IR 05000369/1982018
| ML20058C117 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/28/1982 |
| From: | Belisle G, Fredrickson P, Upright C NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
| To: | |
| Shared Package | |
| ML20058C075 | List: |
| References | |
| 50-369-82-18, 50-370-82-13, NUDOCS 8207260263 | |
| Download: ML20058C117 (2) | |
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o UNITED STATES g
NUCLEAR REGULATORY COMMISSION
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E REGION 11
o 101 MARIETTA ST., N.W., SUITE 3100 ATLANTA, GEORGIA 30303 o
July 2, 1982 Report Nos. 50-369/82-18 and 50-370/82-13 Licensee: Duke Power Company 422 South Church Street Charlotte, NC 28242 Facility Name: McGuire 1 and 2 Docket Nos. 50-369 and 50-370 License Nos. NPF-9 and CPPR-84 Inspection at McGuire site near Charlotte, NC Inspectors: [
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6 28[8C G.A.Belisleg Sate signed Ag; L[W M'<
6Aeke P. E. Fredricpn /
/Date 6igned Approved by:_ dM/
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C. M. Upright.,Sy'ctiojrv hief IDate/ Signed Engineering Irptecti6h Branch Division of Engineering and Technical Programs SUMMARY Inspection on June 7-11, 1982 Areas Inspected This routine, unannounced inspection involved 46 inspector-hours on site in the
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areas of licensee action on previous enforcement matters, design changes and modifications. 0A program review, the nonroutine reporting program, upper RHR heat exchanger fasteners, and licensee action on previously identified inspection findings.
Results Of the six areas inspected, no violations or deviations were identified.
8207260263 820702 PDR ADOCK 05000369 G
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REPORT DETAILS
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Persons Contacted
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Licensee Employees
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- E. Estep, Project Engineer
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s G. Gilbert, Operating Ensineer
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D. Harrington, Training aid Safety Coordinator N
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- D. Lampke, Assistant Engineer
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- M. McIntosh, Station Manager
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M. Mills, Materials Coordinator T. Parker, Training Coordinator T. Ryan, Support Engineer
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B. Travis Operating Engineer
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Other licensee employees contacted included technicians, operators. and office personnel.
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- Attended exit interview
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2.
Exit Interview
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The inspection scope and findings were summarized on June 11, 1982, with those persons indicated in paragraph 1 above. The licensee acknowledged the _
inspection findings.
3.
Licensee Action on Previous Enforcement Matters (92702)
The following items from Inspection Report N6s. 50-369/81-17 ano~370/81-05 were reviewed with respect to licensee correspondence dated August 20, September 30. and October 23, 1981.
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a.
(Closed). Violation (369/81-17-01):
Failure to' Review Plant Procedures.
The inspector verified that the licensee has established a system for review of station directives. The reviews are scheduled as part of the computerized program which handles periodic surveillances and calibra-tions.
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b.
(Closed) Violation (369/81-17-02):
Failure to Control. Temporary (
Modification Installation and Failure to Document Temporary Modi fica-tion Removal.
The inspector verified that the licensee has completed
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the specific corrective actions relative to these items.
c.
(Closed) Violation (369/81-17-03):
Failure to Establish and Maintain Cleanliness Requirements.
Based on discussions with the NRC resident inspector, who has reviewed the plant's housekeeping condition, the inspector determined that this item has been corrected.
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d.
(Closed) Violation (369/81-17-04):
Failure to Use Approved Tape on Quality Stainless Steel Piping. The inspector toured the warehouse and observed the tape display board showing the approved tapes to be used s
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to meet ANSI N45.2.2 requirements.
Warehouse personnel were also
. interviewed to verify knowledge of this tape requirement and that the approved tapes were on hand, e.
,(Closed) Violation (369/81-17-05): Failure to Properly Store Training Records.
The inspector reviewed the storage of training records, A
particularly the licensed operator qualification material.
A micro-s fiche program is now in effect for the storage of this qualification information. All other training type information is stored in adequate fire protected cabinets.
4.
Unresolved Items Unresolved items were not identified during this inspection.
5.
Design Changes and Modifications (37700 and 37702)
References:
(a) APM, Section 3.4, Modifications, Revision 16 (b) APM, Section 4.4, Administrative Instructions for Modifications, Revision 19 (c) APM, Appendix E, Design Process Guidelines, Revision 19 (d) SD 4.4.0, Processing Design Changes, Revision 10 (e) SO 4.4.1, Processing Nuclear Station Modifications, Revision 3 (f) SD 4.4.2, Control of Temporary Modifications s
(g) CQAP, Chapter 3, Design Control, Revision 0
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(h) PR-160, Nuclear Station Modification, Revision 1 (1) 'QA-506, Quality Assurance Review of Nuclear Station Modifications / Nuclear Problem Reports, Revision 5 The inspector reviewed the references to verify that they met requirements of the accepted QA Program and ANSI N45.2.11 as 2ndorsed by that program.
The inspector verified the following aspects of the design change program:
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Procedures have been established for control of design and modification
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change requests.
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Procedures and responsibilities for design control have been estab-
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lished.
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Administrative controls for design document control have been estab-lished.
- - Administrative controls assure that design changes are incorporated into plan't procedures, operator training, and plant drawings.
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Controls have been developed that define channels of communication between design and responsible organizations.
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Administrative controls require that design documentation and records be collected and stored.
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Controls require that implementation of approved design changes be in accordance with approved procedures.
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Responsibility has been assigned for identifying post-modification testing requirements.
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Controls require that post-modification testing be performed per approved test procedures and that the results be evaluated.
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Responsibility and method for reporting design changes to the NRC in accordance with 10 CFR 50.59 has been identified.
Similar methods and controls were also verified for use of temporary modifications (jumpers and disconnected leads).
In order to verify implementation of the program, the inspector reviewed four plant change /
modifications (MS 00695, 00109, 00254, and 00439) against the procedural requirements.
Based on this review, no violations or deviations were identified.
6.
QA Program Review (35701)
References:
(a) Duke Power Company QA Program, Duke 1-A, Amendment 5 (b) QA 100, Preparation and Issue of Quality Assurance Procedures, Revision 6 (c) QA 101, Quality Assurance Records Storage Vault (General Office), Revision 3 (d) QA 112, Certification of Quality Assurance Analysts, i
Revision 2 (e) QA 130, Qualifications and Training of Lead Auditors, Revision 7 (f) QA 150, Trend Analysis, Revision 3 (g) QA 160, Performance of Corporate Quality Assurance Audits, Revision 0 (h) QA 410, Processing of QA Records for Purchased Items, Revision 7 (i) QA 501, Placing, Reviewing and Verifying Quality Assurance Requirements on Station Procedures, Revision 4 (j) QA 504, Quality Assurance Records, Operations, Revision 9 (k) QA 506, Quality Assurance Review of Nuclear Station Modifications / Nuclear Problem Reports, Revision 5 (1) QA 510, Quality Assurance Review of Station Work Request, Revision 4
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The inspector reviewed the references and verified that they met require-ments of the accepted QA Program and ANSI standards endorsed by that program. The inspector verified by questioning licensee personnel that they understand changes made to the QA program.
Based on this review, no violations or deviations were identified.
7.
Nonroutine Reporting Requirements (90714)
References:
() QA 121, Nuclear Regulatory Commission Reporting Requirements, Revision 4 (b) APM, Section 2.8, Reporting, Revision 19 (c) APM, Section 4.9, Operating Experience Evaluation Program, Revision 19 The inspector reviewed the references and verified the following aspects of nonroutine reporting:
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Administrative controls have been established for prompt review and evaluation of off-normal events to assure identification of safety related events.
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Admini strative controls have been established for reporting safety related events internally and to the NRC.
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Administrative controls have been established for completion of corrective actions relating to safety related operating events.
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Administrative controls contain provisions for recognition and reporting of events covered by 10 CFR Part 21.
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Administrative controls have been established for prompt review and evaluation of vendor bulletins and circulars.
Based on this review, no violations or deviations were identified.
8.
Upper RHR Heat Exchanger Fasteners (92706)
The inspector assisted the resident inspector in evaluating the omission of upper fasteners on Unit 1 RHR heat exchangers.
The omission was discovered by the licensee on June 7 and reported to the NRC on June 8, 1982. Details of this event will be adoressed in the resident inspector's monthly report.
9.
Licensee Action on Previously Identified Inspection Findings (92701)
a.
(Closed) Open Item (369/78-39-10):
Approval of Revisions to Design Changes.
The inspector reviewed APM Section 3.4, Modifications, Revision 16, and Section 4.4, Administrative Instructions for Modifica-tions, Revision 19, and verified that the latter procedure delineates actions to be taken by the licensee in making revisions to plant
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5 modifications and also addresses reviews to be made by groups processing these revisions, b.
(Closed) Open Item (369/78-39-11): Establishment of External Interface and Communications Documentation.
The inspector reviewed APM Section 4.4, Administrative Instructions for Modification, Revision 19. and verified adequate interf ace and communication documentation requirements.
c.
(Closed) Open Item (369/78-39-12):
Design Input Information.
The inspector reviewed APM Section 4.4, Administration Instructions for Modifications, Revision 19, and verified that this procedure delineates design inputs to be considered by the licensee when developing design modifications.
The inspector also reviewed APM Appendix E. Design Process Guidelines, and verified that this appendix supplements Section 4.4 relative to specific design inputs, final design summaries, verification and approval of designs, and design analyses.
d.
(Closed) Open Item (369/78-39-02): Equipment Trend Analysis Program.
The inspector reviewed Maintenance Management Procedure 4.2, Revision 0, and Station Directive 2.3.0, Control of Measuring and Test Equip-ment, Revision 9, and determined that a system to detect maintenance trends in test equipment has been developed and that an expansion to all safety related plant equipment is in the planning stage.
e.
(Closed) Inspector Followup Item (369/79-36-01): Record of Technician Occupational Training. The inspector reviewed several personnel files and determined that technical skill qualifications are now being adequately documented.
f.
(Closed) Open Item (369/81-17-07, 370/81-05-07): Conflict of Calibra-tion Frequency in Administrative Procedure for Measuring and Test Equipment. Station Directive 2.3.0, Revision 9, has been clarified to cover the use of the one week " grace period" for test equipment calibrations.
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(Closed) Open Item (369/81-17-08, 370/81-05-08): Retraining Time Frame Not Specified.
Station Directive 2.5, Revision 5, has incorporated periodicity for each area taught under the general employee training program.
h.
(Closed) Open Item (370/81-05-09): Failure to Review Plant Procedure.
This area is discussed in paragraph 3.a.
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(Closed) Open Item (370/81-05-10): Use of Unapproved Tape on Quality Identified Stainless Steel Piping. This area is discussed in paragraph 3.d.
j.
(Closed) Open Item (370/81-05-11):
Improper Storage of Training Records. This area is discussed in paragraph.
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(Closed) Inspector Followup Item (369/81-17-12): Temporary Modifi-cation Control After Unit Licensing. The inspector reviewed SD 4.4 2, Control of Temporary Modifications, Revision 1, and verified that the licensee has delineated positive controls for temporary modifications af ter unit licensing.
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(Closed)
Inspector Followup Item (369/81-17-13, 370/81-05-13):
Conflict In Use of Should and Shall (Variation Notices). The inspector reviewed SD 4.4.1.
Processing Nuclear Station Modifications, Revision 4 and verified that conflicts between should and shall have been corrected.
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(Closed)
Inspector Followup Item (369/81-17-14, 370/81-05-14):
Conflict in Use of Should and Shall (Records Storage).
Station Directive 2.1.1, Revision ll, has been changed to reflect the proper terminology.
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(Closed) Inspector Followup Item (369/81-17-16, 370/81-05-16): APM and Technical Specification Inconsistencies.
The NSRB Charter and Technical Specifications agree with respect to numerical quorum requirements.
The APM requires a majority instead of a specific minimum number for a quorum in order to address both the Oconee and McGuire NSRBs.
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(Closed) Inspector Followup Item (369/81-17-17, 370/81-05-17):
NSRB Charter and Technical Specification Inconsistencies. The NSRB Charter, Revir. ion 3, agrees with the Technical Specifications for both quorum requirements and meeting frequency.
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(Closed)
Inspector Foilowup Item (369/81-17-18, 370/81-05-18):
Clarification of NSRB Review Function.
The inspector reviewed the format and content of several NSRB minutes and verified that the individual reviews conducted prior to the NSRB meeting are addressed and documented in the NSRB group meetings.
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(Closed) Inspector Followup Item (369/81-17-19): Strip Charts Receipt.
The inspector reviewed a draf t of Station Directive 3.1.11 which describes the control system for insuring that proper sequencing is obtained for the receiving of recorder strip charts. The site QA has identified this area and will followup on implementation of the program.
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(Closed) Inspector Followup Item (369/81-17-20, 370/81-05-20):
Fi re Loading Review of Satellite Locations.
Station Directive 2.1.1, Revision 11, has been changed to reflect a biennial fire load review of all locations where one-hour fire rated cabinets are in use for storage of quality record.
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(Closed)
Inspector Followup Item (369/81-17-21, 370/81-05-21):
Misinterpretation of Grace Period.
The inspector reviewed a letter from M. D. McIntosh, Station Manager, to line management specifying the requirements for annual retraining and the consequences of not attending required training.
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