ML20032D087
| ML20032D087 | |
| Person / Time | |
|---|---|
| Site: | McGuire  |
| Issue date: | 07/21/1981 |
| From: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20032D063 | List: |
| References | |
| 50-369-81-17, NUDOCS 8111130374 | |
| Download: ML20032D087 (4) | |
Text
.
APPENDIX A NOTICE OF VIOLATION Duke Power Company Docket No. 50-369.
McGuire 1 License No. NPF-9 '
As a result of the. inspection conducted on Jum 1-12, 1981, and in accordance with the Interim Enforcement Policy, 45 FR 6644 (October 7,1980), the following violations were identified.
A.
10 CFR 50, Appendix B Criterion V and the accepted Quality Assurance (QA)
Program (DUKE-1-A), Section 17.2.5, require that activities affecting quality shall be prescribed by documented procedures.
The accepted QA Program Table 17.0-1 endorses ANSI-N 18.7-1976. Paragraph 5.2.12 of-this Standard requires that plant procedures shall be reviewed by an individual knowledgeable in the area affected by the procedure no.less frequently than every two years.
Contrary to the above, Station Directives' (SDs) 2.1.3, 2.l.4, 2.4.0, 3.8.0, 3.10.0, 3.1.3, and 3.1.10 have not been reviewed or revised since 8/78, 5/79, 6/78, 3/79, 3/79, 5/77 and 10/77, respectively. These SDs are not intended to be all inclusive.
This is a Severity Level V Violation (Supplement I.E).
B.
10 CFR 50, ' Appendix B Criterion V and the accepted QA Program, Section 17.2.5, require that activities affecting quality shall be prescribed by documented procedures and that these activities shall be accomplished in accordance with these procedures.
1.
Station Directive 4.4.0, Processing Design Changes, Revision 11-dated December 13, 1980, requires that all temporary modifications (jumpers are considered temporary modifications) shall be documented on the work request (WR) and for temporary modifications remaining in place past a shift change, the temporary modification will be identified with a tag.
A jumper was installed during performance of TP/1/A/2600/08, RTD Bypass Flow Verification on INC PG 5310, RTD Bypass Flow Loop A.
Contrary to the above, the jumper observed on -June 3-4, 1981 installed-on INC PG 5310 (RTD Bypass Flow Loop A) was not recorded on WR 83294, and was not tagged.
2.
Station Directive 4.4.0, Processing Design Changes, Revision 11 dated December 13, 1980, requires for removal of temporary modifications, the-individual documenting removal on the work request shall be per-sonally responsible for documenting removal in the log.
8111130374 811104 PDR ADOCK 05000369 G
. - -. - - ~. -.-.-
Duke Power Company 2
Docket No. 50-369 McGuire 1 License No. NPF-9 Contrary to the above, temporary modification tags 0544, 0737, and 0938 associated with work requests 82799, 19339 and 101254, respectively, were completed but not removed from the log.
This is a Severity Level V Violation (Supplement I.E).
I C.
10 CFR 50, Appendix B Criterion V and the accepted QA Program, Section 17.2.5, require that activities affecting quality shall be prescribed by documented procedures and that these activities shall be accomplished in l
accordance with these procedures. The accepted QA Program Table 17.0-1 states that the licensee conforms to Regulatory Guide 1.39 (Revision 1) which endorses ANSI N45.2.3-1973. Station Directives 3.11.0, Housekeeping and Cleanliness, Revision 7 dated April 1981, implements the cleanliness and housekeeping program and states, in part, the following for zone desig-nations of Level III and IV: smoking or use of tobacco products is not permitted; level cleanliness signs shall be posted; garbage, trash, scrap, litter and other excess materials shall be collected, removed from the job site or disposed of in designated areas following acceptance practices; and that for a Level III zone a log shall be maintained at the entrance of the area to log personnel and materials in and out of the area.
Contrary to the above, activities affecting quality were not accomplished in accordance with the approved procedure in that the following items were identified during the inspector's tour of various plant areas on June 10-11, 1981.
1.
Various Level IV cabinets (Cabinets #2, #5, #7, Common HVAC panels) in the control room had cigarette butts, screws, wire scraps, tie wraps, plastic, and miscellaneous other pieces of material in the bottom of the cabinets.
2.
In Cable Room 801 (Level IV) trash, wire brushes, cigarette butts, paper and extra cable were observed in several of the cable trays.
3.
In the fuel pool area (Level IV) trash and cigarette butts were observed on the floor and loose material was being stored in the area.
In addition, the pool was posted as a Level III area and a review of the log indicated that all material and personnel were not being logged in and out of the area.
4.
Fire hoses designated 1RF168, 1RF167, 1RF176, and 1RF163 were not properly stored in their containers in various plant areas.
5.
Work was being performed on Safety Injection Pump 1A and the pump and surrounding area had been designated as a Level III aree The area i
was not cleaned to level requirements prior to initiating work and the log did not contain an accounting of all material in the area desig-nated; however, materials being used by the crafts performing the pump work was controlled properly.
]
Duke Power Company 3
Docket No. 50-369
~McGuire 1~
License No. NPF-9 6.
Welding cables, temporary lines, and cables that had not been terai-nated were being supported by valves, valve handwheels and instrumen -
tation in various plant areas.
7.
Level III and 'IV. areas are being posted, but certain areas did not meet the posting requirements specified in the Station Directive.
This list is not intended to be all inclusive.
-This is a Severity Level V Violation (Supplement I.E).
D.
10 CFR 50, Appendix B Criterion V and the accepted QA Program, Section 17.2.5, requires that activities affecting quality shall be prescribed by documented procedures and that these activities shall be accomolished 'in accordance with these procedures.
Statien Directive 2.4.1, Control of Surface Applied Material Usage, Revision 1, dated August 1979, requires the.
use of a specific type of tace, Tuck 6224, to be used on stainless steel to meet the sulphur and halogen requirements of ANSI N45.2.2.
Contrary to the above, three types of tape not authorized by Station Directive 2.4.1 were in use on quality identified stainless steel pipe located in warehouse 5 on June 5,1981.
This is a Severity Level VI Violation (Supplement I.F).
E.
10 CFR 50, Appendix B Criterion V and the accepted QA Program, Section 17.2.5, requires that activities affecting quality shall be prescribed by-documented procedures and that these. activities shall be accomplished in accordance with these procedures. Administrative Policy Manual (APM) for nuclear stations, Section 2.2.3.5,. Revi sion 18, dated Septembar 1979, states in part that records shall be stored such that they are protected from possible destruction and that the storage facilities shall meet the NFPA 232-1975 criterion using as a minimum one hour fire rated cabinets.
Section 2.2.3.6.1(b) of the APM states, in part, that qualifications and training records shall be retained.
Contrary to the above, records for certifying individuals to apply for an NRC Senior Operator license are being stored in a cabinet which does not meet the one hour fire rating requirement of NFPA 232-1975.
This is a Severity Level VI Violation (Supplement I.F).
Pursuant to the provisions of 10 CFR 2.201, you-are hereby required to submit to this office within thirty days of the date of. this Notice, a written statement or explanation in reply, including: (1) admission or denial of the alleged viola-tions; (2) the reasons for the violations if admitted; (3) the corrective steps which have been taken and the results achieved; (4) corrective steps which will
e Duke Power Company 4
Docket No. 50-369 McGuire 1 License No. NPF-9 be taken to avoid further violations; and (5) the date when full compliance will be achieved. Consideration may be given to extending your response time for good cause shown.
Under the authority of Section 182 of the Atomic Energy Act of 1954, as amended, this response shall be submitted under oath or affirmation.
_jdl b k Date:
-