviewed.
1377 Sheet 1 of 5 HVAC Equipment Room EL 786'-6" Column 6-12 1377 Sheet 2 of 5 HVAC Equipment Room EL 786'-6" Column 12-18 1377 Sheet 3 of 5 HVAC Equipment Room EL 786'-6" Column 18-24 1377 Sheet 4 of 5 HVAC EL 786'-6" Column 12-18 Duct Hangers 1377 Sheet 5 of 5 HVAC EL 786'-6" Sections Duct Hangers M1390 Sheet 1 of 2 Auxiliary Bay Vent and A/C System EL 768'-0" M1390 Sieet 2 of 2 Auxiliary Bay Vent and A/C System EL 768'-0" Duct Hangers M1391 Sheet 1 of 2 Auxiliary Bay Air Conditioning System EL 768'-0" M1391 Sheet 2 of 2 Auxiliary Bay Air Conditioning System EL 768'-0" Duct Hangers 1378 Sheet 2 of 4 HVAC 802'-0" HVAC Equipment Room Column 12-18 M1443 Sheet 1 of 4 P&ID Control Room Air Conditioning System M1443 Sheet 2 of 4 P&ID Control Room Air Conditioning System M1443 Sheet 3 of 4 P&ID Auxiliary Electrical Equipment Room's Air Conditioning System M1443 Sheet 4 of 4 P&ID Auxiliary Electrical Equipment Room's Air Conditioning System 5.
Record Review The inspector reviewed tne seismic analysis of the ductwork and hangers suomitted by Zack Company.
This analysis had been reviewed and approved by S&L Engineers. The analysis was acceptable.
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Observation of Work
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The insp_cscr observed installation of the HVAC systems for the cont oi room, Auxiliary Building, Reactor Building, and Auxiliary Electrical Equipment Rooms. The systems observed were considered to be 85%, 75%, 89% and 80% complete, respect ively.
No items of noncompliance were identified.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain wr her they are acceptable items, items of noncompliance or deviations.
Unreso.ved items disclosed during this inspection are discussed in Section II, Paragraphs 1 and 2, and in Section III, Paragraph 1.f.
Exit Interview The inspectors met with the site representatives (denoted under Persons Contacted) at the conclusion of the inspection.
The inspectors summarized the purpose and findings ofthe inspection.
The licensee acknowledged the findings reported herein.
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