IR 05000324/1980018
| ML19347B794 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 07/25/1980 |
| From: | Conlon T, Hardwick R NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML19347B787 | List: |
| References | |
| 50-324-80-18, 50-325-80-21, NUDOCS 8010150671 | |
| Download: ML19347B794 (5) | |
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'o UNITED STATES
NUCLEAR REGULATORY COMMISSION 3.,,.,-
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"'/.. E REGION 11 I-
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- Av [of 101 MARIETT A ST., N.W., Sulf E 3100 o,,
e ATLANTA, GEORGIA 30303
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i Report Nos. 50-324/80-18 and 50-325/80-21 Licensee: Carolina Power & Light Company
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411 Fayetteville Street i
Raleigh, NC 27602 j
Facility Name: Brunswick Steam Electric Plant Docket Nos. 50-324 and 50-325
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License Nos. DPR-62 and DPR-71 Inspection at Brunswick site near Southport, North Carolina
Inspector: W gf h h
7.!2f'80 R. J. Hardwick, Jr.
Date Signed
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Approved by:
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T. E. Conlon, Section' thief, RCES Branch Date Signed
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SUMMARY Inspection on May 28-30, 1980 and June 9-12, 1980 AreasInspecte[1 This special, announced inspection involved 47 inspector-hours onsite in the of-installed electrical equipment review with respect to the IE Bulletin area 79-01B response.
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Results Of the area inspected, one item of noncompliance was found (Infraction 325/80-21-04, Failure to follow Maintenance Instruction MI 31-4, " Termination of Elec-trical Cables and Internal Wiring").
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DETAILS 1.
Persons Contacted
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Licensee Employees A. C. Tollison, General Manager
- J. M. Brown, Operations Manager G. T. Milligan, Maintenance Manager
- J. T. Parlier, Chief Projects Engineer
- D. N. Allen, QA Supervisor
- M. D. Mason, Plant Engineer
- D. E. Moore, Engineering Technician Other Organizations United Engineers and Constructors, Inc.
C. D. Greiman, Electrical Engineering Supervisor S. Rubin, Electrical Engineer
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R. D. Magouirk, Project Supervisor NRC Resident Inspector
- J. E. Ouzts M. D. Davis
- Attended exit interview
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Exit Interview The inspection scope and findings were summarized on June 12, 1980 with those persons indicated in Paragraph I above. Deficiency 325/80-21-04, Failure to fol) aw Maintenance Instruction MI 31-4,
" Termination of Electrical Cable 3 and Internal Wiring", was discussed in detail.
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Licensee Action on Previous Inspection Findings Not inspected.
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Unresolved Items Unresolved items were not identified during this inspection.
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IE Bulletin 79-01B A physical examination was made of installed electrical instrumentation and control equipment associated with the Nuclear Boiler (B21) system. All equipment that was examined is located inside the dry well. The environ-mental qualification docuanentation review for this equipment will be performed during a future inspection. The specific equipment examined is listed below:
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Unit 1 Instrument or Component No.
and Description Cable No.
B21-F013F, Solenoid Valve 1-KbO-QC3 B21-F013G, Solenoid Valve 1-KDI-QC8 J
B21-F013H, Solenoid Valve 1-KD2-QC8
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B21-F013J, Solenoid,alve 1-KD3-QD2
321-F022A, Solenoid Valves 1-KD4-QA0, QA6, QA9, QA0/1
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B21-F022B, Solenoid Valves 1-KD5-QAO, QA0/1, QA6, QD2 B21-F022C, Solenoid Valves IKD6-QA1, QA9, QC3, QA1/1 B21-F022D, Solenoid Valves IKD7-QA1, QC3, QD2, QA1/1 E51-F007, Valve Operator 1-KS8-QB3, QB3/1, QB3/2 E41-F002, Valve Operator
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QB3, Electrical Penetration QB5, Electrical Penetration
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QCO, Electrical Penetration
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B21-F021A, Limit Switches
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B21-F022B, Limit Switches
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B21-F022C, Limit Switches
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B21-F022D, Limit Switches
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Unit 2
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Instrument or Component No. and Description Cable No.
B21-F013C,' Solenoid Valve
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B21-F013F, Solenoid Valve 2-KD0-QC3 J
B21-F013G, Solenoid Valve 2-KDI-QC8
B21-F013H, Solenoid Valve 2-KD2-QC8 B21-F013J, Solenoid Valve 2-KD3-QD2 B21-F022A, Solenoid Valves 2-KD4-QA0, QA0/1, QA6, QA9 B21-F022B, Solenoid Valves 2-KD5-QA0, QA0/1, QA6, QD2 B21-F022C, Solenoid Valves 2-KD6-QA1, QA1/1, QA9, QC3 B21-F022D, Solenoid Valves 2-KD7-QA1, QA1/1, QC3, QD2 E51-F007, Valve Operator 2-KS8-QB3, QB3/1 E41-F002, Valve Operator
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QB3, Electrical Penetration
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QB5, Electrical Penetration
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QCO, Electrical Penetration
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QA1, Electrical Penetration
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B21-F022A, Limit Switches
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B21-F022B, Limit Switches
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B21-F022C, Limit Switches
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B21-F022D, Limit Switches
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A review of the 45-day response to the Bulletin has identified three areas where additional information or clarification is necessary. These areas are listed below:
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Section IV, Part 2, Note K, Figure 3 Note K indicates thr'. Figure 3 should be used as the qualification test profile for temperature per document 29.
However, Figure 3 provides no temperature data.
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Section VII, Page 2, General Comment 3 This comment states that Boston Insultated Wire and Cable Company (BIW) instrument cable does not " meet or exceed the specified require-ments". Also, specific cable test data is given. 1 sing the information provided, the basis for qualification acceptance is not evident.
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Section VII, Page 2, General Comment 4
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This comment states in part that those terminations whose
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proximity to one another could cause an electrical failure 'will be modified such that they can be considered as qualified". There is no information provided that identifies what the modification will be or
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why they can be considered qualified.
These thr. : items were discussed with the licensee and the inspector agreed that the additional information may be provided in the 90-day response to the Bulletin. This is identified as Inspector Follow-Up Item 324/80-18-01 and 325/80-21-01, Clarification of IE Bulletin 79-01B 45-day response.
During the Unit 1 and 2 electrical penetration assembly (EPA) inspec-tions, it was noted that most penetrations had cover screws missing.
When discussing this problem with respect to environmental integrity, the licensee stated that they had previously identified this item and were currently obtaining replacement cover screws. Maintaining equipment environmental integrity is a major concern of the NRC. This item is identified as Inspector Follow-Up Item 324/80-18-02 and 325/80-21-02, Missing electrical penetration cover screws.
Examination of the electrical connections of solenoid valves B21-F013H and B21-F013J in Unit 2, revealed a termination method which is not addressed in the 45-day response to the Bulletin. After discussions with the licensee and architect-engineer (AE) personnel, the licensee determined that the electrical connections were not environmentally qualified. Licensee Event Report (LER) Namber 2-80-46 was issued on June 12, 1980 to report that safety relief valves B21-F013 (A-L) on both Unit I and 2 were notenvironnmentally qualified.
Examination of the installed cable :.nd conduit runs for the above listed solenoid valves and limit switches revealed the use of cable termination boxes. These termination boxes are not addressed in the 45-day response to the Bulletin. The licensee identified these terminal boxes as being part of the Nuclear Steam Supply (NSS) equipment package
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Inclusion of the terminal boxes in the 90-day response is identified as Inspector Follow-up Item 324/80-18-03 and 325/80-21-03, Environmental quali-fication of terminal boxes.
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While inspecting 480 volt electrical penetration assembly (EPA) number QC0 in Unit 1, it was noted that 17 feed-thru penetration leads were not connected to the penetration terminal boards. These leads were l
lugged, tagged with lead identification numbers, and lying loose on the bottom of the penetration. The current wiring diagrams (Drawing Nos. FP-9527-3495 and FP-9527-3499) for this EPA showed the discon-
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nected leads as spare leads and terminated on spare terminal board points. A review of Maintenance Instruction number MI 31-4, "Termina-
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l tion of Electrical Cables and Internal Wirang", revealed that mainten-l ance personnel are required to use the most recent revised drawing /
i documentation to terminate electrical cables. This item is an infraction j
and is identified as 325/80-21-04, Failure to follow Maintenance Instruction i
MI 31-4, " Termination of Electrical Cables and Internal Wiring".
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