IR 05000373/1981050
| ML20040H009 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 01/26/1982 |
| From: | Connaughton K, Knop R, Shepley S, Walker R, Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20040H008 | List: |
| References | |
| 50-373-81-50, NUDOCS 8202160730 | |
| Download: ML20040H009 (11) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
Report No. 50-373/81-50 Docket No. 50-373 License No. CPPR-99 Licensee: Commonwealth Edison Company P. O. Box 767
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Chicago, IL 60690 Facility Name: LaSalle County Nuclear Station, Unit 1 Inspection At: LaSalle Site, Marseilles, IL Inspection Conducted: November 16 through December 31, 1981 bb Ndh Inspectors:
R. D. Walker 14d4 he S. E. Shepley
/ N-$ A 0k $!k f
e G. C. Wright l-Ad-D M
K. A. M ton s f M/FA
/4 c 6 r Approved By:
R. C. Knop, Chief
/2 b
Reactor Projects Branch 1 Inspection Summary In_spection on November 16 through December 31, 1981 (Report No. 50-373/81-50)
Areas Inspected: Routine, resident inspection and preoperational testing.
The inspection consisted of a review of licensee action on previous findings, followup on significant events, preoperational test results evaluation, inspection of activities preparatory to license issuance, and a plant walk-through/ operational status review. The inspection involved a total of 493 inspector-hours onsite by four NRC inspectors including 102 inspector-hours q
onsite during off-shifts.
Results: Of the five areas inspected, no apparent items of noncompliance or deviations were identified.
8202160730 820127 PDR ADOCK 03000373 G
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DETAILS 1.
Persons Contacted B. B. Stephenson, LaSalle County Station Project Manager R. H. Holyoak, Station Superintendent
- R. D. Kyrouac, Quality Assurance Engineer
- G. J. Diederich, Station Operating Assistant Superintendent
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R. D. Bishop, Administrative and Support Services Assistant Superintendent C. W. Schroeder, Technical Staff Supervisor J. M. Marshall, Operating Engineer H. J. Hentschel, Assistant Technical Staff Supervisor E. E. Spitzner, Startup Coordinator J. M. Damron, Technical Staff Engineer W. C. Kirchhoff, Technical Staff Engineer W. A. Stewart, Fuel Handling Foreman M. Santic, Technical Staff Engineer W. H. Donaldson, Assistant Construction Superintendent 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 conducted at the close of the inspection period.
2.
Licensee Action On Previous Inspection Findings (Closed) Unresolved Item (373/81-00-05): Replacement of all jet pump hold down beams when available per the Safety Evaluation Report (SER),
Section 3.9.5.
The licensee has replaced these hold down beams with the new revised heat treatment jet pump hold down beams as committed to the Office of NRR in a letter dated December 4, 1981 to Mr. A. Schwencer from C. E. Sar :ent. This open item was closed by the Office of NRR based on the ;ommitment to install the revised jet pump hold beams stated above. NRC Region III is now closing the open item because of the installation.
" Closed) Unresolved Item (373/81-00-08): Section 7.2 of NUREG 0619 requires that licensees with carbon steel exhaust headers who have capped the CRD return line must; install flushing ports and revise maintenance procedures to include ilushing of the exhaust headers and cleaning of the HCU filters. LaSalle Station has capped the
CRD return line; however, the exhaust headers are stainless steel rather than carbon steel. Therefore, it is concluded that flushing
ports and applicable maintenance procedures are not required. This item is considered c1csed.
(Closed) Unresolved Item (373/81-00-14): Development of an Inplant Main Steam Safety / Relief Valve Test to establish the difference between local and bulk pool temperature and to demonstrate that a-2-
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maximum low pool temperature specification of 200* F will not be exceeded per SER 6.2.1.1.
The inspector determined that this test will be included in the Inplant Main Steam Safety / Relief Valve Tests that will be developed to confirm adequacy of loads per SER 3.8.1 which is NRC Region III Open Item (373/81-00-02). The inspector will follow all of the concerns associated with Inplant Main Steam Safety / Relief Valve Testing under the (373/81-00-02) Open Item Number.
(Closed) Unresolved Item (81-00-44): The inspector reviewed drafts of the following procedures:
1.
LOA-AP-03'
2.
LOA-AP-05
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3.
LOA-AP-07 4.
LOA-AP-08 l
The inspector's concerns, developed during a previous review, deal-l ing with cross-tie and bus stripping procedures for the 125/250 VDC Battery Chargers and the 250 VDC buses, have been adequately addressed.
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I This item is considered closed.
(Closed) Items of Noncompliance (373/81-30-10) and (373/81-36-03):
(373/81-30-10) was written because Secondary Containment Leak Testing was conducted without using procedures.
(373/81-36-03) was written subsequent to (373/81-30-10) because Secondary Containment Leak Testing was subsequently perforced using a procedure, but the pro-cedure used was not properly reviewed and approved. The inspector verified by record review, observation and discussions with licensee personnel the following information relating to followup on the items of noncompliance:
The licensee management forwarded copies of reply to appropriate a.
onsite representatives.
b.
That recponsibility has been assigned for effecting the described corrective action.
That the licensee responded in a timely manner.
c.
d.
That the items (s) of noncompliance was reviewed as required by approved administrative procedure or Quality Assurance p rogram.
e.
That the corrective measures taken for each of t'ae identified items of noncompliance were reviewed by appropriate licensee c
personnel and that the results were as described in the reply.
f.
That the corrective measures taken to avoid further items of noncompliance were effected within the time period described in the reply.
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g.
That other licensee commitments discussed in the reply were also completed.
h.
That the licensee posted copies of enforcement correspondence as required by 10 CFR 19.11.
(Closed) Unresolved Item (373/81-00-26): The licensee must provide redundant chlorine and ammonia detectors that meet the sensitivity requirement of Regulatory Guide 1.95 per SER 6.4.2.
The inspector has determined that the detectors are iristalled and will be calibrated by procedures and to the sensitivity specifications submitted to the Office of NRR in a letter dated November 4, 1981 to A. Schwencer from C. E. Sargent. The inspector discussed with Mr. A. Bournia, the Office of NRR, Licensing Project Manager, the acceptability of the November 4, 1981 submital and was informed that it was accepted by the Office of NRR. This item is closed based on the Office of NRR acceptance.
(Closed) Unresolved Item (373/81-30-07): The inspcetor referred his concerns with the core spray pattern to the Office of NRR. The licensee and his vendor met with the Office of NRR and subsequently submitted to the Office of NRR in a letter dated December 7, 1981 to R. L. Tedesco from C. E. Sargent, a justification for accepting the Core Spray Pattern Tests. The inspector was informed by Mr. A. Bournia, the Office of NRR, Licensing Project Manager, that the Office of NRR has accepted this submittal and this item is closed.
(Closed) Unresolved Item (373/81-36-02): The licensee had not pro-vided a clear containment vent path for emergency venting at elevated containment pressures in Procedure LOA-VP-03 " Emergency Primary Con-tainment Relief." The inspector reviewed Revision 1 of this procedure and found that this vent path has been clearly identified in this revision.
(Closed) Unresolved Item (373/81-36-04): The inspector had concerns with the adequacy of the Temporary Turnover Procedure found in Pro-cedure LSU-100-2 " Construction-Operating Turnovers and Releases."
The inspector reviewed Revision 11, dated December 15, 1981 of this procedure and found his concerns were adequately addressed.
(Closed) Unresolved Item (373/80-30-06):
When reviewing the Preopera-tional Tests; PT-LP-101, PT-HP-101, PT-RH-101, and PT-RI-101, the inspector found that the procedures did not assure that certain valves were tested to assure that they would open with design differential pressures across them as called for in the vendor design specifica-tions. The review of the results of these preoperational tests by the inspector has assured him that the differential pressure tests q
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were incorporated and testing was performed in the preoperational tests on these valves, except for PT-RI-101 valves. The PT-RI-101 valve testing has been incorporated into a apecial test procedure to be performed. The inspector is closing this item based on the above.
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(Closed) Unresolved Item (373/81-15-10): There were no procedural instructions for venting and aligning system instrumentation during system filling and venting. The inspector found that a new Procedure-LIP-GM-29 " Instrument Valve Position Checkoff" provides the alignment
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procedure for this operation and that requirement for performing the venting of the instrumentation via LIP-GM-29 has bean placed in the various system filling, venting and draining procedures. This item is closed.
(Closed) Unresolved Item (373/81-00-15): Section 6.2.1.1 of the SER required that the licensee provide the following items:
Commonwealth Edison Company must substantiate the following items for containment:
Procedures to manually actuate wet well spray after 30 psig is a.
reached in the drywell.
b.
Perform a high pressure bypass leakage test.
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Establish acceptance criteria for the high pressure bypass leakage c.
test to be the measured leakage less than 10% of capability.
d.
Provide redundant. position indicators on all vacuum breakers with indication and redundant alarms in the control room.
Establish surveillance procedures to test the vacuum breakers e.
at monthly intervals.
The inspector has reviewed the procedures for requirements a. and e., determined that the switches and indications in requirement d.
has been provided, determined that items b. and c. have_been per-formed and documented in a letter to the Office of NRR dated December 16, 1981 to A. Schwencer from C. Sargent, and has deter--
mined from A. Bournia, the Office of NRR, Project Manager, that the Office of NRR finds the High Pressure Bypass Leakage Test per-formed by the licensee to be acceptable based on the information in the December 16, 1981 submittal. This item is closed based on this information.
(Closed) Unresolved Item (373/79-33-01): Amendment 57 to the FSAR changed the requirement on Replacement Training from actually start-ing up and shuting down the unit to five reactivity changes which may be performed on the LaSalle simulator when completed. NRR has accepted'the amendment; thus we have no further concerns in this area.
l (Closed) Unresolved Item (373/79-44-08): The inspector reviewed draft Procedure LES-MS-101 pertaining to Main Steam Isolation Valve Limit Switch Set Point Verification. The inspector's concerns, developed during a previous review of the item, have been adequately addressed in the latest draft. This item is considered closed.
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(Closed) Unresolved Item (373/81-00-07): The licensee was required to submit a response to NRC concern for achieving the required flow rate (180 gallons per minute) compared to the actual measured flow rate (130-gallons per minute) when the Control Rod Drive System is used as an emergency high pressure water source to the core. The licensee submitted this response to the Office of NRR via a letter
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dated December 8, 1981 to R. L. Tedesco from C. E. Sargent. The Office of NRR, Licensing Project Manager, Mr. A. Bournia, has in-formed the inspector that the Office of NRR has accepted the li-censee's response in the December 8,1981 letter as being adequate.
(Closed) Open' Items (373/81-00-17) and (373/81-00-20):
SER ISI con-cerns in Sections 6.2.3.3 and 6.2.5.1.
The inspector reviewed the applicant's Inservice Testing Program for pumps and valves to verify that valves serving as isolation barriers in the Reactor Building, Closed Cooling Water and Post LOCA Combustible Gas Control Systems
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were included and that leak rate testing was to be performed in accordance with Section XI of the A.S.M.E. Boiler and Pressure Vesse' Code, The inspector determined that the applicant's Inservice Test Program, given interim NRC approval pending review, included a request to exempt these valves from the leak testing requirements
of Section XI of the A.S.M.E. Boiler and Pressure Vessel Code. The exemption request proposed that the valves be leak tested in accord-ance with 10 CFR 50, Appendix J as an alternative. Discussions with the NRC reviewers responsible for the Inservice Test Program, Reactor Building Closed Cooling Water Systems, and the Post LOCA, Combustible a
Gas Control Systems revealed that the commitment to perform Appendix J leak rate testing was an acceptable alternative on an interim basis and that a final determination would be made as part of the NRC's Inservice Test Program review.
(Closed) Unresolved Items (373/81-06-04), (373/79-33-09), and (373/79-33-14): ' Closure of IE Circulars No. 81-01, 79-12, and 78-04 respectively. The inspector determined for each of these circulars that:
The circular was received by licensee management.
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a.
b.
That a review for applicability was performed.
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For circulars that were applicable to the facility, appropriate c.
corrective actions have been taken or are scheduled to be taken.
(Closed) Unresolved Item (373/79-44-07): Closure of IE Bulletin 79-27.
This bulletin was sent to the licensee for information only. The q
inspector determined that the licensee took the following action with respect to this bulletin:
The bulletin was received by licensee management.
j a.
b.
A review for applicability was performed.
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The licensee has taken appropriate corrective actions.
c.
(0 pen) Unresolved Item (373/79-33-03): The inspector reviewed the information submitted by the licensee pertaining to IE Circular 79-04. The information did not cover the items to be addressed in Circular 79-04.
This item remains open.
(Open) Unresolved Item (373/80-30-03): The inspector reviewed licensee procedures and determined that one item out of the three applicable open items, pertaining to I.B.Bulletin 80-17, could be closed. The remaining two items have been discussed with the licensee.
This item remains open.
(0 pen) Unresolved Item (373/81-30-03): The inspector reviewed Pro-cedure LOP-RH-07 on the operation of the shutdown cooling mode of the Residual Heat Removal System. For the purposes of IE Circular 81-11, the inspector determined that the procedure -did not ' provide
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sufficient information to preclude the type of event described in i
the circular. This item remains open.
(0 pen) Unresolved Item (373/81-00-22): The inspector reviewed Pro-cedures LTS 900 - 6, 7, 8, 9, 10, 11 and 12.
After discussions with the licensee, the Procedures LTS 900-9, 11 and 12 are being revised.
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This item remains open.
l (0 pen) Unresolved Item (373/81-00-25): The inspector was unable to obtain the procedure referenced by the licensee. This item remains l
open.
(0 pen) Unresolved Item (373/81-00-27): The inspector reviewed
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letters of December 19, 1980 and June 24, 1981 from Mr. W. G. Schwartz
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(Sargent & Lundy) to Mr. T. E. Watts (Commonwealth Edison Company).
l The inspector was unable to correlate the information provided in
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the letters with the drawings reference in the same letters. Clari-fication by the licensee has been requested. This item remains open.
(0 pen) Unresolved Item (373/81-00-47): The inspector reviewed the
licensee procedures pertaining to lifting and moving of heavy loads.
The licensee is presently revising the procedures to address safe l
load paths and crane inspections.
This item remains open.
No items of noncompliance were identified in this area.
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3.
Tagout Procedure Problems There were two incidents involving equipment tagouts during this inspec-tion period:
A sensing line boundary valve was open when it was tagged shut during a.
a construction hydro. This resulted in the spraying of water on some workers in the reactor vessel.
b.
A valve in the cooling water line-up to the LPCS pump was closed when it was tagged open. This resulted in the LPCS pump running without cooling water, which contributed to the running of the LPCS pump while temperatures were above the alarm limits. The LPCS pump has since been inspected for damage.
Both of these incidents require further investigation to determine if procedures were violated and are carried as Unresolved Item #
(373/81-50-01).
No items of nonecmpliance were identified in this area.
4.
Lifted Lead Documentation Problem LPCS pump temperature thermocouple leads appear to have been determin-ated without any authorizing documentation and without operations know-ledge. This contributed to the LPCS pump being run while temperatures were above alarm limits.
This incident requires further investigation to determine if procedures were violated and is carried as Unresolved Item #(373/81-50-02).
No items of noncompliance were identified in this area.
5.
Control Rod Blade Guide Problem During this inspection period, the licensee discovered that a control
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rod blade guide was apparently incorrectly seated such that the control rod blade was not inside the guide, but was riding outside the blade guide. This resulted in damage to the control rod blade.
This incident required further investigation to determine if procedures were violated and is carried as Unresolved Item #(373/81-50-03)
No items of noncompliance were identified in this area.
6.
Technical Specification Review
The inspector reviewed the Proof and Review version of the LSCS Technical Specification for clarity and enforceability, and trans-mitted all applicable comments to appropriate people.
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The inspector also attended announced NRR/ licensee meetings and ensured gene al acceptability of negotiated changes.
No items of noncompliance were identified in this area.
7.
Pre-Operational Test Results Evaluation The inspector reviewed the test results of the Residual Heat Removal System (RHR). The review included test changes, deficiencies, summary and evaluation, and verification that test results have been approved.
The inspector determined that test changes, and the summary and I
evaluation portions of the test, conducted by the station were in
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conformance with the applicable regulations and commitments.
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The review, while essentially done, will not be completed until the licensee finishes their review of this test.
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No items of noncompliance were identified in this area.
l 8.
Inspection Activities Preparatory to License Issuance (Status of I
Licensee Procedures and Preoperational Testing Program)
Operating, Maintenance, Surveillance, Abnormal and Emergency I
a.
Procedure Status
The licensee and NRC have effectively completed their review of these procedures.
b.
Pre-Operational Testing Program Status
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l The licensee has a total of 99 Preoperational Tests / Systems l
Demonstrations required by the FSAR for Unit I fuel load or low power operations of which 89 are specific to Unit 1 and the re-maining 10 are specific to Unit 2.
The licensee reported that 99 of these systems have been turned over for preoperational testing, that 98 of these Preoperational Tests and Systems Demonstrations have been started, that 76 Preoperational Tests i
and Systems Denonstrations have been completed, and the program i
is 96% complete at this time. The licensee stated that final Preoperational Test or System Demonstration results for 50 tests of the 98 required by the NRC are ready for NRC review, i.e.,
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the entire test is complete and the results have been reviewed and accepted by the licensee. These 50 tests are:
f PT-AP-101, " Unit 1 AC Distribution" PT-AR-101, " Area Radiation Monitoring Equipment"
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SD-CX-102, " Rod Worth Minimizer" PT-DO-101, " Unit 1 Diesel Oil System" PT-FC-101, " Fuel Pool Cooling System" SD-FC-101, " Fuel Pool Cooling System"
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PT-HC-101,
" Reactor Building Crane" j
PT-HP-101,
"High Pressure Core Spray System" PT-LD-101,
" Leak Detection System" PT-LP-101, " Low Pressure Core Spray System" PT-NB-101, " Nuclear Boiler" PT-NR-101A, " Source Range Monitor" PT-NR-101B, " Intermediate Range Monitor" PT-NR-1010, " Power Range Neutron Monitors" SD-PS-101, " Process Sampling System" PT-PV-101, " Reactor Vessel Internals Vibration Monitoring" PT-RD-101A, " Rod Drive Control and Rod Position Indication System" PT-RD-102,
" Control Rod Drive Hydraulic" PT-RI-101,
" Reactor Core Isolation Cooling System" SD-SA-101,
" Service and Instrument Air System" PT-SC-101,
" Standby Liquid Control System" PT-VD-101,
" Diesel Generator Ventilation System" PT-VJ-101,
" Machine Shop Heating, Ventilation, and Air Conditioning System" PT-VL-101,
" Laboratory, Heating, Ventilation, and Air Ccaditioning System" PT-V0-101,
"Off Gas Filter Building Heating, Ventilation, and Air Conditioning System" PT-VP-101,
" Primary Containment Vent and Purge System" PT-VP-104, " Primary Containment Chilled Water System" PT-VY-102,
" Core Standby Cooling System Equipment Ventilation" SD-WR-101,
" Reactor Building Closed Cooling Water System" SD-WS-101,
" Service Water System" SD-WX-101,
" Solid Radwaste System" SD-CD-101,
" Condensate and Condensate Booster Syctem" SD-CD-102, " Condenser and Auxiliary Equipment System" SD-CW-101,
" Circulating Water and Auxiliary Equipment System" SD-CY-101, " Cycled Condensate System" SD-EH-101A, " Turbine EHC" SD-EH-101B, " Turbine Supervisory Panel" SD-FW-101,
" Reactor Feedwater" SD-FW-102, "Feedwater Control System" SD-HD-101A, " Heater Drains" SD-HD-101B, " Moisture Separator / Reheater" SD-WE-101A, " Waste Collector" SD-WE-101C, " Laundry Equipment and Floor Drain Reprocessing and Disposal System" SD-WE-101E, " Equipment Floor Drains" PT-AP-201,
" Unit 2 AC Distribution" PT-AP-202,
" Unit 2 DC Distribution" PT-DO-201, " Unit 2 Diesel Oil System" PT-VD-201, " Unit 2 Diesel Generator Ventilation System" PT-VP-202, " Unit 2 Post LOCA Hydrogen Control System" PT-VY-201, " Unit 2 Ccre Standby Cooling System Equipment Cooling"
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c.
Deficiency Status The licensee is currently listing 883 Station Operations deficiencies and 2060 Station Construction deficiencies as outstanding items on the 98 Preoperational Tests / System Demonstrations required by the licensee. The licensee has segregated these deficiencies into those that will impact fuel load and those that will not. The licensee has reviewed approximately 2893 of these deficiencies for segregation and preliminary assessment is that 962 of those reviewed would need to be cleared prior to fuel load. The inspector will continue to review this matter.
No items of noncompliance were identified in this area.
9.
Plant Walkthrough/ Operational Status Review The inspector conducted walkthroughs and reviewed the plant opera-tions status including examinations of control room log books, routine patrol sheets, shift engineers log books, equipment outage logs, special operating orders, and jumper tagout logs for the period of November 16, 1981 through December 31, 1981. The inspector observed the operations status during three off-shifts during the same period as above. The inspector also made visual observations of the routine surveillance, functional, and preoperational tests in progress during this period. This review was conducted to verify that facility operations were in conformance with the requirements established under 10 CFR and administrative procedures. The inspector observed shift turnovers to verify that plant component status and problem areas were being turned over to a relieving shift. The inspector conducted tours of Unit I and 2 reacter, auxiliary, and turbine buildings throughout the period and noted the status of construction and plant housekeeping / cleanliness. With respect to housekeeping / cleanliness, the inspector found conditions tc Se adequate during this inspection period.
No items of noncompliance were identified in this area.
10.
Unresolved Items Unresolved Items are matters about which more information is required in order to ascertain whether they are acceptable Items, Items of Noncompliance, or Deviations. Unresolved Items disclosed during the inspection are discussed in Paragraphs 3, 4 and 5.
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11.
Management Interview The inspector met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection period. The inspector summarized the scope and findings of the inspection activities.
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