IR 05000373/1979015
| ML19246C306 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/30/1979 |
| From: | Spessard R, Walker R, Wright G NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19246C304 | List: |
| References | |
| 50-373-79-15, NUDOCS 7907240127 | |
| Download: ML19246C306 (6) | |
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U.S. SUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-373/79-15
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Docket No. 50-373 License No. CPPR-99 Licensee:
Commonwealth Edison Company P. O. Box 767 Chicago, IL 60690 Facility Name: La Salle County Nuclear Station, Unit 1 Inspection At: La Salle Site, Seneca, Illinois Inspection Conducted: April 2-3 and 18-20, 1979 b-N
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Inspectors:
R. D. Val er, h/3c,79 ri O
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R. L. Spessard,-Chiet
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Reactor Projects Section 1 In ;pection Summa ry M spection on April 2-3 and 18-20, 1979 (Report No. 50-373/79-15)
Arjas Inspected:
Routine, unannounced preoperational inspection concisting of a review of responses to IE Bulletins, operating proctdures, IE Headquarters requests, NRR requests, a plant walk-through and an onsite meeting with the facility staff and NRR, concerning facility Technical Specifications.
The inspection involved a total of 66 inspector-hours onsite by two NRC inspectors.
Results: No items of noncompliance or deviations were identified.
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DETAILS 1.
Persons Contacted
- R. H. Holyoak, Plant Superintendent
- G. J. Diederich, Assistant Plant Superintendent
- R. D. Bishop, Technical Staff Supervisor
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- R. H. Raguse, Senior Operating Engineer
- G. W. Reardanz, Senior Quality Assurance Inspector
- J. C. Renwick, Operating Engineer
- R. F. Phares, Maintenance Fuel Foreman
- R. D. Quinn, Maintenance Staff
- J.
W. Andrews, Technical Staff
- Denotes those present at the exit interview.
2.
Licensee Actior_pn Previous Inspection Findings Station Operating Procedure Review The inspecto..,ntinued his review of stetion operating proce-dures for scope, content and formats to assure that the plant operating procedures are prepared to adequately control safety-related operations =ithin applicable regulatory require-ments. This review will continue for some time as more systems are walked down by the operating staff to finalize valve lists, etc.
The inspector will carry the operating procedure review as an open item and specific identification numbers have been assigned 'or purposes of open item tracking, as listed below.
Inspectic a Report No. 50-373/78-21 listed the following procedures as having been reviewed by the inspector.
LOP-RT-01E Reactor Water Cleanup System Electrical Checklist.
LOP-RT-OlM Reactor Water Cleanup System Mechanical Checklist.
LOP-RT-01 Reactor Water Cleanup System Filling and Venting.
LOP-RT-05 Reactor Water Cleanup System Filter / Denim Backwash.
LOP-RT-02 Reactor Water Cleanup Systeo Startup LOP-RT-08 Reactor Water Cleanup System Strainer Backwash-2-bb
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LOP-SC-01E Standbf Liquid Control System Electrical Checklist.
LOP-SC-01M Standby Liquid Control System Mechanical Checklist.
LOP-SC-01 Filling, Venting and Draining the Standby Liquid Control System.
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LOP-WR-01E Reactor Building Closed Cooling Water System Electrical Checklist.
LOP-WR-Olri Reactor Building Closed Cooling Water System Mechanical Checklist.
LOP-WR-02 Startup and Operation of th. Reactor Building Closed Cooling Water Syrtem.
LOP-WR-03 Charging the Reactor Building Closed Cooling Water System Chemical Feeder.
LOP-WR-04 Reactor Building Closed Cooling Water System Supply to Drywell Coolers.
LOP-SC-02 Standby Operation of the Standby Liquid Control System.
LOP-SC-03 Standby Liquid Control Solution Tank Draining.
LOP-SC-04 Standby Liquid Control Solution Tank Filling.
LOP-HP-01E High Pressure Core Spray Electrical Checklist.
LOP-HP-01M High 'ressure Core Spray Mechanical Checklist.
LOP-HP-01 Filling and Venting of High Pressure Core Spray System.
LOP-HP-03 Preparation for Standby Operation of High Pressure Core Spray System.
LOP-RI-01E Reactor Core Isolation Cooling System Electrical Checklist.
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LOP-RI-01M Reactor Core Isolation Cooling System Mechanical Checklist.
LOP-RI-05 Preparation for Standby Operation of the Reactor Core-solation Cooling System.
u0P-RI-04 Turbine Trip Recovery and Turbine Reset Reactor Core Isolation Cooling System.
LOP-RI-02 Startup and Operation of the Reactor Core Isolation Cooling System.
LOP-RI-03 Reactor Core Isolation Cooling System Shutdown LOP-LP-01E Low Pressure Core Spray System Electrical Checklist.
LOP-LP-01M Low Pressure Core Spray System Mechanical Checklis*-
LOP-LP-02 Preparation for Standby Operation of the Low Pres re
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Core Spray System.
LOP-LP-03 Shutdown of Low Pressure Core Spray System After Automatic Initiation.
The inspector reported in the above referenced report with respect to these procedure. that numerous procedures required are not yet available for.eview by the inspector and that many of the procedures reviewed by the inspector were incomplete or in error.
The licensee responded that these problems would be worked out and the procedures would be ready for review at the completion of preoperational testing. The inspector cautioned
. that he must have suf ficient time for procedure review prior to license approval. The licensee's procedures in this area will be reviewed in a future inspection.
SL5 sequent reviews of the following procedures ' ave satisfied a
the.2spector's concerns for the below listed procedures.
LOP-SC-Olm Standby Liquid Control System Electrical Checklist LOP-SC-01M Standby Liquid Control Ssytem Mechanical Checklist LOP-WR-03 Charging the Reactor Building Closed Cooling Water System Chemical Feeder.
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LOP-HP-03 Prepara[ ion for Standby Operation of High Pressure Core Spray System.
LOP-LP-01E Low Pressure Core Spray System Electrical Checklist.
The remaining procedures from Inspection Report No. 50-373/78-21 have been assigned open item numbers as listed below. Further tracking of the status of the review of these procedures will
be per the open item numbers shown.
Open Item Number Procedure 373/79-15-01 LOP-RT-01E Reactor Water Cleanup System Electrical Checklist S73/79-15-02 LOP-RT-OlM Reactor Water Cleanup System Mechanical Checklist 373/79-15-03 LOP-RT-05 Reactor Water Cleanup System Filter / Denim Backwash 373/79-15-04 LOP-RT-02 Reactor Water Cleanup System Startup 373/79-15-05 LOP-RT-08 Reactor Water Cleanup System Strainer Backwash 373/79-15-06 LOP-E :-01 Filling, Venting and Draining the Standby Liquid Control System 373/79-15-07 LOP-WR-01E Reactor Building Closed Cooling Water System Electrical Checklist 373/79-15-08 LOP-WR-01M Reactor Building Closed Cooling Water System Mechanical Checklist 373/79-15-09 LOP-WR-02 Startup and Operation of the Reactor Building Closed Cooling Water System 373/79-15-10 LOP-WR-f'4 Reactor Building Closed Cooling Water System Supply to Drywell Coolers 373/79-15-11 LOP-SC-02 Standby Operation of the Standby Liquid Control Syrcem f
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373/79-15-12
' LOP-SC-03 Standby Liquid Control Solution
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Tank Draining 373/79-15-13 LOP-SC-04 Standby Liquid Control Solution Tank Filling 373/79-15-14 LOP-HP-01E High Pressure Core Spray Electrical Checklist
373/79-15-15 LOP-HP-01M High Pressure Core Spray Mechanical Checklist 373/79-15-16 LOP-HP-01 Filling and Venting of High Pressure Core Spray System 373/79-15-17 LOP-RI-01E Reactor Core Isolation Cooling System Electrical Checklist 373/79-15-18 LOP-RI-01E Reactor Core Isolation Cooling System Mechanical Checklist 373/79-15-19 LOP-RI-05 Preparation for Standby Operation of the Reactor Core Isolation Cooling System 373/79-15-20 LOP-RI-04 Turbine Trip Recovery and Turbine Reset Reactor Core Isolation Cooling System 373/79-15-21 LOP-RI-02 Startup and Operation of the Reactor Core Isolation Cooling System 373/79-15-22 LOP-RI-03 Reactor Core Isolation Cooling System Shutdown 373/79-15-23 LOP-LP-01M Low Pressure Core Spray System Mechanical Checklist 373/79-15-24 LOP-LP-02 Preparation for Standby Operation the Low Pressure Core Spray System 373/79-15-25 LOP-LP-03 Shutdown of Low Pressure Core Spray System After Automatic Initiation No items of noncompliance or deviations were identified.
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3.
Review of IE Bulletins The following Bulletins were sent to all BWR facilities with a construction permit for intormation only and no written response
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was required:
78-03 " Potential Explosive Gas Mixture Accumulations Associated with BWR Off gas System Operations"
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78-14, " Deterioration of Buna-N Components in Asco Solenoids" 79-08, " Events Relevant to Boiling Water Reactors Identified During Three Mile Island Incident" The inspector explained to the licensee that these IE Bulletins required no written response to the NRC by a construction permit holder because they principally concern the operations phase of the Reactor Inspection Program. The inspector further explained that the bulletins should however, be reviewed by the licensee and appropriate actions taken and documented to assure that the problems identified in the bulletins would not be manifested when the plant achieves operating status.
The inspector reviewed the licensee's action on these three bulletins to assure himself that the licensee is addressing in an appropriate fashion bulletins which require no response are germain to BWR's during the operations phase.
The results of that review are as follows:
The licensee had conducted an onsite review of the issues addressed in that bulletin and documented his review. The inspector obtained a copy of the licenser's documentation and is conducting an in office review to assure himself that the licensee's revies is adequate. This item will remain open until the inspector completes his in office review.
(337/79-15-26)
The licensee has started action to formalize a program to change out these components on a regu-larly scheduled basis.
This program has not been formalized and the inspector will review it when it is formalized.
The licensee has checked the cure date en the applicable com-ponents which are on site as spare parts and found that they are out of date. The licensee is attempting to return these components to the vendor to receive new ones.
The licensee has-7-nn0 i~
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agreed to check the cure date on the installed components to ascertain if they are out-of-date.
The licensee's actions in these areas will be reviewed on o subsequent inspection and the review of IE Bulletin No 78-14 will remain open until the inspector completes his review.
(373/79-15-27)
The licensee had just received this bulletin and no action has been taken. The bulletin is quite extensive and will take some time for the licensee to implement action in full. The inspector will review the licensee's actio. on this bulletin on a subsequent inspection and this itee will remain open until the inspector completes this review.
(373/79-15-28)
Response to IE Headquarters Requests IE Temporary Instruction TI 2515/22 called for an inspection of concerns addressed in that instruction with respect to Terry turbines equipped with PG-PL Woodward Governors used to drive auxiliary feedwater pumps at some PWR's.
The inspector exten-ded this review to assure himself the problem did not occur in Terry Turbines used in BWR, HPCI and RCIC applications. The inspect ascertained that Terry Turbines used in these BWR applications do not have PG-PL Woodward Governors, but are equipped with EB/R-EG/M Woodward Governors. The inspector discovered that GE FDI No. 73-57434 addresses problems with Terry Turbines equipped with EG/R-EG-M Woodward Governors. The licensee has performed the modifications suggested in GE FDI No. 73-57434.
No items of noncompliance or deviations were identified.
5.
I_E Input to NRR Review The inspector was asked to review the following items for the NRR Instrument and Control Brancb:
Main Steam line leak detection thermocouple amplifier a.
power supplies Division 1 and Division 2 separation by six inches or a metal barrier within junction boxes.
The specific cable and junction boxes in question are cable ILD168 and panels 632 and 642. Drawing No. 214629AC shows that GE field disposition instruction H4DC2 calls for a metal enclosure in panel 642 to meet this criteria.
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Wiring from bypass switches for APRM's, RBM's, and IRM's is not joined together in one bundle from the control room panels.
Observation showed RPS divisionel separation is maintained in these bundles.
No items of noncompliance or deviations were identified.
5.
Meeting with Licensee Staff and NRR Regarding Facility Technical
Specifications Mr. Robert Bottimer of the Office of Nuclear Reactor Regulation (NRR) conducted a meeting with members of the licensee's staff on April 18 and 19, 1979.
The n"
pose of the meeting was to attempt to resolve issres related to issuance of the licensee's Technical Specifications in final form. The inspectorr, attended this meeting to provide I&E input to the discussions. Meetings of this type will continue throughout the licensing process and the cssector intends to attend as many as possible to assure himself that the Technical Specifications are adequate for facility operation.
6.
Plant Walkthrough The inspector conducted a plant walkthrough on April 13 and again on April 20, 1979, to review the status of plant equip-ment and general housekeeping.
The inspector noted on both occasions that cleanliness in the area of new fuel storage was much improve 3.
The licensee has turned over responsibility for cleanliness in this area from station construction to station operations. The station main-tenance refueling personnel now have cognizant responsibility for cleanliness in this area. The inspector was still coccern-ed with the quality of the air on the refueling floor and the affects of air quality on fuel cleanliness once the new fuel is unpackaged and channeled for storage.
The licensee responded to the inspectors concerns by agreeing to the following:
a.
All fuel will remain covered with a fire retardant protec-tive cover. The inspector reviewed the cleanliness of fuel stored in this manner under similar air quality conditions for approximately two months.
The inspector's review e, cart. tined no si.gnificant contamination of sur-faces from sc2page during such storage.
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Fuel that is to be coaaneled will be removed from th'.s storage in racks of approximately ten bundles.
Prior to removal the protective
,ver will be vacuumed to preclude dirt on the cover from,.lling onto exposed fuel.
The cover will be replaced over the remaining fuel after the bundles to be channeled are removed.
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While a bundle is being channeled the remaining bundles in c.
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the removed rack will be covered to preclude contamination.
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The rack of fuel bundles will be returned to the protective covering upon completion of channeling activities.
The inspector deemed these procedures adequate to protect fuel cleanliness, but cautioned the licensee that if current atmos-pheric conditions on the refueling floor significantly deterio-rate, further actions will have to be taken.
No items of noncomoliance or deviations were identified.
7.
Exit Interview The inspectors met with licensee representatives (denoted in Paragraph 1) at the conclusion of the inspection on April 20, 1979. The inspectors summarized the purpose and the scope of the inspection findings.
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