IR 05000373/1981010
| ML20008F803 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 03/30/1981 |
| From: | Reimann F, Shepley S, Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20008F802 | List: |
| References | |
| 50-373-81-10, NUDOCS 8105120080 | |
| Download: ML20008F803 (8) | |
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U.S. NUCLEAR REGULATORY COMMISSION j}
OFFICE OF INSPECTION AND ENFORCEMENT v
REGION III
Report No. 50-373/81-10 Docket No. 50-373 License No. CPPR-99 Licensee:
Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name:
LaSalle County Nuclear Station, Unit 1 Inspection At:
LaSalle Site, Marseilles, IL Inspection Co ucted: February 9 through March 6, 1981
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Inspectors:
R. D.
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F. W. Reimann, Acting Chief Reactor Projects Section 1C Inspection Summary Inspection on February 9, through March 6,1981 (Report No. 50-373/81-10)
Areas Inspected: Routine, resident inspector, preoperational inspection consisting of a review of licensee action on previous inspection findings, IE Bulletins and Circulars received by the licensee since last inspection, proposed licensee technical specifications, licensee training provided to meet NUREG 0737 requirements, inspection activities preparatory to license issuance, and a plant walkthrough/ operational status review. The inspection involved a total of 107 inspector-hours onsite by two NRC inspectors includ-ing 24 inspector-hours onsite during off-shifts.
Results:
No items of noncompliance were identified.
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8105120080
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- 4 DETAILS 1.
Persons Contacted B. B. Stephenson, LaSalle County Station Project Manager
- R. H. Holyoak, Station Superintendent R. D. Kyrouc, Quality Assurance Engineer
- G. J. Diederich, Station Operating Assistant Superintendent
- R. D. Bishop, Administrative and Support Services Assistant Superintendent C. W. Schroeder, Technical Staff Supervisor R. Raguse, Senior Operating Engineer J. M. Marshall, Operating Engineer
- W. Huntington, Assistant Technical Staff Supervisor H. J. Hentschel, Assistant Technical Staff Supervisor F. Lawless, Rad-Chem Supervisor
- E. E. Spitzner, Startup Coordinator
- E. Stevak, Quality Assurance L. W. Duchek, Project Management Staff J. Bowers, Onsite Nuclear Safety Engineering Group (ONSEG)
T. Borzym, Security Administrator The inspector also interviewed other licensee employees including members of the Technical, operating, and construction staff, as well as certain licensee contractor employees.
- Denotes persons present at management interview onsite.
2.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (373/79-15-01): Minor problems with operating procedure LOP-RT-01E, " Reactor Water Cleanup System Electrical Checklist."
The inspector reviewed Revision 2, dated January 1, 1981, of this pro-cedure and found it satisfactory.
(Closed) Unresolved Item (373/79-15-02):
Minor problems with operating procedure LOP-RT-01M, " Reactor Water Cleanup System Mechanical Checklist."
The inspector reviewed Revirion 1, dated January 1,1981, of this pro-cedure and found it satisfactory.
(Closed) Unresolved Item (373/79-15-03):
Minor problems with operating procedure LOP-RT-05, " Reactor Water Cleanup System Filter /Demineralizer backwash." The inspector reviewed Revision 1, dated February 6, 1981, of the procedure and found it satisfactory.
(Closed) Unresolved Item (373/79-15-04): Minor problems with operating procedure LOP-RT-02, " Reactor Water Cleanup System Startup." The inspector reviewed Revision 2, dated February 3, 1981 of this procedure and found it satisfactory.
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(Closed): Unresolved Item (373/79-15-16): Minor problems with operating-procedure LOP-HP-01, " Filling and Venting the High Pressure Core Spray System." The inspector reviewed Revision 3, dated May 1, 1980, of the proceo re and found it satisfactory.
(Closed) Unresolved Item (373/79-15-17): Minor problems with operating procedure LOP-RI-01E, " Reactor Core Isolation Cooling System Electrical Checklist." The inspector reviewed Revision 3, dated December 10, 1980, of the procedure and found it satisfactory.
(Closed) Unresolved Item (373/79-15-18): Minor problems with operating
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procedure LOP-RI-01M, " Reactor Core Isolation Cooling System Mechanical Checklist." The inspector reviewed Revision 1, dated December 10, 1980 of this procedure and found it satisfactory.
(Closeo) Unresolved Item (373/79-15-21):. Minor problems with operating procedure LOP-RI-02, " Starting and Operation of the Reactor Core Isolation Cooling System." The inspector reviewed Revision 2, dated January 14, 1981, of this procedure and found it satisfactory.
(Closed) Unresolved Item (373/79-15-20): Minor problems with operating
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procedute LOP-RI-04, " Turbine Trip Recovery and Turbine Reset Reactor Core Isolation Cooling System." The inspector reviewed Revision 2, dated January 13, 1981, of the procedure and found it satisfactory.
(Closed) Unresolved Item (373/79-15-19): Minor problems with operating procedure LOP-RI-05, " Preparation.for Standby Operation of the Reactor Core Isolation Cooling System." The inspector reviewed Revision 2, dated January 13, 1981, of this procedure and found it satisfactory.
(Closed) Unresolved Item (373/79-15-24): Minor problems with operating procedure LOP-LP-02, " Preparation for Standby Operation of the Low Pressure Core Spray System." The inspector reviewed Revision 3, dated December 15, 1980, of this procedure and found it satisfactory.
(Closed) Unresolved Item (373/79-15-23): Minor problems with operating procedure LOP-LP-01M, " Low Pressure Core Spray System Mechanical Check-list."
The inspector reviewed Revision 3, dated January 1, 1981, of this procedure and found it satisfactory.
(Closed) Unresolved Item (373/80-05-09): The inspector had concerns for cleanliness during channeling of fuel and for subsequent storage of channeled fuel. The licensee has completed channeling fuel and has stored the channeled fuel in the Unit No. 2 Spent Fuel Storage Pool under adequate cleanliness conditions. This item is closed.
(Closed) Unresolved Item (373/80-37-02): Review of IE Circular 80-16.
The inspector determined that the licensee management received this
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IE Circular, that a review for applicability was performed, and the circular was not applicable to the licensee so no corrective action was taken or is scheduled.
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k (Closed) Unresolved Item i373/80-16-05): Review of IE Circular 80-12.
The inspector determined that the licensee management received this
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IE Circular, that a review for applicability was performed which established that the circular was not applicable to the licensee'
safety related components and therefore, no corrective action was taken or scheduled.
(Closed) Unresolved Item (373/79-33-19): Review of IE Circular 78-16.
The inspector determined that the licensee management received this IE Circular, that a review for applicability was performed, and that-the licensee's corrective action was adequate.
(Closed) Unresolved Item (373/79-38-18): Review.of IE Circular 77-16.
The inspector determined that the licensee management received this IE Circular that a revicw for applicability was performed, and that the licensee's corrective action was adequate.
(Closed) Unresolved Item (373/80-30-04): Review of IE Bulletin 80-16.
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The inspector determined that for this IE Bulletin, the licensee man-agement forwarded copies of the written response to appropriate onsite management representatives, the written response included the infor-mation required to be reported, the written response included corrective action commitments based on information presented in the bulletin and the licensee's response, and information discussed in the licensee's response was accurate.
(Closed) Unresolved Item (373/80-56-04): Review of IE Bulletin 80-23.
The inspector determined that for this IE Bulletin, the licensee management forwarded copies of this written response to appropriate onsite management representatives, the written response was within the time period stated in the bulletin, the written response included corrective action commitments based on information presented in the bulletin and the licensee's response, and information discussed in the licensee's response was accurate.
(Closed) Unre;olved Item (373/79-15-27): Review of IE Bulletin 78-14.
The inspector determined that the licensee management received this IE Bulletin, that a review for applicability was performed, and that I
the licensee's corrective action was adequate.
(Closed) Unresolved Item (373/80-16-07): Annunciator windows on control room alarm panels improperly engraved and dynotape used for correction. The inspector has determined that these annunciator windows have been properly engraved and that the procedure for " Conduct of Operations" LAP 1600-2, Revision 13, dated October 7, 1980 carries specific requirements for minimizing the use of dynotape on control room annunciator panels. This item is closed.
(Closed) Unresolved Item (373/80-16-06): Minor technical faults in certain Emergency / Abnormal procedures (LOA's) for Control Room Panel
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1-H13-P603. Recent revisions to these procedures corrected these~
technical faults. This item is closed.
(Closed) Unresolved Item (373/80-05-12):
Concern for diesel genera-tor load shedding circuitry when buses are in test. This item has been referred to the Office of NRR for resolution via inspection report 50-373/81-06. The resolution of this item is being tracked via Open Item Number (373/81-06-13) and therefore, Open Item Number (373/80-05-12) is closed.
(Closedi Unresolved Items (373/80-43-06, 07, 08): Resolution of Onsitt dafety Review Function requirements at LSCS. -Through dis-cussions with the licensee and NRR, the inspector has determined that when currently proposed changes to LSCS administrative pro-cedures are completed and implemented, the LSCS Onsite Safety Review Function will be in compliance with all requirements anticipated to be made applicable to LSCS.
Pending the implementation of these procedure changes', this issue wi.1 be given Open Item (373/81-10-01).
No items of noncompliance were identified in this area.
3.
Review of IE Circulars Received Since Last Inspection Report The licensee has received IE Circulars 81-02 and 81-03 since the last inspection report written by the inspector. The licensee is still reviewing these circulars at this time, and the inspector will review the licensees' responses during a subsequent inspection under Open Item Numbers (373/81-10-02) and (373/81-10-03) for IE Circulars 81-02 and 81-03 respectively.
No items of noncompliance were identified in this area.
4.
Review of Proposed Facility Technical Specifications The licensee has issued a complete new revision of the proposed facility Technical Specifications and the inspector is currently reviewing that docmnent as well as recent changes to the Technical Specifications issued -
by the Office of NRR. The inspector will attend a Technical Specifications meeting with the licensee during the next inspection period.
5.
Licensee Training to Meet NUREG 0737 Requirements The inspector audited a portion of the licensee's training program that was designed to incorporate training concerns for Operators, Senior Operators, and Shift Technical Advisors expressed in NUREG 0737 TMI TASK ACTION PLAN Item I.A.I.2 and I.A.2.1.
Specifically, this training was conducted to give the attendees information with respect to Reactor Vessel Instrumentation such that the attendee would:
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Know which control room instrumentation is used to monitor reactor vessel conditions.
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Be able to describe the detection and operating principle of these instruments.
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Know the function and setpoint of these instruments.
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Know the instrument setpoint bases.
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Know the indication ranges and calibration conditions of these instruments.
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Be able to describe the effect of changes in plant operating conditions on the level instruments.
g.
Be able to calculate indicated level for any plant condition.
The inspector also reviewed training records and interviewed personnel who are to be assigned as Shift Control Room Engineers'or Shift Technical Advisors and found that they had attended or are acheduled to attend a forty hours course at the Illinois Institute of Technology on Electcical Engineering and Instrumentation and Control Theory.
These training programs meet the licensee's commitments for training in the area of instrumentation and control provided to meet the
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requirements of the NUREG 0737 Task Action Items.
No items of noncompliance were identified in this area.
6.
Inspection Activities Preparatory to License Issuance (Status of Licensee Procedures and Preoperational Testing Program a.
Operating, Maintenance, Surveillance, Abnormal and Emergency Procedure Status The licensee currently has approved for use approximately 90% of these procedures, 8% of these procedures have been drafted but not reviewed, and 2% of these procedures remain to be drafted.
b.
Preoperational Testing Program Status The licensee projects a total of 125 Preoperational Tests / System Demonstrations required for Unit 1 operations of which 115 of these are specific to Unit I and the remaining 10 are specific to Unit 2.
The licensee reported that 122 systems have been turned over for preoperational testing, that 115 Preoperational Tests and Systems Demonstrations have been started, that 68 Preoperational Tests and System Demonstrations have been completed, and the preoperational testing program is approximately 80% complete at this time. The licensee stated that final Preoperational Test or System Demonstra-tion results for 24 tests are ready for NRC review, i.e.,
the entire test is complete and the results have been reviewed and accepted-6-
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by the licensee. These twenty-four tests are PT-DO-101 " Diesel Oil,"
PT-VY-102 "LSCS Equipment Ventilation,".PT-PV-101 " Reactor Vessel Internals Vibration," PT-DO-201 " Unit 2 Diesel Oil," PT-FC-101'" Fuel Pool Cooling And Cleanup," PT-NR-101A " Source Range Monitors,"
PT-SC-101 "Staadby Liquid Control," PT-VJ-101 " Machine Shop Ventila-tion," PT-VG-101 "Off Gas Ventilation," SD-WR-101 " Reactor Building Closed Cooling Water System," SD-CW-01 " Circulating Water System,"
SD-CX-102 " Rod Worth Minimizer," PT-AP-202 " Unit No. 2 DC Distri-bution," SD-CD-101 " Condensate and Condensate Booster System,"
SD-HD-101A "Feedwater Heaters and Drains," SD-CY-101 " Cycled Condensate System," SD-WE-101A " Equipment Drain and Waste Collector Process System," PT-AR-101 " Area Radiation Monitors," PT-NR-101C
"Powcr Range Neutron Monitors," PT-NR-101B " Intermediate Range Neutron Monitors," PT-RD-101A " Rod Drive Control," PT-VD-101 " Diesel Ventilation, SD-WS-101 " Service Water," and SD-EH-101B " Turbine Supervisory.
c.
Deficiency Status The licensee is currently listing 1707 Station Operations deficienc-ies and 3687 Station Construction deficiencies as outstanding items.
The licensee is stil.1 attempting to segregate these deficiencies into those that will impact feel load and those that will not.
The licensee has reviewed approximately 2120 of these deficiencies for-segregation and preliminary assessment is that 791 of those reviewed would need to be cleared prior to fuel load. The inspector expressed'
concern that the segregation of these deficiencies'into those that will effect fuel load versus those that will not is_ progressing slowly. The inspector will continue to review this matter.
No items of noncompliance were identified in this area.
7.
Plant Walkthrough/ Operational Status Review The inspector conducted walkthroughs and reviewed the plar.t operations status including examinations of control room log books, routine patrol i
sheets, shift engineers log books, equipment outage logs, special operating orders, and jumper tagout logs for the period of February 9, j
1981 through March 6, 1981. The inspector observed the operations
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status during three off-shifts during the same period as above. The inspector also made visual observations of the routine surveillance,
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l functional, and preoperational tests in progress during this period.
l This review was conducted to verify that facility operations were in L
conformance with the requirements established under 10 CFR and
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administrative procedures. The inspector conducted tours of Units 1 l
and -2 reactor, auxiliary, and turbine buildings throughout the period
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and noted the status of construction and plant hosuekeeping/ cleanliness.
With respect to hous3 keeping / cleanliness, the inspector noted that conditions of general cleanliness have improved throughout the facility, however, conditions still need to be improved. The Station Project
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Manager acknowledged the inspector's concern and stated that a new-housekeeping procedure has been implemented that he feels will taxe care of any concerns in this area. The inspecter observed shift turnovers to verify _that plant component status and problem areas were being turned over to a relieving shift.
No items of noncompliance were identified in this area.
8.
Managemen+ Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection pe.tod. The inspector summarized.
the scope and findings of the inspection activities.
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