IR 05000010/1980001
| ML19309B476 | |
| Person / Time | |
|---|---|
| Site: | Dresden  |
| Issue date: | 02/08/1980 |
| From: | Hayes D, Julie Hughes NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19309B473 | List: |
| References | |
| 50-010-80-01, 50-10-80-1, 50-237-80-01, 50-237-80-1, 50-249-80-01, NUDOCS 8004040199 | |
| Download: ML19309B476 (5) | |
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U.S. NUCLEAR REGULATORY COMMISSION OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-10/80-01; 50-237/80-01; 50-249/80-01 Docket No. 50-10; 50-237; 50-249 License No. DPR-2; DPR-19; DPR-25 Licensee:
Commonwealth Edison Company Post Office Box 767 Chicago, IL 60690 Facility Name: Dresden Nuclear Power Station, Units 1, 2 and 3 Inspection At: Dresden Site, Morris IL Inspection Conducted: January 8-9, 1980 Inspector:
. Hughe FC
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' Q2 ApprovedBy:f.W. Hay
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, Chie Engineering Support Section 1 Inspection Summary Inspection on January 8-9, 1980 (Report No. 50-10/80-01; 50-237/80-01; 50-249/80-01 Areas Inspected: Routine, announced inspection of Units 2 and 3 Emergency Diesel Generator modifications; modification of electrical equipment for Unit I relative to compliance to IEEE-279 and, followup of previously
identified unresolved items. The inspection involved a total of 14 in-spector hours on site by one NRC inspector.
Results: No items of noncompliance were identified.
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(Closed) Unresolved Item (10/78-26-03) - No documentary evidence that
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multiconductor instrument (mfg. unknown) cable is environmentally quali-fied. The licensee determined that this type of cable is not being used in safety-related systems.
Plant Modifications for the Diesel Generators (Units 2 and 3)
1.
The inspector observed the installed diesel generator modifications:
(Reference NRC letter to C. Reed dated April 16, 1978)
Alarm for manual air shutoff valve placed in the closed position.
a.
b.
Alarm for bus tie ' reaker between the diesel generator and its s
emergency bus placed in the test position.
Circuit revisions to allow multiple diesel air start attempts, c.
d.
Alarm for incorrect droop setting.
2.
The inspector reviewed the modification packages and determined the following:
Work requests properly identified the work, approved procedures a.
were being used, activities were being inspected.
b.
Functional testing and calibration was done prior to returning
' systems to an operating status.
Quality control records were adequate, except, the records did c.
not establish that the pressure switch, Square D type 9012 GAW 5, was seismically qualified for its intended use. The pressure switch is mounted on the generator exciter box which is attached to the diesel skid.
This matter is an unresolved
item.
(237-80-01-01; 249/80-01-01).
No items of noncompliance were identified.
Modifications for liigh Pressure Core Injection System and to Meet IEEE 279 Requirements Unit No. I 1.
Reference NRC letter to J. S. Abel, dated August 5, 1974.
The inspector observed partially completed cable trays, suppor+,s, a.
and electrical penetrations and determined the following:
(1) Electrical penetrations were being installed to current drawing revisions and procedures.
(2) Cable trays and supports were being installed to current drawing revisions.
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s (3) The inspector noted there wasn't any clearance between the cable tray supports and the ventilation duct supports.
This matter is an open item and further review is planned.
(10/80-01-01).
(4) Marathon terminal blocks type 6004 DJ-SV and 6012 DJ-SV were being used inside the drywell for connections of the RPS cables. The licensee could not provide documentation to prove that these terminal blocks were environmentally qualified for use inside containment. This matter is an unresolved item.
(10/80-01-02).
b.
The RIII inspector reviewed receiving and qualification records for Class 1E Equipment and '+termined the following:
(1) Franklin Institute Research Laboratories (FIRL) test report F-C3441 dated September 1972, titled " Qualification Test of Limiterque Valve Operators in a Simulated Reactor Containment Post-Accident Steam Environment". Test results included affects of thermal aging simulation, humidity, radiation, pressure, temperature and electrical tests according to IEEE 382 Draft 13, dated June 1972.
(2) Limitorque Corporation test report No. B-0009, titled
" Qualification Type Test Report, Limitorque DC Valve Actua-tors for Nuclear Power Station Service Conditions" dated April 30, 1976. Tests performed per IEEE 382, 323 and 344.
Test results included affects of humidity, pressure temper-ature, radiation, thermal aging and electrical tests.
(3) Okonite test report No. 207600 for cables titled "Qualifi-cation Okoguard Ethylene-Propylene Rubber Insulation for Nuclear Plant Service" dated May 2, 1977. Test results included affects of pressure, temperature, humidity, radia-tion, vertical flame test, moisture resistance and thermal aging.
(4) Samuel Moore Company cables, FIRL test report F-C3683
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titled " Qualification Tects of Electric Cables under Con-ditions Simulating Normal Reactor Containment Service and a Loss of Coolant Accident" dated November 1973. Test results included affects of thermal aging, irradiation, pressure, temperature, steam / chemical spray and electrical tests. Flame tests were conducted by Samuel Moore at their Aurora facilities on June-27, 28, and 29, 1974 ac-cording to IEEE 383, year unknown.
(5) Araconda cables, FIRL test report F-C4350-3 titled " Tests of Electrical Cables Subjected to Thermal Aging, Gamma Radiation, and a Loss of Coolant Accident Simulations"
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dated July 1976. Test results included affects of pres-
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sure, temperature, thermal aging, radiation and electrical test according to IEEE 323-1974 and IEEE 383-1974 for the vertical flame test.
(6) Conax electrical penetrations for the reactor protection systems (RPS).
Conax test report IPS 344 Revision A titled
" Qualification Report". The RIII inspector will complete review of this test report during a subsequent inspection.
(010/80-01-03).
(7) Conax electrical penetrations for the HPCI system. The RIII inspector reviewed Canax Corporation certificate of conformance which states that the electric penetrations furnished on this order (P.O. 227052) meet or exceed the 4.
service conditions of Sargent and Lundy Specificatic.1 No.
K-4037 and IEEE Standard 317-1976, 323-1974, 344-1975.
This item is open pending review of the test report.
(010/80-01-4).
(8) Material receipt records (MRR) for cable pan trays and supports.
Certified material test reports, magnetic particle inspection, heat numbers and related documents.
Note: With respect to the environmental qualification documentation reviewed, no attempt was made to evaluate tests, rather they were reviewed to verify their existence. The NRC will evaluate test results at a later date.
No items of noncompliance were identified.
Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whetner they are acceptable items, items of noncom-pliance, or deviations.
Unresolved items disclosed during the inspection are discussed in " Licensee Action on Previous Inspection
.ndings", and
Paragraphs 2c and la(4).
Exit Interview The inspector met with site staff representatives (denoted in the Persons
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_ Contacted Paragraph) at the conclusion of the inspection on January 9, 1980. The inspector summarized the scope and specific findings of the inspection. The licensee acknowledged the findings.
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DETAILS
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Persons Contacted
- B. Stephenson, Station Superintendent
- B. Shelton, Administrative Services and Support Asst. Supt.
- E. F. Wilmere, QA Coordinator
- R. Dier, Technical Staff Engineer
- G. Reimers, Technical Staff Engineer
- B. Weibeler, Technical Staff Engineer
- J.
Kovic, Substation Construction
- D. Wheeler, Site Construction NRC Resident Inspectors
- J. Barker
- T. Tongue The inspector also talked with several other licensee employees, including members of the technical and engineering staffs.
- Denotes those present at the exit interview.
Licensee Action on Previous Inspection Findings (Closed) Unresolved Item (237/78-23-01; 249/78-25-01) Qualification test results for containment penetration assemblies associated with the ACAD/ CAM System. The RIII inspector reviewed Conax Test Report IPS-420 Revision A titled, " Qualification Report for Electric Penetration Assemblies" dated July 24, 1979. The test was conducted to satisfy the requirements of IEEE Standard 323-1974, 317-1976, and 344-1975. Test conditions appliable included temperature, pressure, radiation, humidity, packaging, electrical and seismic requirements. The inspector has no further questions regarding this item.
(Closed) Unresolved Item (237/78-23-02; 249/78-25-02) - Simplex cable was not environmentally qualified for DBE. The licensee stated that this type of cable was not being used for safety-related equipment located inside the dry well. The RIII inspector has no further questions at this time.
(Open) Unresolved Item (10/78-26-01) - Magnetrol level switches. The licensee has committed to change out non-qualified switches. The RIII inspector will review documentation for these new switches during future routine inspections.
(Closed) Unresolved Item (10/78-26-02) - Instrumentation cable installed in drywell requires environmental qualifications. The licensee is replacing safety-related cables under the modification program to comply with IEEE requirements.
Pefer to Paragraph 4b(4).
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