IR 05000373/1986019
| ML20198K407 | |
| Person / Time | |
|---|---|
| Site: | LaSalle  |
| Issue date: | 05/28/1986 |
| From: | Falevits Z, Muffett J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML20198K400 | List: |
| References | |
| 50-373-86-19, 50-374-86-18, NUDOCS 8606040019 | |
| Download: ML20198K407 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION III
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i Reports No. 50-373/86019(DRS); 50-374/86018(DRS)
Docket Nos. 50-373; 50-374 Licenses No. NPF-11; NPF-18
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Licensee: Commonwealth Edison Company
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Post Office Box 767 Chicago, IL 60690 i
Facility Name:
LaSalle County Station, Units 1 and 2 l
Inspection At:
LaSalle Site, Marseilles, IL
Inspection Conducted: M 6-8, 1986 k, &hl Inspector:
Z. Falevits 5/ts/16 Date dow d Approved By:
J. Muffett, Chief F/28/%
l Plant Systems Section Date Inspection Summary i
Inspection on May Areas Inspected:
_6-8, 1986 (Reports No. 50-373/86019 (DRS); 50-374/86018 (DRS))
Routine unannounced inspection of corrective action taken to reduce excessive temperatures in Unit 2 drywell; applicable surveillance
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procedures; environmental qualification program for safety-related equipment
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in the drywell; licensee action on previous inspection items.
Results: Of the areas inspected, one violation was identified (failure to follow procedures which require quarterly submittal of collected drywell temperature data to SNED for review and evaluation - Paragraph 2.c.).
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9606040019 B60528 PDR ADOCK 05000373 G
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DETAILS 1.
Persons Contacted Commonwealth Edison Company (CECO)
- R. D. Bishop, Service Superintendent
- P. F. Manning, Technical Staff Supervisor
- R. W. Stdbert, Station Quality Assurance (QA) Supervisor
- H. L. Massin, Station Nuclear Engineering Department (SNED) Supervisor
- K C. Wittenburg, Technical Staff Engineer
- A. M. Lucietto, Technical Staff Engineer
- D. A. Spencer, Technical Staff Engineer US NRC M. J. Jordan, Senior Resident Inspector
- Denotes those in attendance at the exit meeting on May 8, 1986.
The inspector also contacted and interviewed other licensee and contractor personnel during this reporting period.
2.
Licensee Deferral of Unit 2 Drywell Cooling Long Term Modification a.
In a CECO letter to the NRC dated April 30, 1986, the licensee described the deferral of certain Unit 2 high drywell temperature long term modifications until the second refueling outage of Unit 2.
The licensee's reason for this deferral was to reduce the scope of work scheduled for the first Unit 2 refueling outage. The licensee concluded that postponement of the modification would not, adversely affect the equipment qualification analysis on file, and that the primary intent of this modification is to restore drywell cooling redundancy.
l As part of the Region III review of the licensee's deferral request, the inspector reviewed the short term corrective actions taken by i
the licensee to reduce Unit 2 excessive drywell temperatures, and to l
ascertain whether they had been effectively controlled and i
implemented.
During a previous NRC inspection conducted in August, l
1985, the inspector noted that Unit 2 temperatures in the upper L
elevations of the drywell were excessively high.
Subsequently, the licensee has taken the following corrective measures to reduce the
drywell temperatures to acceptable levels.
(1) Multipoint recorders have been added to allow for continuous
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drywell temperature monitoring from the temporary thermocouples located near safety-related components inside the drywell.
(2) A new procedure was issued specifically addressing the drywell i
temperatures monitoring program to assure that any higher than
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expected drywell temperatures that might develop will be promptly
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detected, analyzed and resolved.
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(3) Drywell temperature data collected on a weekly basis to be transmitted to SNED, quarterly, for review and evaluation of the system's operation to assure continued environmental qualification of drywell equipment.
(4) The area monitoring technical specification for the environmental qualification of drywell electrical equipment requires a special report if temperatures near safety-related equipment exceed 150 F.
If temperatures exceed 180 F the equipment must be declared inoperable.
(5) The licensee noted that with the current understanding of the drywell heat loads, LaSalle can meet Technical Specification 3.6.1.7 and the drywell equipment is qualified to operate during the Design Basis Accident during which equipment must perform an active safety function, b.
The inspector reviewed licensee's drywell temperature monitoring program weekly surveillances (LTP-100-3) conducted since December, 1985. The data collected indicated that the actual average air temperature in the Unit 2 drywell has decreased as compared to readings taken in August, 1985.
Except for thermocouple 2TE-VP215 located by Safety Relief Valves 2B21-F013K and 2B21-F013S which exceeded the technical specification limit of 150 F by 3 F, all other thermocouples located by safety-related equipment transmitted readings which were below 150 F.
In regard to 2TE-VP215 readings recorded, the licensee submitted two special reports dated January 8 and April 4, 1986.
These reports were submitted in accordance with Technical Specifications 3.7.7.a and 6.6.c.
The special report dated January 8, 1986, indicated that the corrective actions taken by the licensee have made considerable improvements in the drywell temperature.
The majority of temperatures monitored have decreased markedly, as shown by the following table:
Sensor Evaluation Temperature Change Drywell Head-60 F j
815'
-51 F 810'
-50 F 804'
-90 F 795'
-25 F 790'
-10 F 785'
-15 F 777'
-10 F Bulk Average-12 F Regarding the remaining qualified life of the SRV solenoids, the analysis of the NUREG 0588 Category II of the SRV solenoids performed by the licensee shows that with temperatures below 170 F by the SRV solenoids, they still have almost 16 years of qualified life.
With the understanding that readings are taken once a week using the temporary thermocouples and that technical specifications temperature e
limits are monitored on a daily basis, the inspector believes that the drywell temperatures can be controlled within acceptable limits.
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Based on the licensee's drywell monitoring program now in effect to assure that safety-related equipment and cables do not degrade beyond predefined thresholds, and the fact that the licensee concluded that postponement of the modifications would not adversely affect the equipment qualification analysis or file, the inspector has no further concerns.
c.
Item F.4. of procedure LTP-300-17, Revision 1, requires that once per quarter the collected drywell temperature data be submitted to SNED for review and evaluation of the system's operation with respect to the requirements of the environmental qualification analysis. The
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inspector noted that drywell temperature data covering the quarterly period from October 18 to December 31, 1985, was transmitted to SNED.
However, no objective evidence was available to substantiate that the data collected from January 1 to March 31, 1986 was transmitted. The inspector informed the licensee that failure to adhere to Procedure LTP-300-17, Revision 1, requirements constitutes a violation of 10 CFR 50, Appendix B, Criterion V (374/86018-01).
During this D
inspection the licensee promptly transmitted the quarterly collected f
drywell temperature data to SNED for review and evaluation and assured
the inspector that closer attention will be placed to this issue in the future.
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d.
The inspector compared the licensee's temperature trigger setpoints to each thermocouple's output reading as denoted in AIR-251-85-00121.
This was done to assure that Procedure LTP-300-17 addresses environ-mental qualification (EQ) threshold temperatures and also to correlate a sensor with the applicalbe EQ binder.
The inspector noted that a trigger setpoint of 170 F was given to Sensor 2TE-VP209 in Procedure LTP-300-17 where AIR-215-85-0021 required a trigger setpoint of ISC F.
The licensee informed the inspector that the procedure will be revised to reduce the trigger setpoint of Senor 2TE-VP209 to 150 F.
e.
Review of the EQ binders indicated that since September, 1986, a revision of all binders has been in progress (Revision 3) to reflect the new analysis and trigger setpoints. Action item report AIR-373-251-85-0016 requested that the revision to the binders be completed by February 1, 1986, however, as of May 9, 1986, Revision 3 was not included in the EQ binders at the LaSalle plant.
i During the exit meeting on May 8, 1986, a SNED representative stated that Re ision 3 will soon arrive at the LaSalle plant.
f.
The inspector reviewed the design drawings associated with RCIC Valve 2E51-F066.
This valve's limit switches and solenoid had been downgraded by the licensee from Category I (ESS), to Category II (Bop). However, all applicable design drawings including cabling denote this valve as ESS Category I.
The licensee stated that the engineering department will review this issue for both Valves IE51-F066 and 2E511F066, and that corrective action will be taken to resolve this issued.
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3.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (373/85013-04):
This item concerns lack of an approved vendor QA program to repair a Diesel Generator Cooling Water motor.
The licensee has adequately addressed the inspector's concerns.
The corrective action taken by the licensee is documented in AIR-373-100-01304 dated September 17, 1985.
(Closed) Open Item (373/85034-01): This item concerns yellow termination lugs inside the upper most limit switch box on Valve 1E12-F041C which were dark brown and appeared to the inspector to be charred (an indication of overheating).
Licensee response to this item as documented in AIR-373-100-85-83401 dated March 11, 1985, indicates that although the lugs in the upper box were brown rather than yellow in color no apparent overheating was noticed. The licensee inspected the lugs for brittleness, cracking, or deformation none were found.
The licensee also notes that the limit switches of Valve IE12-F041C do not serve a safety function.
(Closed) Open Item (374/85035-02):
The NRC inspector noted, metal grinding products on the stem and in the bell casting of RCIC Steam Supply Valve 2E51-F063.
The licensee inspected Valve 2E51-F063 and noted in AIR-374-100-85-03502 dated March 11, 1986 that the bronze grinding products found on the valve stem are due to normal wear between the stainless steel valve stem and the Aigh tensile bronze stem nut.
The licensee cleaned and lubricated the valve stem under Work Request L53393. Also, a new surveil-lance lubrication program at LaSalle will assure that valve stems area cleaned and lubricated during each refueling outage.
(Closed) Open Item (373/85034-03): This item concerns the determination of two safety-related deformed cables passing through junction box IJB200C have been damaged.
Licensee's review of this item is documented in AIR-373-100-85-03403 dated March 11, 1986.
The licensee indicated that the only deformities on cables in junction box 1JB200C were observed at the point the cables were spliced. The licensee determined that the deformation of these cables does not present an operability concern.
4.
Exit Interview The inspector met with the licensee representatives at the conclusion of the inspection on May 8,1986, and summarized the scope and findings of the inspection.
the licensee acknowledged the statements made by the inspector. The inspector also discussed the likely informational content of the inspection report with regard to documents reviewed by the inspector during the inspection. The licensee did not identify any such oocuments a prop ri e ta ry.
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