ML20207T833
| ML20207T833 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 03/03/1987 |
| From: | Reyes L NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20207T814 | List: |
| References | |
| 50-324-87-02, 50-324-87-2, 50-325-87-02, 50-325-87-2, NUDOCS 8703240373 | |
| Download: ML20207T833 (3) | |
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ENCLOSURE 1 NOTICE OF VIOLATION Carolina Power and Light Company Docket Nos. 50-325 and 50-324 Brunswick 1 and 2 License Nos. DPR-71 and DPR-62 During the Nuclear Regulatory Commission (NRC) inspection conducted on January 1-31, 1987, violations of NRC requirements were identified.
The violations involved an inadequate procedure for responding to a control room high chlorine alarm, failure to have Control Rod Drive (CRD) pipes supported in accordance with piping specification, and failure to follow procedures for installation of motor-operated valve anti-rotation devices. In accordance with the " General Statement of Policy and Procedure for NRC Enforcement Actions," 10 CFR Part 2, Appendix C (1985), the violations are listed below:
b 1.
Technical Specification (TS) 6.8.1.a, requires written procedures be
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established for procedures in Appendix A of Regulatory Guide 1.33, 1
November, 1972. Item E of Appendix A of Regulatory Guide 1.33, November 1972, requires procedures for correcting abnormal, off normal or alarm conditions. Annunciator procedure APP-UA-28, 5-1, provides a procedure for manually isolating the control room if automatic isolation fails to occur on a detected high chlorine condition.
Contrary to the above, written procedure APP-UA-28, 5-1, required by TS 6.8.1.a and Appendix A of Regulatory Guide 1.33, was inadequately estab-lished, in that the steps provided to manually isolate the control room would not isolate the control room, resulting in the makeup air damper remaining open when manual isolation was initiated on December 31, 1986.
This is a Severity Level V violation (Supplement I) applicable to Unit 1 and Unit 2.
2.
10 CFR 50, Appendix B, Criterion V, as implemented by FSAR Chapter 17.2.5, Instructions, Procedures and Drawings, requires that activities affecting quality shall be accomplished in accordance with approved procedures.
Installation of open type pipe clamps on safety related CRD pipes is an activity affecting quality.
Approved procedure BSEP 248-107 installs these clamps and requires specific tolerances on open type pipe clamps.
Contrary to the above, activities affecting quality were not accomplished in accordance with approved procedures, in that as of January 9,1987, tolerances associated with open pipe clamps on the CRD system safety related piping inside the drywell exceeded the 1/8" tolerance as specified in BSEP 248-107.
In addition, five open type clamps were found missing.
This is a Severity Level IV violation (Supplement I) applicable to Unit 2.
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HbE O 3 1987 Carolina Power and Light Company 2
Docket Nos. 50-325 and 50-324 Brunswick I and 2 License Nos. OPR-71 and DPR-62 3.
10 CFR 50, Appendix B, Criterion V, Instructions, Procedures, and Drawings, requires that activities affecting quality shall be accomplished by documented instructions and procedures.
The Corporate Quality Assur-ance Program, section 13.4.3, Work Execution, implements Criterion V with respect to maintenance control.
Subparagraph 13.4.3.1 requires that Q-list plant item maintenance shall be accomplished as prescribed in maintenance procedures and instructions.
a.
MI-16-503J, Anchor (Pressure-Seal) Globe Valves Maintenance Instruc-tion, step III.D.18, requires placement of a key in the valve stem.
Contrary to the above, activities affecting quality were not accomp-lished as prescribed in maintenance procedures and instructions in that the key was not replaced in valve 1-E41-F012 during anti-rota-tion device reassembly under work request 1-M-84-4007, completed September 12, 1985.
The licensee found the key missing during an inspection conducted under work request 87-ABNR1, completed January 17, 1987.
b.
MI-16-503J, step III.D.17, requires drilling of an indentation in the valve stem to be aligned with a set screw.
Contrary to the above, activities affecting quality were not accomplished as prescribed in maintenance procedures and instructions in that the valve stem was drilled with an indentation not lined up for the set screw in valve 2-E51-F022 under work request 83-AAEF1, completed April 24, 1986. The licensee found the incorrectly drilled stem after the valve failed to shut on January 5, 1987, c.
Work request 85-AAPJ1 required replacement of a key in the valve stem of valve 2-E51-F045.
Contrary to the above, activities affecting quality were not accomplished as prescribed in maintenance procedures and instructions in that the key was not replaced in valve 2-E51-F045 during anti-rotation device reassemble conducted on February 4,1986.
The licensee found the key missing during an inspection conducted under work request 87-AAPJ1, completed January 31, 1987.
This is a Severity Level IV violation (Supplement I) applicable to Unit 1 and Unit 2.
Pursuant to the provisions of 10 CFR 2.201, Carolina Power and Light Company is hereby required to submit to this office within thirty days of the date of the letter transmitting this Notice, a written statement or explanation in reply, including (for each violation): (1) admission or denial of the violation, (2) the reasons for the violation if admitted, (3) the corrective steps which have been taken and the results achieved, (4) the corrective steps which will be l
Malt 0 31987 Carolina Power and Light Company 3
Docket Nos. 50-325 and 50-324 Brunswick 1 and 2 License Nos. DPR-71 and DPR-62 taken to avoid further violations, and (5) the date when full compliance will be achieved.
Where good cause is shown, consideration will be given to extending the response time.
FOR THE NUCLEAR REGULATORY COMMISSION 1
Luis A. Reyes, Director Division of Reactor Projects Dated at Atlanta, Georgia this day of 1987 i
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