IR 05000341/1979024
| ML19257D737 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/18/1979 |
| From: | Julie Hughes, Jablonski F, Knop R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III) |
| To: | |
| Shared Package | |
| ML19257D730 | List: |
| References | |
| 50-341-79-24, NUDOCS 8002060012 | |
| Download: ML19257D737 (7) | |
Text
U.S. NUCLEAR REGULATORY COMMISSION
.
OFFICE OF INSPECTION AND ENFORCEMENT
REGION III
Report No. 50-341/79-24 Docket No. 50-341 License No. CPPR-87 Licensee: Detroit Edison Company 2000 Second Avenue Detroit, MI 48226 Facility Name: Enrico Fermi Nuclear Station, Unit 2 Inspection At: Fermi Site, Monroe, MI Inspection Conducted: November 27-29, 1979 di c &yf, 12.[g[79
Inspereors:
F. J. Jablonski J. Hughe l
D mc Approved By:
R. C. Knop, Chief I 2, P
Project Section 1 Inspection Summary Inspection on November 27-29, 1979 (Report No. 50-341/79-24)
Areas Inspected: Follow-up of previously identified noncompliances/ unresolved items; 50.55(e) reports; independent inspection; electrical work activities; electrical records. The inspection involved 40 inspector-hours onsite by two NRC inspectors.
Results:
Of the fi n areas inspected, one item of noncompliance was identi-fied.
(Infractiot. - failure to review the design of components, limit switches, to accomodate accident environments.
Program areas - Paragraph 5).
1927 079 8002 06 OOP
DETAILS Persons Contacted Detroit Edison Company
- T.
Alessi, QA Director
- G. Carter, QA Engineer W. Fahrner, Project Manager
- E. Hines, Assistant Vice President QA
- H. Tauber, Vice President Engineering and Construction
- A. Walker, Site Project QA Engineer Daniel International Corporation
- M. Albertin, Assistant Program Manager
- J. Blixt, QC Manager
- J. Bolt, QA Manager
- D. Siefert, Project Manager
- Denotes those attending the exit interview.
Licensee Activn on Previous Inspection Findings (Closed) Noncompliance (341/79-14-03): Walbridge Aldinger QA program evaluation. Corrective action was examined during a previous inspection, 341/79-22, and determined to be in accordance with DECO's letter to NRC, dated August 24, 1979.
(Closed) Noncompliance (341/79-14-05):
Identification of vertical cable trays. The RIII inspector examined the following cable trays for proper identification markers; 2P039, 2P074, 2C070, and 20071.
Corrective action was in accordance with DECO's letter to NRC dated August 24, 1979.
(0 pen) Unresolved Item (341/79-14-02):
Items 1.b, motor operated valves, and 1.c, containment cooling for motors, remain open.
Item 1.a, limit switches is being upgraded to a noncompliance as descirbed in paragraph 5 of Program Areas inspected.
Note: Motor operated valves suitable for use inside containment should have class RH motor insulation; all geared limit and torque switch materials should be made of gray or brown melamine. Outside containment, motors have class B insulation and red / black insulator material. All must be qualified for seismic events.
1927 080-2-
.
Licensee Action on Bulletins and Circulars
.
1.
Bulletin 79-15 Deep draft pump deficiencies. The licensee's response to this Bulletin dated August 16, 1979 required further clarification and was so notified by telephone on October 1, 1979. The subsequent response dated October 25, 1979 was deemed adequate. During this inspection, the following points were verified.
The core spray and residual heat removed pumps are single stage,
.
not deep draft.
Deep draft pumps manufactured by Goulds are installed and provide service water for residual heat removal, emergency equipment and the diesel generator.
The pumps were manufactured under a QA program meeting the require-
.
ments of ASME Section III; the pump name plate carried the appropri-ate N stamp.
Drawings, sectional ar emblies and parts lists were available.
.
Only shop tests have been performed.
.
No preop tests have been performed.*
.
No maintenance data has been accumulated.*
.
Pump alignment is controlled within 1 0.003 inches; process
.
travellers provide a permanent record of shaft alignment.
- Results of tests performed during preoperational testing and operations shall be reviewed when applicable. Detailed history of pump maintenance will be reviewed when applicable. The above activities are typically performed by the operations section of IE-RIII.
The inspector has no further questions.
2.
Bulletin 79-23 Potential failure of emergency diesel generator (EDn) field exciter transfo rmer. The licensee's response to this bulletin dated October 23, 1979 stated that wye connected exciter power supply transformers were installed thus susceptibility '.o third harmonic induced circulating currents was not pres at.
Based on interviews with site personnel and the drawings provided to the inspector, the type of transformer and connection installed could not be substantiated. Based on telecon with DECO engineering on December 7, 1979, it was determined that the trans-former is ungrounded. This matter is unresolved. (341/79-24-01).
1927 081-3-
.
3.
Circulars 79-04, 79-05, 79-11, 79-12, 79-13
.
hotor operated lock nuts, moisture leakage in cable, design /construc-tion interface, diesel generator turbocharger, diesel fire pump contactor.
Memoranda on file were reviewed. The circulars had been received, reviewed and corrective action, where necessary, was included. At this time, the inspector has no further questions.
No item: of noncompliance were identified.
Other Inspection Areas 10 CFR 50 Section 50.55(e) Reportable Deficiencies (Closed) 78-XX-07 Defective Kulka terminal blocks supplied by Conax Corporation for drywell electrical penetrations. The RIII inspector reviewed Conax test report IPS-465 Revision A titled, " Design Qualification Report of Terminal Blocks" dated November 8, 1979. The test was conducted to IEEE Standard 317-1972 and Regulatory Guide 1.63, October, 1973. Tests included temperature, pressure, humidity, radiation, and electrical tests. The inspector has n; further ques-tions regarding this item.
Note: IEEE Standard 317-72 does not include aging.
10 CFR Part 21 Reportable Items (Closed) Defective Kulka terminal blocks supplied by Conax Corporation. See the preceeding paragraph.
Program Areas Inspected 1.
Observation of Electrical Work Activities The inspector observed completed or partially completed installation a.
of the following motor operated valves located outside the drywell.
MOV-V8-2100 MOV-V8-2153 MOV-V8-2136 MOV-V8-2156 MOV-V8-2154 b.
The inspector observed the following cable terminations for the above motor operated valves:
cable #214402-2C to end cable #214432-2C to end cable #214390-1C to end cable 214262-2C to end cable #214224-2C to end-4-1927 082
,
The following termination characteristics were in accordance with
-
the current cable pull cards and procedures.
Cable supports, color / numeric code, crimped ligs, conductors identified, separ-ation criteria maintained, properly dressed cond.ctors, and tight connections.
c.
The inspector observed the following cable terminations for the emergency diesel generator control panels, located in the RHR building:
cable #25606-1C cable #356505-1C cable 256576-1C cable #256579-1C cable #256578-IC cable #256582-1C cable #220577-1C cable #220578-1C
-
cable #220584-1C Characteristics included color / numeric code, crimped lugs, con-ductors identified, separation criteria maintained, properly dressed conductors, and tight connections.
The cable terminations had not been QC inspected.
d.
The inspector observed high potential testing of power cable
- 2000081P. The testing was done in accordance with procedure CAIO.000.016 revision 2 dated April 24, 1979.
The test identi-fied no problems with the cable.
-
No items of noncompliance were identified.
2.
Observation of Instrumentation Work Activities a.
The inspector observed partially installed sensing lines (tubing)
in accordance with installation drawing 6WI-G11-70301-1. The tubing lines had not been QC inspected. During review of design specifi-cations 3071-31 and 3071-525 for Instrumentation and Control Piping and Tubing, the inspector could not determine the exact acceptance criteria for the installation of safety-rela tubing. This matter is unresolved. (341/79-24-02)
b.
The inspector observed installed instrument air system lines, located in the reactor building.
Smallbore piping was installed in accordance with the most current drawings and design change notices.
No items of noncompliance were identified.
1927 083-5-
.
3.
Electrical-Review of Quality Records
a.
The inspector reviewed the following records concerning the cable terminations address in paragraph 1:
(1) Cable Pull Cards and Cable Pull Checklists (L. K. Comstock Form #37)
(2) Ele-ctrical Termination Inspection Checklist (L. K. Comstock Form #36)
b.
The records identified the inspector, the type of observation, the governing documents, the results, the acceptability, and action taken with noted deficiencies. The records were identifiable and retrievable.
No items of noncompliance were identified.
4.
Instrumentation - Review of Quality Records The inspector reviewed calibration and relay setting records to a.
confirm that proper calibration and relay settings were made as specified, including use of procedures and test equipment. Records were identifiable and retrievable.
b.
The inspector reviewed control and power metering cables EF2 C&IE continuity and insulation resistance test form TF.000.017.01 revision 1.
The test form included the following:
test procedure no., cable no., location, reference drawings, test equipment number and recalibration. date, sigc?tures for verification sign off during testing, and signat ure of test engineer's review for acceptance.
Records were identifiable and retrievable.
No items of noncompliance were identified.
5.
Other Areas Namco type SL-CB2W limit switches for the Main Steam Isolation Valves (MSIV) were not environmentally qualified for service inside the contain-ment. The inspector was informed by the licensee that the limit switches were for position indication only. FSAR Section 2.2.1.1.3. states in part,
" Position switches mounted on the eight MSIV's signal closure to the RPS logics." This item is considered to be in noncompliance with the require-ments of 10 CFR 50, Appendix B, Criterion II as described in Appendix A of this report.
(341/79-24-03)
6.
Pump process Traveler Travellers for the RHR and CS pumps were reviewed.
Several potential problems exist as follows:
-6-1927 084
.
'
Wo by title has responsibility for checking the technical
.
content.
Wy isn't the instruction book number included.
.
Why aren't precautions included.
.
Why isn't the torque wrench control number included.
.
Wy is seismic marked N/A.
.
Why isn't criteria listed for installation of the hydrostatic
.
bearing chamber gasket.
Why aren't criteria and precautions listed for dimensional
.
checks for the thrust disc.
Why isn't tl.e instruction book and/or criteria listed for
.
installation of the mechanical seal.
Why isn't a procedure or criteria listed for final acceptance
.
inspection.
Why aren't changes such as DCR's, DCN's, FMR's, FDDR;s, FDI's,
.
etc. verified to be completed, incorporated, etc.
Note: The pumps have not been installed. This matter is unresolved.
(341/79-24-04)
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 under Bulletins, Paragraph 2, and Program Areas, Paragraphs 2.a, and 6.
Exit Interview The inspectors met with site staff representatives (denoted in the Persons Contacted paragraph) at the conclusion of the inspection.
The inspectors summarized the scope and findings of the inspection. The licensee acknowl-edged the findings.
~'~
1927 085