IR 05000373/1981015
| ML20009B344 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 06/16/1981 |
| From: | Lanksbury R, Reimann F, Shepley S, Walker R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20009B343 | List: |
| References | |
| 50-373-81-15, NUDOCS 8107150302 | |
| Download: ML20009B344 (17) | |
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U.S. NUCLEAR REGULAiORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No.
50-373/81-15 Docket No.
50-373, License No.
CPPR-99 Licensee:
Commonwealth Edison Company'
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P. O. Box 767
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Chicago, IL 60690
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Facility Name: LaSalle County Nuclear Station, Unit 1
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Inspection At: LaSalle Site, Marseilles, IL Inspection Conducted: March 9 through April 17, 1981 hk Y
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Inspectors:
R. D. Walker 6<cx1 3s ) 913 l
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nn, Act ing Chief Approved By:
Reactor Projects Section 1C
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Inspection Summary
Inspection on March 9, through April 17, 1981 (Report No. 50-373/81-15)
Areas Inspected:
Routine, resident inspector, preoperational inspection consisting of a review of licenste action on previous inspection findings, IE Bulletins and Circulars received by the licensee since last inspection, operating procedures, SER items requiring Office of Inspection and Enforcement followups, participation in the ACRS meetings, inspection activities preparatory to license issuance, and a plant walkthrougb/cperational status review. The inspection involved a total of 277 inspector-hours onsite by three inspectors including 33 inspector-hours onsite during off-shifts.
l Results: No items of noncompliance were identified.
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8107150302 810617 PDR ADOCK 05000373 O
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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 Sup trintendent 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, Proj ect Management Staff J. Bowers, Onsite Nuclear Safety Engineering Group (ONSEG)
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T. Borzym, Security Administrator
- E. Boyd, Master Mechanic
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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.
j 2.
License Action on Previous Inspection Findings (Closed) Unresolved Item (373/80-14-03): The inspector needed NRR interpretation of proposed Technical Specification 3.8.1'.1, item a, requiring two physically independent circuits between the offsite transmission net-work and the onsite class 1E distribution system.
The inspector noted this requirement is not met with current design for ESF Division III.
The inspector has reviewed the most recent revision
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to the proposed Technical Specifications dated April 16, 1981, and fcund that in the Bases for this Technical Specification, it clearly explains the requirement within the Technical Specification such that the requirement only applies to ESF Divisions I and II.
(Closed) Unresolved Item (373/80-05-11): FSAR states that the MCPR Safety Limit of 1.06 would be exceeded in the Abnormal Events of Turbine Trip or Load Reject without bypass valves in the event that the reactor was operating on the steady state MCPR LCO at maximum power.
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This item has been an SER open item, however; part 4.4 of the SER
" Thermal Hydraulic Design" explains thac these Abnormal Events have been reanalyzed using the NRR approved ODYN computer code instead of the REDY computer code and that these Abnormal Events no longer predict that the MCPR Safety Limit will be exceeded.
- (Closed) Unresolved Item (373/80-16-10): A floor plate was dropped on the fuel racks in the Unit #1 spent fuel pit causing minor surface damage. The damage was subsequently repaired P.d the racks were tested to assure a fuel bundle would fit in them properly.
No structural damage occurred in this event.
(Closed) Unresolved Item (37.3/80-41-06):
The Of fice of NRR had not accepted the licensee's position with rrspect to using the Station Control s
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Room Engineer (SCRE) as the Senior Reactor Operator in the Control Room at the time of inspection report 50-373/80-41. The Office of NRR has subsequently accepted this position in the SER, Section 22 under Item I.A.1.1.
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(Closed) Unresolved Item (373/.80-41-07): The licensee was required to submit to the Office of NRR a schedule for training the initial and replacement shift crew personnel.
The licensee subsequently submitted
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the required schedule in Amendment 54 to the FSAR and the Office of NRR has reviewed this submittal and accepted in the SER, Section 22 under Item I.A.1.3. that the licensee has adequate SRO and RO exam candidates
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to provide the required licensed operators for two units.
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(Closed) Unresolved Item (373/80-41-08):
The licensee was-informed during inspection 50-373/80-41 that the NRC intended to considet the subject of shif t crew concept.
The Of fice of NRR in the SER, Section 22 under Item I.A.1.3. stated that the licensee had subsequently informed them that it would implement the shif t crew concept on Unit' 1 for a year to assess its merits.
The licensee expects that this commitment will provide information against which existing experience on other operating nuclear facilities with shif t preference concepts can be compared. The Office of NRR states that such a comparison would assist them in evaluating the merits of the shift crew concept and found the licensee's ccmmitment to be acceptable for LaSalle.
(Closed) Unresolved Item (373/80-41-12): The licensee's Draft Procedure for " Control Room Access" was reviewed during inspection 50-373/80-41 and a number of suggestions were made that addressed problems with these
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procedures with respect to the NRC requirements.
The SER in Part 22, Item I.C.4 required that the procedure be' prepared in a manner that eliminates these problems and requires the Office of I and E to review the final procedures for acceptability.
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"The inspector reviewed procedure LAP 1100-12 Revision 1, dated April
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1,1981 " Control Room Access" and found that these problems had been
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(Closed) Unresolved item (373/80-41-14): The Off.._m of NRR in inspection 50-373/80-41 veviewed Station Procedure LAP 850-4 which defined the method for dissemination of operating experience, but the procedure did not
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adequately..specify the program. The Office of NRR required that the licensee ? chang.e-its procedure prior to fuel load to more fully describe how both in-house and out-of-house cp _,ac.a,, experience is disseminated to station operating personnel and to better assure that it will be disseminated to them.
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The Office of NRR stated that the Office of I and E would review the final procedures to assure that they are acceptable to meet the requirement and are implemented prior to fuel load.
- The inspector reviewed LAP 850-6, Revision 0, dated March 12, 1981, entitled
" Distribution and Processing of Operating Experience and Information", and found that it adequately -described how both in-house and out-of-house
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operating experience is disseminated to station operating personnel.
Subsequently, the inspector interviewed several persons assigned to the operating shif ts and found that the requirements of the procedure are being implemented.
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i (Closed) Unresolved Item (373/80-16-09):
FSAR Table 15.0-1, " Input Parameters and Initial Conditions for Transient and Accidents" quoted numbers for the accident analysis that were more limiting than the values used for instrumen-tation LCO's in the proposed Technical Specifications.
The FSAR, Table 15.0-1 was in error by referencing the bottom of.the Steam Separator as instrument zero than giving distance measurements for ECCS initiation i
levels.
This error has been corrected by General Electric who acknowledged j
the archaic reference point and provided the correct reference to the bottom I
of the Steam Dryer Skirt (Instrument Zero for LaSalle).
The FSAR' Table was corrected in Amendment 56 to the FSAR.
The licensee has used the correct instrument zero reference (Technical Specifications value of 529.5 inches
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f rom the inside bottom head / bottom of the Steam Dryer Skirt) for training and procedure development all along and the ECCS safety analysis had also used the correct reference; hence, there is no reason to assume a non conservative value has been used.
(Closed) Unresolved Items (373/80-56-05), (373/80-24-01), (373/80-14-01),
and (373/79-38-32) for IE Bulletins 80-25, 80-07, 80-06, and 79-01/79-01B (including supplements) respectively.
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For the IE Bulletins closed, the inspector verified that:
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The licensee management received them.
b.
The licensee reviewed them for applicability.
c.
If the IE Bulletin was applicable to the facility appropriate
. corrective actions have been taken or are scheduled to be taken.
d.
.If a written response was required, it was within the time period stated in the IE Bulletin.
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If a written response was required, the response included information required to be reported by the IE Bulletin.
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If a written response was required, the response includes adequate corrective action commitments based on information presented in the IE Bulletin and the licensee's response.
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g.
If a written response was required, the licensee management forwarded copies of the written response to appropriate onsite management representatives.
The IE Bulletins reviewed are listed below:
Bulletin No.
Title Open Item No.
80-25 Operating Problems with Target Rock Safety-Relief 373/80-56-05 Valves at BWR's
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80-07 BWR Jet Pump Assembly Failures 373/PJ-24-01 80-06 Engineered Safety Feature (ESF) Reset Controls 373/80-14-51 79-01 Environmental Qualification of Class 1E Equipment 373/79-38-32 (this includes79-01B and supplements)
(Closed) Unresolved Items (373/81-10-03), (373/80-37-03), (373/79-44-03), (373/79-38-19), (373/79-38-16), (373/79-38-15), (373/79-38-03), and (373/79-33-06) for IE Circulars 81-03, 80-18, 79-25, 76-03, 77-14, 77-15, 79-20, and 79-09 respectively.
For the IE Circulars closed, the inspector verified that:
a.
The licensee management received them, b.
The licensee reviewed them for applicability.
c.
If the IE Circular was applicable to the. facility appropriate corrective actions have been taken or are scheduled to be taken.
The IE Circulars reviewed are listed below:
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Circular No.
Title Open Item No.
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81-03 Inoperable Seism!c Monitoring Instrumentation 373/81-10-03 80-18 10 CFR 50.59 Sa fety Evaluations for Changes to ;
373/80-37-03 Radioactive Was e Treatment Systems
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m 79-25 Shock Arrestor Strut Assembly Interference 373/79-44-03
~ 76-03 Radiation Exposures in Reactor Cavities 373/79-38-19 77-14 Separation of Contaminated Water Systems from 373/79-38-16 Noncontaminated Plant Systems 77-13 Reactor Safety Signals Negated During Testing 373/79-38-15 79-20 Failure of GTE Sylvania Relay, Type PM Bulletin 373/79-38-03 7305, Catalog SU12-11-AC with a 120V AC Coil 79-09 Occurrences of Split or Punctured Regulator 373/79-33-06 Diaphragms in Certain Self Contained Breathing
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Apparatus y
No items of noncompliance were identified in this area.
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Review of IE Bulletins Received Since Last Inspection Report
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The licensee received IE Bulletins 81-02 and 81-03 since the last inspection report written by the inspector.
The inspector verified that IE Bulletins 81-02 and 81-03 were received by the licensee with a response required.
The time periods for the licensee's required responses to IE Bulletins 81-02 and 81-03 have not elapsed and the licensee is still formulating the required responses.
The inspector will review the licensee's responses to these bulletins under Open Item Number (373/81-15-01) and (373/81-15-02) for IE Bulletins 81-02 and 81-03 respectively.
No items of noncompliance were identified in this area.
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Review of IE Circulars Received Since Last Inspection Report
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The licensee has received IE Circulars 81-05 and 81-06 since the last inspection report written by the inspector.
The licensee is still reviewing these circulars
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at this time, and the inspector will review the licensee's response during a
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subsequent inspection under Open Item Numbers.(373/81-15-03) and (373/81-15-04)
for IE Circulars 81-05 and 81-06 respectively.
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No items of noncompliance were identified in this area.
5.
Review of Operating Procedures The inspector reviewed the following LaSalle Operating Procedures (LOP's)
for content and format per Regulatory Guide 1.33 and ANSI N18.7-1976:
i LOP-FW-01, Rev. 1 of 4/4/79, Feedwater System Filling and Venting
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LOP-FW-01M, Rev. O of 1/77, Unit 1 Feedwater Mechanical Checklist LOP-MS-01, Rev. O of 1/10/79, Pressurizing and Warmup of the Main Steam Lines From Hot Standby Condition
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LOP-MS-01M, Rev. O of 4/79, Unit 1 Main Steam Mechanical Checklist LOP-NB-01M, Rev. O of 3/79, Unit 1 Nuclear Boiler Mechanical Checklist LOP-RD-01, Rev. 1 of 3/5/81, Filling, Venting and Startup of Control Rod Drive System LOP-RD-01M, Rev. 1 of 3/1/81, Unit 1 Control Rod Drive Mechanical Checklist LOP-RP-01, Rev. O of 10/27/77, Reactor Protection System MG-Set Startup and Operation LOP-RR-01, Rev. O of 2/23/79, Filling and Venting an Isolated Recirculation Loop After Maintenance-LOP-RR-01M, Rev. O of 5/79, Unit 1 Reactor. Recirculation System Mechanical Checklist LOP-RS-01E, Rev. O of 1/79, Unit 1 Rod Sequence Control System Electrical Checklist LOP-RW-01, Rev. 1 of 3/16/81, Rod Worth Minimizer Initialization and Operation All comments on the above procedures were resolved with the licensee, during the exit interview, with the following exceptions:
LOP-FW-01, Rev. 1 of 4/4/79, Feedwater System Filling and Venting and LOP-FW-01M, Rev. O of 1/77, Unit 1 Feedwater Mechanical Checklist: The licensee reported that extensive new revisions to these procedures were being worked on.
The inspector will review the new revisions against his comments during a subsequent inspection under Open Item Numbers (373/81-15-05) and (373/81-15-06) for LOP-FW-01 and LOP-FW-01M respectively.
LOP-RP-01, Rev. O of 10/27/77, Reactor Protection System MG-Set Startup and Operation: The inspector expressed concern on procedure clarity since the
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last step of the procedure leaves the power source selector switch in " Alternate" versus " Normal." The inspector will review the licensee's response during a subsequent inspection under Open Item Number (373/81-15-07).
LOP-RR-01, Rev. O of 2/23/79, Filling and Venting an Isolated Recirculation Loop After Maintenance and LOP-RR-01M, Rev. O of 3/1/81 - 5/79, Unit 1 Control Rod Drive Reactor Recirculation System. The question was raised as to whether or not the suction and discharge valves (1B33-F023A/B and IB33-F067A/B)
would be vented, through their respective vent valves, if they are closed.
The inspector will review the licensee's response during a subsequent inspection under Open Item Numbers (373/81-15-08) and (373/81-15-09) for LOP-RR-01 and LOP-RR-01M respectively.
The inspector also raised a generic question regarding the lack of procedural instructions for venting and aligning system instrumentation during afstem filling and venting. The inspector will review the licensee's responue during a subsequent inspection under Open Item Number (373/81-15-10).
No items of noncompliance were identified in this area.
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SER Items Requiring Office of Inspection sad Enforcement Followup A.
Task Action I.D.1 Control Room Design Review The Office of Nuclear Reactor Regulation (NRR) in the Safety Evaluation Report (SER) required the Office of Inspection and Enforcement (I and E)
verify corrective actions required by the SER.
A memorandum from Joei Kramer, Deputy Director, Division of Human Factors
Safety to Robert L. Tedesco, Assistant Director for Licensing, Division of Licensing dated November 24, 1980 and titled " Control Room Design Review Input For The LaSalle SER" defines these deficiencies into three categories which are as follows:
a.
Deficiencies to be corrected prior to fuel loading.
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Deficiencies to be corrected before full power operation.
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Deficiencies to be addressed in the Detailed Control Room Design Review.
All of these deficiencies are a sub' set of the staff's Control Room Design Review Report transmitted to the licensee on October 23, 1980.
The inspector reviewed the items and the results are as follows per the November 24, 1980 memorandum:
1.
Category A Deficiencies to be corrected prior to fuel loading.
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Item A.1.e. Annunciator tile reflash capability will be dersonstrated.
A.1(b) (2) *
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This item is closed.
The inspector observed reflash capability oy observing an alarm trip which annunciated, the alarm was acknowledged, which made the
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annunciator glow solid, and then another alarm was received which made the annunciator commence flashing again.
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Item A.2.a. Demarcation will be applied to control panels to promote visual recognition of closely spaced J-handle controls. A.2(b)(1)*
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This item is closed.
The inspector observed that all such demarcations have been installed.
These demarcations consist of lines on the panels that bound the J-handle controls and a color coding painted on the panels that
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Icem A.2.d. J-handles for pumps, open-close valves and throttleable l
valves will be differentiated by color, shape and texture coding.
A. 2(b) (6) *
i This item is closed. The inspector observed that J-aandles are colored
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coded such that white is a piece of equipment controller, black non-throttleable valve and brown is a throtticable valve.
The inst ecor
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h observed that a different indent shape on the lower handle also identified the purpose of the handle.
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Item A.2.f. Demonstrate availability of tools.for replacement
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of indicator lamps.
A. 2. (b) (8) *
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This.iten is closed., The inspector observed the availability of this tool and the operator demonstrated to the inspector that the tool.could be used by changing an indicator lamp.
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Item A.2.g. Demonstrate availability and use of administrative ij '
r procedures to assess indicator light status, failure or degradation.
A. 2. (b) (9 ) *
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This item is closed. The inspector reviewed LaSalle Administrative
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Procedure (LAF) LAP 1600-2. Revision 14 and determined this procedure addresses the assessment of indicator light' status, failure or
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degradation.
The inspector interviewed operators and shift engineers j
and determined that they understood how to make this assessment.
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Item A.3.b. Relabel meter strings of five or more meters to aid in meter identification. A.3.(b)(2)*
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This item is closed.
The inspector observed that all such meter
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strings have each meter uniquely identified and labeled.
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Item A.3.d. Provide demarcation to organize and identify related meters on electrical panel IPM01J.
A. 3. (b) (5) *
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The inspector observed that 'the main generator controls and meters are a grey background bound by black lines, the
"0" diesel generator controls and meters are a lighter shade of grey.
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l bound by black, and the "1A" diesel generator controls and meters are a sky blue bound by black. The described demarcation adequately organizes the related meters and controls, h.
Item A.3.f. Provide demarcation lines to improve the visual i-association of legend / indicator lights with their associated controls.
A. 3. (b) (7) *
This item is closed.
The inspector observed demarcation lines placed
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such that the indicator lights are defined to the specific control device
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that the lights are associated with.
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Item A.3.g. Replace blue indicator lamp covers for those indicators where luminance contrast is too low.
A.3.(b)(9)*
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1, This item is closed.
The licensee replaced all blue indicator lamp I
covers with clear lens spray painted with a very light blue which gives
cicar luminance while retaining the basic blue glow.
j Item A.4.a. Demonstrate that valve position indications are
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based on positive indication of plant status.
A. 4. (b) (1) *
This item is closed. The item specifically refers to ADS System and Safety / Relief Valves.
The licensee has Crosby Safety Relief
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Valves which provide positive indication of plant status via g
mechanical limit switches on the valve.
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Item A.4.c.
Relabel HPCS pump displays.
A.4. (b) (4) *
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This item is closed.
These displays, have been clearly labeled to indicate whether they are HPCS pomp discharge pressure, flow, etc.
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Item A.4.d.
Provide demarcation lines and possible color coding to associate the HPCS current meter with the HPCS pump controls.
A. 4. (b) (5) *
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This item is closed. This meter has been provided with a black boundary that clearly disassociates, the current meter frca the HPCS
diesel Fenerator controls and associates it with HPCS pump controls.
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Item A.4.e.
Provide identical penetration pressure B/C duct and B/C room temperature motors.
A. 4. (b) ( 6) (b) *
This item is closed.
The scales have been changed such that they are both 0-300 degrees F and they are clearly labeled and color coded.
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Item A.4.f.
Relocate labels that are partially obscured by indicator light covers at base of panel 1H13P601.
A. 4. (b) ( 6) (c) *
This item is closed. The inspector observed that 'the name plate has been lowered and is no longer obscured.
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Item A.4.g.
Provide RHR system white indicator lights with labels / legends that indicate system stat'us.
A. 4. (b) (6) (d) *
This item is closed.
The inspector observed legends on the white indicator light.
The legend usually is MANUAL OVERRIDE.
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Item A.4.h.
Provide label for LPCS pump cooler valve.
A. 4. (b) (7) *
Th'is item is closed. The inspector observed.a legend in place which states "LPCS Pump Cooler Upstream Stop 1DG035".
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Item A.4.i.
Relabel motor driven feedwater pump.
A. 4. (b) ( 11) (c) *
This item is closed. The pump - contro,ls. and indicators are labeled.
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P' ovide demarcation and color coding to enhance r.
Item A.4.m.
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control display relations and discrimination for Auxiliary Systems Panel / Console 1PM09 J and IPM10J.
A.4. (b) (12) (b) (c) *
This item is closed.
The inspecto observed that meters and controls have been juggled on the panels so that they are arranged by system.
The systems have been color coded, and the systems have demarcation lines.
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Item A.4.n.
Provide Electrical Control Panel IPM01J demarcation and color coding to improve control / display relationships.
A. 4. (b) (13) (a) (c) *
This item is closed.
The inspector observed proper demarcation and color coding installed in this panel.
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Item A.4.o.
Correct Turbine Control Panel labeling errors and revise turbine bearing lif t pump status indicators to read off-auto trip-on.
A.4. (b) (14) (b) (c) *
This item is closed.
The lif t pump status indicators have been revised in the proper fashion and the labeling errors have been corrected.
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Item A.4.p.
Revise Reactor Water Cleanup and Recirculation Panel
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1H13P602 filter demineralizer status light sequence to correspond to vertical panel indicator se.quence, and provide missing labels for this panel.
A. 4. (15) (a) (d) *
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This item is. closed.
The status light sequence and vertical panel indicators are now in conformance, and the missing labels have been provided.
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Item A.4.q.
Provide Reactor Control Panel range switch A lab el.
A. 4. (16) (c) *
This item is closed.
The proper label has been placed.
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Item A.4.r.
Provide HVAC Console and Panel 1PM05J and IPM06',J vith color coding and shading to associate related controls
and displays, and provide demarcation to discriminate specific HVAC subsystens.
A. 4. ( 17) (a) (b) *
This item is closed.
Color coding is provided which matches systems from bench board to systems on vertical panels.
Demarcation lines are provided
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between systems ac ecil as color coding.
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Tem 1 A.5.a.
Increase size of system or oajor function labels for all panels.
A. S. (b) (1) *
This item ir closed.
The labels have been increased to minimum 1/2" and nomiral 7/8" size and they are clearly readable.
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Item A.5.c.
Provide demarcation lines to improve visual discrimination of auxiliary system indicator lights (10x11 matrix).
A. S. (b) (4) *
This item is closed.
This item was particularly concerned with the indication for the excess flow check valves on panel IPM10J. The
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. inspector observed that each of the green open and red closed lights
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' are separated from its counterpart by an installed black demarcation line.
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Item A.S.e.
Demonntrate accomplishment of the labeling revisions
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specified in the Pceliminary Assessment Report, items Id 2-5, 3:'
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A. 5. (b) (6) *
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This item is closed.
The inspector followed the mimics and labeling, and established that it is done.
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Item A. 6.b.
Establish consistent systems for dual-recorder
upper / lower pen colors, and provide appropriate labels for each recorder that will be consistent with pen location and color.
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coding.
A. 6. (b) (2) (3) (4) (5) *
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This item is closed.
The dual pen recorders always have red on top and blue or black on the bottom, and the labels are correct.
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Item A.6.d.
Modify SRKtemperature recorder (panel 1H13P614)
to eliminate cmbiguity as to which channel is being displayed.
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A. 6. (b) (8) *
This item is closed.
The inspecto, observed that the panel has a lite lit identifying the point and c'ard which identifies the point with the
valve being monitored.
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Item A.7.c.
Replace white indicator lights with white backlight legend lights.
A. 7(b) (2) (a) *
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This item is closed.
This item'is redundant-to o. above Item A.4. g.,
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except that it extends to other panels with white lights.
The fix is the same as o. above in that the lenses have been engraved.
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Item A.7.d.
Replace black emergency trip push buttons with red push buttons.
A. 7. (b) (2) (b) *
This item is closed.
The turbine trips, manual scrams, ECCS manual initiations, etc. have been converted to red buttons.
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Item A.7.e.
Demonstrate installation and accuracy of new mimics and demarcations as described in the Preliminary' Assessment Report.
A. 7. (b) (3) (4) *
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This item is closed.
The inspector reviewed mimicing and demarcation on:
HVAC panel IPM063 RHR pump IC RHR pump 1B
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RHR A and B heat exchangers RHR shutdown cooling and head spray RCIC and steam condensing mode of RHR
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Main steam lines The inspector found no problems, ff.
Item A.7.g.
Install new covers for blue status lights where luminance contrast is too low.
.A. 7. (b) (5) (b)
This item is closed.
This item > is. redundant to 1. above * Item'1.'-3. g.,
and is closed in the same fashion.
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Item A.7.j.
Improve visual recognition of phone jacks on control room back panels.
A. 7. (b) (8) (a) *
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This item is closed.
These jacks are labeled and bound in black lines of demarcation.
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Item A.8.
Remote shutdown panel is to be provided with panel
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mimics and demarcation as well as demonstration of emergency lighting provisions in the remote shutdown panel area.
A. 8. (b) (1) (3)
This item is complete.
The panel is mimiced, demarcation lines h' ave been provided between systems, and the emergency lighting is installed and is working.
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Item A.9.a.
Demonstrate trending capability of computer printouts and CRT displays.
Install labeling system for strip chart trend recorders.
A. 9 (b) (1) *
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This item is closed.
The inspector observed that the labeling system identifies which pen is which and that the trending. recorders work
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and it is assumed will trend when there is something for it to trend.
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Item A.9.c.
Modify CRh displays to improve CRT Teadability.
A. 9. (b) (3) *
This item is closed.
The licensee increased the stroke width for easier readability.
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Item A.9.e.
Relabel point ID display to be consistent with thumbwheel control.
A. 9. (b) (5) *
This item is closed.
The inspector observed that the point ID display
is consistent with the thumbwheel control.
ii.
Item A.9.f.
Reorganize point ID index by component number and
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A.9.(b)(7)*
This item is closed.
The licensee has reorganized this index into alphabetical order by system.
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2.
Items which remain to be closed:
Category A deficiencies to be corrected prior to fuel loading a.
Open Item Number (373/81-15-11):
1) Item A.1. a. ( A.1. (b) (2)) *
2) Item A. l.b. (A.1. (b) (4))*
3) Item A.l.c.
( A.1. (b) (8)) *
4) Item A.I.d. ( A.1. (b) (9)) *
5) Item A.2.b. ( A. 2. (b) (2)) *
6) Item A.2.c. ( A.2. (b) (4)) *
7) Item A.2.e.
(A. 2. (b) ( 7)) *
8) Item A.2.h.
(A. 2. (b) (10)) *
9) Item A.3.9. ( A. 3. (b) (1)) *
10) Item A.3.c. ( A. 3. (b) (3)) *
11) Item A.3.e. ( A. 3. (b) (6)) *
'12) Item A.4.b. ( A.4. (b) (3)) *
' 13) Item A. 4. i. ' (A.4. (b) (9))*
14) Item A.4.j. (A. 4. (b) (10) ) *
15) Item A.4.k. (A.4. (b)(11)(a),(b),(c), and (d))*
16) Item A.S.b.
( A. 5. (b) (2)) *
17) Item A.5.d.
( A. S. (b) (5)) *
18) Item A.6.a.
(A. 6. (b) ( 1)) *
19) Item A.6.c.
(A. 6. (b) (6))*
20) Item A.7.a.
(A. 7. (b) (1) (d)) *
21) Item A.7.b. _(A.7. (b)(1)(i))*
22) Item A.7.f.
(A. 7. (b) (5) (a) ) *
23) Item A.7.h.
(A. 7. (b) (5) (c)) *
24) Item A.7.1.
( A. 7. (b) (6) *
25) Item A.7.k.
( A. 7. (b) (8) (b)) *
26) Item A.7.1. ( A. 7. (b) (8) (c)) *
27) Item A.7.m.
(A. 7. (b) (9) (b) (c)) *
28) Item A.9.b.
(A. 9. (b) (2)) *
b. Category B' deficiencies to be corrected prior to full power operations Open Item Number (373/81-15-12):
i All listed.
c. Category C deficiencies to be addressed in The'Jetailed Control Room Design Re. view. Open Item Number (373/81-13-13):
All listed.
- Indicates Control Room Design Review of October 23, 1980 identifying number.
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B. Ta_sk Action I.C.4 Control Room Access This item was closed in part 2. of this report " Licensee Action on Previous Inspection Findings" by closing Open Item (373/80-41-12)
as stated.
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C. Task Action I.C.5 Licensee Dissemination of Operating Experience This item was closed in part 2. of this report " Licensee Action on Previous Inspection Findings" by closing Open Item (373/80-41-04)
as stated.
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No items of noncompliance were identified in this area.
7.
Participation Advisory Committee On Reactor Safeguards (ACRS) Meetings The Senior Resident Inspector prepared for and attended an ACRS meeting held on 4-3-81 and 4-4-81 in Morris, Illinois 'and an ACKS meeting held on 4-9-81 in Washington, D.C.
The Senior Resident Inspector's participation in these tectings was requested by the Offi.e of Nuclear Reactor Regulation (NRR) Licensing Project Manager (LPM) becau e the meetings were held to discuss in a public forum the issues surrounding LaSalle County Units #1 and #2
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Safety Evaluation Report (SER).
No items of noncompliance were identified in this area.
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8.
Inspection Activities Preparatory to License Issuance (Status of Licensee Procedures and Preoperational Testing Program)
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'a.
Operating. Maintenance, Surveillance, Abnormal and Emergency Procedure Status The licensee currently has approved for use approximately 91% of these procedures, 7% of these procedures have been draf ted but not reviewed, and 2% of these procedures remain to be draf ted.
b.
Preoperational Testing Program Status i
- The licensee projects a total of 125 Preoperational Tests / System l
Demonstrations required for Unit 1 operations of which 115 of these l
are specific to Unit 1 and the remaining 10 are cpecific 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, unat 73 Preoperational Tests and l
System Demonstrations have been completed, and the preoperational testing program is approximately 81.5% complete at this time.
The licensee stated that final Preoperational. Test or System Demonstra-
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tion results for 28 tests are ready for NRC review, i.e., the entire test is complete and the results have been reviewed and accepted by the
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i licensee. These twenty eight tests are PT-D0-101 " Diesel Oil,"
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PT-VY-102 "LSCS Equipment Ventilation," PT-PV-101 " Reactor Vessel
Internals Vibration," PT-D0-201 " Unit 2 Diesel Oil," PT-FC-101 " Fuel Pool Cooling and Cleanup," PT-NR-101A " Source Range Monitors,"
PT-SC-101 " Standby Liquid Control," PT-VJ-101 " Machine Shop Ventila-tion," Pt-VD-101 "Off Gas Ventilation," SD-WR-101 " Reactor Building Closed Cooling Water System," SD-CW-101 " Circulating Water System,"
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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
" Power 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," SD-EH-101B " Turbine Supervisocy," SD-CD-102 " Condenser and Auxiliaries," SD-W-102
"Feedwater Control," SD-HD-101B " Moisture Separator Reheaters,"
and PT-VP-101 " Primary Containment Vent and Purge".
i c.
Deficiencey Status The licensee is currently listing 1471 Station Operations deficienc-ies and 3050 Station Constructiot deficiencies as outstanding itens.
The licensee has attempted to segregate these deficiencies into those that will impact fuel load and those that will not.
The licensee has reviewed approximately 4032 of these deficiencies for segregation and preliminary assessment is that 1479 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
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The inspector conducted walkthroughs and reviewed the plant operations status including examinations of control room log books, routine patrol sheets, shif t engineers log books, equipment outage logs, special operating orders, and jumper tagout logs for the period of March 9,1981 through April 17, 1981. The inspector observed the operations status during three off-shif ts 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 conducted tours of Units 1 and 2 reactor, auxiliary, and turbine buildings throughout the period and noted the status of construction and plant housekeeping / cleanliness. With respect to housekeeping / cleanliness, the inspector noted that conditions of general cleanliness we e adequate throughout the facility. The inspector observed shif t turnovers to verify
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that plant component status and problem areas were being turned over to a relieving shift.
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No items of noncompliance were identified in this area.
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10.
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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