IR 05000334/1982012
| ML20054G978 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 06/02/1982 |
| From: | Caphton D, Eapen P, Shaub E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20054G972 | List: |
| References | |
| 50-334-82-12, NUDOCS 8206220465 | |
| Download: ML20054G978 (9) | |
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U. S. NUCLEAR REGULATORY COMMISSION Region I Report No. 50-334/82-12 Docket No. 50-334 License No. DPR-66 Priority Category C
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Licensee:
Duquesne Light Company Post Office Box 4 Shippingport, Pennsylvania 15077 Facility Name:
Beaver Valley Power Station Inspection At:
Beaver Valley Power Station Inspection Conducted:
May 10-14, 1982 Inspectors:
[7M 4*/- 4 6 - 2 ' 8 2-PT K.'Eapen, Ph.D., Reactor Inspector date signed
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fo'd'8E T. Shaub ea,ct,pr Inspector date signed Approved By:
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6g F-D. L. Caphfon, Chief, Management Program date signed Section Inspection Summary:
Inspection on May 10-14, 1982 (Report No. 50-334/82-12)
Areas Inspected:
Routine, unannounced inspection of Receipt, Storage and Handling of Safety-Related Materials and Equipment and Audits. The inspection involved 76 inspection hours onsite by two region based inspectors.
Results: No violations were identified in the inspected areas.
8206220465 820603 PDR ADOCK 05000334 PDR g
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DETAILS 1.
Persons Contacted
- D. Batina,-Senior QA Engineer
- D. Beron, Materials Control Supervisor S. Fenner, Director Operations Quality Control
- S. Hall, QC-Engineer
- D. Hunkele, Director QA
- F. Lipchick, Sr. Compliance Engineer
- C. Sabol, QA Engineer
- B. Sepelak, Safety and Licensing Engineer NRC
- W. Troskoski, Resident Inspector The inspector also held discussions with other members of the power station, and corporate Technical and Administrative staff.
- denotes those present at the exit interview conducted onsite, May 14, 1982.
2.
Receipt, Storage and Handling 2.1 References
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Appendix A to the facility's Final Safety Analysis Report (FSAR);
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ANSI N45.2-1971; ANSI N45.2.2-1972, Packaging, Shipping, Receiving, Storage, and
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Handling; and,
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Regulatory Guide 1.38 (Rev. 0).
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2.2 Program Review The licensee's program for receipt, storage and handling of safety related equipment and materials was reviewed to verify that the I
program was consistent with the requirements of the references in
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paragraph 2.1 above and to determine that administrative controls provided for:
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Requirements for conducting receipt inspection on all incoming safety related materials and equipment;
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Requirements that materials and equipment be examined fe*
conformance with requirements specified on original procurement documents;
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Provisions for identification of those materials and equipment
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that can be accepted by only a " certification of quality" (C of C);
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Controls for acceptance of items including tagging / marking for storage or immediate use; Controls for nonconfo ming items which include:
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Marking and segregating nonconforming items
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Disposition of nonconforming items (reevaluate, rework,
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repaired, or return)
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Prohibiting use of nonconforming items
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Notification of licensee audit group responsible for
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supplier (vendor) evaluation documentation of nonconforming items;
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Methods for conditional release of nonconforming items including justification for use, documentation and authority for conditional release;
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Requirements for providing proper levels of storage and appropriate environmental conditions;
-_ Requirements for specifying storage controls including access, identification, coverings, and preservatives;
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Requirements for periodic inspections of the storage' areas;
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Requirements for specifying ?,sintenance and care of items in storage including shelf life;
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Requirements for routine and special handling measures; and,
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Controls for hoisting equipment.
The following procedures were reviewed to verify the adequacy of the administrative controls:
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OP-6 (Rev. 4), Material Control;
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0QC-7.2 (Rev. 6), Receiving and Inspection of Materials Procured Through Duquesne Light Company Purchasing Department and BVPS;
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G.S.200.0 (Rev. 0), Quality Control Program;
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G.S.201.0 (Rev. 2), Handling Function;
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G.S.202.0 (Rev. 4), Identification Control Function;
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G.S.203.0 (Rev. 4), Receiving Inspection Function of Stock and
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Nonstock Material; i
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G.S.204.0 (Rev. 3),- Storage Function;
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G.S.207.0 (Rev. 1), Accumulation, Storage, Distribution and Retention of Records; G.S.208.0 (Rev. 0), Stores Personnel Training;.
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G.S.209.0 (Rev. 0), Training Records;
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G.S.210.0 (Rev. 0), Identification and Notification of Noncompliance Involving Store Material;
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G.S.211.0 (Rev. 2), Procurement of Stock Material; i
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G.S.212.0 (Rev. 0), Inspection of Material Handling Equipment;
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G.S.213.0 (Rev. 2), Issuing Function; i
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G.S.214.0 (Rev. 0), Procurement of Nonstock Material;
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G.S.215.0 (Rev. 2), Borrowing and Replacement of Mater.ial;
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G.S.217.0 (Rev. 0), Returned Material Function;
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G.S.218.0 (Rev. 1), Initiating a Stock Item;
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G.S.218.1 (Rev. 0), Revision of a Stock Item Request;
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G.S.219.0 (Rev. 0), Replacement and Scrap Function; i
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G.S.220.0 (Rev. 0), Receipt of ASME Material;
G.S.300 (Rev. 0), Requirements for Preparation of Temporary
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Store Procedures;
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G.S.302 (Rev. 0), Offsite Storage;
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G.S.303 (Rev. 0), Receipt Inspection of Stone and Webster Purchased Material for Unit 1 Modification.
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2.3 Implementation 2.3.1 The inspector selectively sampled safety related materials and equipment received on site to. verify:
Receipt inspections were conducted in accordance with
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administrative controls
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Disposition of the' item was in accordance with administrative controls
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Storage of items including packaging, preservatives, covering and environmental conditions were in accordance with manufacturers' recommendations
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Tagging / marking allowed tracing the item back to procurement documents, receipt documents and " quality certification" documents
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Nonconforming items were clearly marked and segregated from other safety related items
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Documentation of nonconforming items was transmitted to affected organization for them to determine final item disposition.
2.3.2 The inspector accompanied licensee personnel during their
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monthly inspection of the onsite warehouse to verify:
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Controlled access to the storage area is maintained
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Cleanliness and good housekeeping practices are enforced
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Fire protection was commensurate within the type of storage area and materials involved
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Food and associated items were not permitted
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The adequacy of material storage, including protective coverings, coatings and preservatives
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Hazardous material segregation
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Clear identification of shelf life of applicable mdterial.
2.3.3 The inspector interviewed the Materials Control Supervisor to determine that the current staffing level as depicted in the' plant's organizational charts was adequate to effectively manage and maintain the spare parts inventory
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program.
In addition, the inspector reviewed the training records of 2 store keepers and 2 quality control receipt inspectors to verify that their training was adequate to perform their assigned tasks.
2.4 Findings (1) The Controlled Copy (No. 6) of the store's procedures, issued to the storeroom, was missing copies of QA review and approval tags. The inspector informed the licensee's representatives that the Controlled Copy should be complete.
The Material Control Supervisor stated to the inspector that Controlled Copy No. 6 would be reviewed and the missing information will be added either by copying the QA review and approval tag or by revising the signature block to include QA review and approval.
This procedure revision will be reviewed in a future NRC inspection (IFI-50-334/82-12-01).
(2)
' Post Fire Evaluation' requirements of ANSI N45.2.2-1972 were not incorporated in stores procedures. However, the stores personnel conducted a post evaluation, preceeding the fire on April 16, 1982 that met the intent of the above ANSI requirement.
The inspector stated that the licensee should review the stores procedures and the procedures of the supporting organizations; identify missing ANSI N45.2.2-1972 requirements from these procedures; and revise the procedures to incorporate the missing ANSI N45.2.2-1972 requirements.
The licensee's representative acknowledged by stating that they would review the stores procedures, station procurement procedures, the engineering management procedures for the nuclear engineering department and the QC procedures and would revise them as necessary by September 1, 1982. The above procedure review and revision will be followed in a future NRC inspection (IFI-50-334/82-12-02).
(3) The licensee has noted that the originators of purchase orders were not providing the ' stores' with the long term storage and handling requirements for the material and equipment procured.
(Procedure G.S.203.0 (Rev. 4) states that the long term storage and handling requirement will be provided by the originator of the purchase order). The licensee is currently developing a program to establish the long term storage and special handling requirements for safety related material and equipment.
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effectiveness of the above program will be reviewed in a future i
NRC inspection (IFI-50-334/82-12-03).
l (4) The equipment qualification reports, contained in the receipt and storage records, were not reviewed by engineering for technical adequacy.
For example, the qualification report for
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Purchase Order No. C014539 indicated that the procured equipment-was qualified to a less conservative environment than that for the facility.
The report contained no justification for the use of this equipment at the facility. A licensee representative informed the inspector that the required justification was-maintained at the corporate office.
The inspector stated that the engineering personnel should review and accept the qualification reports prior to filing at stores. The licensee's representatives acknowledged the inspector's statement.
The engineering review and acceptance of qualification reports contained in receipt and storage records will be followed in a future NRC inspection (50-334/82-12-04).
(5) The inspector informed the licensee that the present staffing is below the required level and the licensee acknowledged the inspector's statement.
3.
Audits 3.1 Requirements The requirements governing the performance of quality assurance audits of safety-related areas are specified in 10 CFR 50, Appendix B, " Quality Assurance Criteria for Nuclear Power Plants" and Technical Specifications, Section 6, " Administrative Controls." In addition, the Duquesne Light Company Quality Assurance Program for Operations requires compliance with the requirements of ANSI N45.2, " Quality Assurance Program Requirements for Nuclear Power Plants", 1972, ANSI N18.7, " Administrative Controls for Nuclear Power Plants", 1972, and ANSI N45.2.12, " Requirements for Auditing of Quality Assurance Programs for Nuclear Power Plants", Draft 3, Rev. 4, February 22, 1974.
3.2 Review The inspector reviewed the applicable Quality Assurance Procedures and Instructions to determine:
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The content of audit reports clearly defines the scope of the audit and the results.
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Audits are conducted by trained personnel not having direct responsibility in the area being audited.
Frequency of audits are in conformance with Technical Specifications
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and the QA program.
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Appropriate followup actions (including reaudit, if necessary)
are being taken, are in progress or are being initiate. _
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The audited organization's response to the audit findings is in
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writing, is timely, and adequately addresses the findings and recommendations.
-In addition, the inspector reviewed the following to verify compliance with the requirements:
1981 and 1982 audit schedules
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Qualification records of six auditors and the licensee's response
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to generic letter 81-01, " Qualification of Inspection, Examination, and Testing and Audit Personnel"
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QA Outage surveillance log and five surveillance reports.
A selective sample of 1981 and 1982 audits including:
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(1) BV-1-82-31, Corrective Actions Technical Specification 6.5.2.8.c, October 26 - November 13, 1981; (2) BV-1-82-03, Emergency Preparedness Plan, January 25 -
March 5, 1982; (3) BV-1-80-44, Fire Protection and Loss Prevention, for Technical Specification 6.5.2.8.j, December 9-16, 1980; (4) BV-1-81-09, Fire Protection and Loss Prevention Program for Technical Specifications 6.5.2.8.h and i, April 27-30, 1981 and May 13-15, 1981; (5) BV-1-81-06, Technical Specification Appendix A for Technical Specification 6.5.2.8.a, February 23 - July 10,1981; (6) BV-1-81-20, Compliance to Technical Specifications Appendix B for Technical Specification 6.5.2.8.a, July 13-17, 1981; (7) BV-1-81-14, Teledyne Isotope for Technical Specification 6.5.2.8.a, June 23-24, 1981; (8) BV-1-81-29, Teledyne Isotopes Field Activities for Technical Specification 6.5.2.8.a, September 22 and October 15, 1981; (9) BV-1-81-34, Effluent Monitoring Audit, November 30 -
December 2, 1981; (10) BV-1-82-10, ORC Audit of Training, April 12-23, 1982; (11) BV-1-82-18, EDS Nuclear Inc., April 20-21, 1982;
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(12) BV-1-82-05, Engineering and Construction Clerical and.
Records Section, February 22-23, 1982; (13) BV-1-80-36, Security Audit, August 18-22, 1980; (14) BV-1-81-22, Security Audit, August 25-28, 1981; (15) BV-1-82-07, Chemistry Aud,i, February 25-26, 1981; (16) BV-1-81-21, Offsite Review Committee, August 28, 1981; and, (17) BV-1-81-17, Compliance to License Conditions, June 15-July 14, 1981.
No violations were identified.
3.3 Implementation The inspector witnessed portions of the audit BV-1-82-21, "BV Procurement",
to verify that:
a written audit plan and checklist were developed and followed;
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a pre-audit conference was conducted with cognizant management;
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conditions or nonconformances requiring immediate corrective action are reported to management;
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objective evidence was examined for compliance with quality assurance program requirements.
In addition, the inspector discussed the current QA department staffing level and the licensee's plans to fill the current vacancies.
No violations were identified.
4.
Unresolved Items j
Unresolved items are matters about which more information is required in i
order to ascertain whether they are acceptable, deviations or violations.
l No unresolved items were identified during this inspection.
5.
Exit Interview I
l The inspectors met with the licensee's representatives denoted in paragraph 1 at the conclusion of the inspection on May 14, 1982 to formally present l
the findings. The licensee representatives acknowledged the inspector's
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statements.
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