IR 05000423/1985036
| ML20134H792 | |
| Person / Time | |
|---|---|
| Site: | Millstone  |
| Issue date: | 08/23/1985 |
| From: | Dev M, Jerrica Johnson, Oliveira W, Prell J NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| To: | |
| Shared Package | |
| ML20134H774 | List: |
| References | |
| 50-423-85-36, NUDOCS 8508290171 | |
| Download: ML20134H792 (17) | |
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U.S. NUCLEAR REGULATORY COMMISSION
REGION I
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Report No.
50-423/85-36
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Docket No.
50-423
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l License No. CPpR-113 i;
Licensee: Northeast Nuclear Energy Company p. O. Box 270 (
Hartford, Connecticut 06101 i
Facility Name: Millstone Nuclear Power Station, Unit 3 i
Inspection At: Waterford, Connecticut
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Inspection Conducted: July 22 - 26, 1985
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II Inspectors:
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a n bev, Rea or Engineer date
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Approved by: (
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Jon Johnso'n", Chief, Operational date l
Programs Section, Operations Branch, DRS
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L Ins Routine unannounced inspection conducted on July _22-26, 198bectionSummary:50_4237FNi,
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(]eport_No.
e Area..s_In spec ted: QA/QC Administration; audit program; procurement program;
_ receipt, storage and handling program; record storage program; and document control program.
The inspection involved 111 hours0.00128 days <br />0.0308 hours <br />1.835317e-4 weeks <br />4.22355e-5 months <br /> on-site by 3 region-based l
inspectors.
_Results: No violations woro identified.
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DETAILS 1.0 Persons Contacted Northeast Utilities A. Andreae, Assistant Supervisor, Quality Control (QC)
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- R. Asafaylo, Supervisor, Quality Services t
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- 0. Bluementhal, Quality Assurance (QA) Engineer i
l A. Bruckner, Lead Stockhandler
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G. Castagna, QC Technician (
L. Chatfield, Supervisor, Site Engineering and Design Group
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- R. Cikatz, QC Engineer
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- G. Closius, Supervisor, QA/QC
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- J. Crockett, Superintendent, Millstone Point Unit 3
- K. Gray, Jr., Staff Assistant, Construction QA l
R. Griswald, Storeroom Supervisor M. Hess, Engineering Supervisor
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E. Lambert, Office Supervisor R. Langer, Assistant Supervisor, Chemistry T. Lewis, QC Technician D. Miller, Jr., Manager, Start-Up
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R. Montgomery, QC Senior Technician i
- 0. Nordquist, Manager, QA
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P. O'Connell, A,sociate Scientist S. Orefice, Project Engineer
"V. Papadopoli, Supervisor, Construction QA l
R. Sachatello, Supervisor, Radiation Protection i
S. Sudigala, Assistant Start-Up Engineer i
R. Vaccaro, Senior Engineering Technician
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- R. Viviano, Assistant Project Engineer l
R. Welzant, Document Coordinator i
J. Winn, Supervisor, Nuclear Records
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U.S. Nuclear Regulatory _Commi3._fon
- T. Rebelowski, Senior Resident inspector
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- J. Johnson, Chief, Operational Programs Section
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- Denotes those present at the exit meeting on July 26, 1985.
t 2.0 QAProgram
2.1 Refer es I
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1.
Millstone Nuclear Power Station, Unit 3. Final Safety Analysis
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Report, Volume 14, Section 17.2 i
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Northeast Utilities Quality Assurance Program (NUQAP) Topical l
Report r
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Nuclear Quality Assurance Branch Procedure (NQA)-1.01, Revision 2, Quality Assurance Branch Organization i
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NQA-1.02, Revision 3, Preparation, Issuance and Control of the
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Northeast Utilities Quality Assurance Program Topical Report
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NQA-1.03, Revision 4. Preparation, Issuance and Control of NUSCO Quality Assurance Branch Procedures t
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NQA-1.05, Revision 3, NUSCO Quality Assurance Branch Indoctri-nation and Training Program I
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NQA-1.06, Revision 0, Northeast Utilities Quality Assurance Orientation and Training Program
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NQA-1.10, Revision 2, Review of NUSCO Quality Related Procedures / Drawings 9.
Adminstration Control Procedure (ACP) - QA-1.01, Revision 4 Millstone Administration
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10. ACP-QA-1.02, Revision 16, Organization and Responsibilities 11. ACP-QA-1.03, Revision 10, Assumption of Responsibilities by Key Personnel 12. ACP-QA-1.04, Revision 19, Plant Operations Review Committee 13. ACP-QA-1.06, Revision 8, Quality Assurance-Quality Control Program
14. ACP-QA-2.01, Revision 5, Quality Assuranco Program Boundary t
15. ACP-QA-3.01, Revision 15 Administrative Control Procedures and
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Station Forms t
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16. ACP-QA-3.02, Revision 32, Station Procedures and Forms
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17. ACP-QA-3.07, Revision 4, Maintenance of Station Implementing
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Procedures in accordance with NUSCO Governing Documents l
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18. ANSI /ASMC N45.2.6-1978, Qualification of Inspection, Examination
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l and Testing Personnel for Nuclear Power Plants l
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19. ANS!/ASME N45.2.23-1978, Qualification of Quality Assurance
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Program Audit Personnel for Nuclear Power Plants l
l 2.2 fr_ogramReview r
i The above reforonces were reviewed to determine if the Itcensee has
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established an acceptable QA program which will be in effect when
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Millstone Point, Unit 3, goes operational.
Based upon this review I
the following items were verified References 2, 3, 10, 11, 12, 14 and 15, of Section 2.1 above, I
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clearly define and identify those organizations, systems, i
structures, components, documents and activities to which the QA i
program applies.
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References 2, 4, 5, 9, 13, 16, 17 and 18 of Section 2.1 above
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have established responsibilities and controls for making changes to QA documents.
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Corporate QA procedures and procedural changes are reviewed and
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approved by the QA Manager. Millstone site QA procedures and their revisions are reviewed and approved by the site QA/QC group.
Procedures are controlled (distributed and recalled) by the Design and Operations QA Group.
The QA program is annua 11) reviewed by the Joint Utilities'
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Audit.
In addition, all QA audits are reviewed by senior management and the Nucioar Review Board.
When Unit 3 receives its operating license, NUSCO will assume
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responsibility for all site audit activities.
The responsibil-
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ity of site QC activities will remain with the site (Northeast
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NuclearEnergyCo.(NNECO)QA/QCorganization.
The QC organi-l zation is administrativo1y independent of the Unit 3 l
superintendent.
2.3 Findings
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l The QA/QC program for Millstone Unit 3 will be the same as that
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presently being used for Units 1 and 2.
NUSCO Construction QA/QC l
personnel will be dispersed among the separate operating QA l
organizations.
Personnel are trained and certified to the appro-priate ANS! standards.
Present staffing levels are adequate to meet operational QA/QC requirements.
Except for a few minor procedural l
revisions which have to be made to reflect Unit's 3 operational l
status, the QA/QC operational program is ready to be implemented.
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No violations were identified.
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3.0 QAAuditPro2r_am j
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3.1 Re fe rence_s j
P 1.
Northeast Utt11ttes QualPy Assurance Program (NVQAP) Topical
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Report
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ANS! N18-7/ANS-3.2 - 1976, Adtninistrative Controls and Quality t
i Assurance for the Operational Phase of Nuclear Power Plants
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ANSI /ASME N45.2.12 - 1977, Requirements for Auditing of Quality
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l Assurance Programs for Nuclear Power Plants
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NQA-1.07, Revision 2, Training and Qualification of NQA Branch Lead Auditors and Surveyors 5.
NQA-1.08, Revision 2 Selection, Training, Qualification and Certification of NUSCO Non-NDE Inspection and Testing Personnel
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NQA-1.14, Revision 5, Conduct, Reporting and Follow-Up of Audits 7.
NQA-2.10, Revision 3, Performance, Reporting and Follow-Up of l
Surveillance Activities l
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ACP-QA-8.07, Revision 3, QA Training Program l
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ACP-QA-8.16, Revision 12, Training, Cortification and Identift-cation of Qualified Inspection and Testing Personnel 10. ACP-QA-8.21 Revision 5, Qualification of Audit Personnel 11. ACP-QA-9.01, Revision 11, Quality Assurance Audits 12. ACP-QA-9.02, Revision 12, Station Surveillance Program 13. ACP-QA-9.05, Revision 12, Monitoring of QA Activities 14. Millstone, Unit 3, first draft, Technical Specifications, Section 6
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3.2 P_rogram Review
The references of section 3.1 were reviewed and discussions were held
with management personnel to determine if the licensee had developed
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an 6 h quate QA audit program for implementation upon receipt of their s
operating license.
Based upon this review, it was determined that:
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Specifications and QA program requirements.
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responsibilities had boon assigned for the management of the
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audit program.
These responsibilities include training, certi-fication and qualification requirements for audit personnel;
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independonce from operating management of audit personnel; requirements for assuring that corrective actions are taken for deficienclos identified during audits; responsibility for deter-
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mining when re-audits are required; requirements for assuring
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that audit reports are reviewed by upper management; periodic
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review by management of the audit program to determine its l
status and adequacy; and preparation of long range audit plans.
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the audited organization is required to respond in writing with-
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in 30 days to audit findings.
distribution requirements for audit reports and corrective
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action responses have been defined, and checklist or procedures are required to be used in the per-
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formance of audits.
3.3 Findings The Itcensee has not yet developed the long range audit schedule for Millstone, Unit 3.
This schedule, however, will be developed by January 1986, and will include Units 1 and 2.
Presently, the licensee has a one year audit schedule for Unit 3.
A review of the training / certification records for 3 auditors was performed.
In addition, discussions were held with management con-cerning the proposed upgrading of the auditor training program.
This program will be designed to identify and specify weaknesses in an auditors background.
NUSCO QA personnel have the responsibility for performing all required audits.
NNECO QA/QC personnel, however, perform audits requested by site or unit management of perceived weak areas.
Both NUSCO and NNECO QA personnel perform surveillancos.
NUSCO uses checklists to perform their surveillances while NNECO surveillances are less structured. NNECO QC personnel are responsible for all QC inspections. Although, the NUSCO and NNECO QA organizations have different reporting chains, it appears they complement each other and provide good overall QA coverage of sito activities.
No violations were identified.
4.0 Document Control and Records Program 4.1 R_equirements/Re ferences
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1.
ANSI N45.2.9 - 1974, Requirement for Collection, Storage and l
Maintenance of Quality Assurance Records for Nuclear Power
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Plants 2.
Northeast Utilities Quality Assurance Program Topical Report 3.
Administrative Control Proceduro (ACP) - QA-2.02C, Revision 4, Work Orders 4.
ACP-QA-3,02, Revision 32, Station Proceduros and Forms
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ACP-QA-3.03, Revision 27, Document Control l
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ACP-QA-10.04, Revision 25, Nuclear Power Plant Records 7.
NUSCO QA Section Audit, Survey, Inspection Schedule printout
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dated June 20, 1985 4.2 Program Review i
The inspector reviewed the licensee's Quality Assurance Document l
Control and Records programs.
These programs were established to
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meet the requirements of the documents referenced in paragraph 4.1.
l The licensee's procedures adequately identified the documentation and records required to be maintained.
Responsibilities and controls for
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storage and filing, transfer, retention, maintenance and disposition of documents and records were also identified and assigned in the licensee's procedures.
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4.3 Program Implementation The inspector verified the implementation of the Quality Assurance (QA) Document Control and Records Program as presented in ACP-QA-3.03 and ACP-QA-10.04.
Tours of several departments and the storage vault were made to review implementation of the program. The inspector determined that document control personnel:
(1) readily retrieved any document requested.
(2) controlled the receipt and verification of documents and records including revisions and changes.
The inspector reviewed the Nuclear Plant Record Transmittal form (ACP-QA-10.04, Attachment A) submitted by the Maintenance and Instrument and Control (I&C)
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(3) controlled access to files and established the accountability of l
records, and l
i (4) were knowledgeable of the retention requirements for records, i
retention and turnover schedule for the Maintenance, Operations,
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Health Physics, Startup Engineering, and I&C Department.
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Administration Control Procedures (ACPs) are administrative 1y con-i trolled by the Station Office Supervisor, NNECO.
The Administrative Record Clerk for Millstone Unit 3 reports to the Station Office r
Supervisor.
The Records Clerk receives new procedures or revisions i
in draf t form, types them for QA review and Station Operations Review l
Committee (50RC) approval, and issues the approved procedures, i
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revisions or changes in accordance with an approved distribution list.
The Records Clerk also prepares the transmittal form and submits the procedure or revision to Nuclear Plant Records Facilit;
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t (NPRF) for filming.
The inspector walked through the approval process for several procedures and found that the procedures were I
being processed in accordance with ACP-QA-3,02. Other records clerks i
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i or custodians perform the same or similar duties as the Administra-tive Records Clerk. The Administrative Records Clerk also controls the care, maintenance and issuance of technical manuals received primarily from the construction architect-engineer (A-E). When
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operational, this function will be performed by NPRF.
The Station storage vault was inspected. This vault met the require-ments of a single storage facility discussed in ANSI N45.2.9, Para-I graph 5.6.
The temperature and humidity gauge was calibrated and is i
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read and logged daily.
Improvements to the vault include a separate air conditioniny unit, a Halon fire protection system, and space saver l
shelving. Access to the vault is controlled by the NPRF Supervisor.
The permarent records in the vault for MP-3 consisted mainly of con-trol rotm strip charts.
TN inspector randomly selected the following documents and records for review to verify proper implementation of the program:
Surveillance of Fire Detection Panel and Detector Operability
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Check-Fuel Butiding (Ops Form 354!N-6) and Daily Fire Door Surveillance (Ops Form 36415)
Shift Supervision Log Book (September 16, 1984 - January 30,
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Changes to ACP Distribution Lists, e.g. SF-304 added Unit 3 l
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(MP-3) Startup form and SF-328-3 for Emergency Planning added
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for Unit 3 (MP-3).
Quality Control (QC) Personnel Qualification Records i
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Work Orders - M3-85-22196, RHR Pump Suction Isolation Valve;
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M3-85-202393, MCC and Rod Control Area AC Unit outlet; M3-85-21470 Cire. Pump Water Supply Pressure Switch; and
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M-3-85-06153 Steam Generator (50) No. 2 Feed Water PICO fuses Chemistry records, e.g.-Analysis Sheet for SG No. 4; BOP
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Chemistry Control; Chloride analysis (mercuric Nitrate Titra-
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tion), Secondary Chemistry Control
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Radiation Protection System records, e.g. Receipt Shipment of
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fuel Elements Survey for fuel cells: Smear Test for Sealed Source Contamination QA Surveillances, e.g. 585-27, 33, 39, 42, 49, 54, 62, 68 and 69
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have overdue responses per MPS-QA 1266 Memo of July 24, 1985 Valve line up for "B" Otosel Cooling Water
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4.3 Program Implementation The transfer of standard information, e.g. test reports, specifica-tions, purchase orders (PO), etc., from Stone and Webster Engineering Corporation (SWEC) to NUSCO is proceeding as planned with an estimated completion date (ECD) of December 1985. A sum of 1761 out of a total of 2400 rolls of film have been delivered by SWEC.
Drawing control for MP 3 was not reviewed by the inspector because the drawings have not been officially turned over by SWEC to NUSCO.
The turnover is scheduled to begin in August 1985 with a ECD of May 1986. The 20,000 vendor drawings and the 6,000 SWEC drawings have NUSCO drawing numbers.
SWEC has been giving NUSCO, on a continual basis, the current status of the drawing turnover program.
4.4 QA/QC Interface All ACPs and Work Orders for Category I (safety related), radwaste, and fire protection are reviewed by QA.
Document Control and Records audits are scheduled and conducted.
The Site QA personnel conducted an audit during November 19 to December 6, 1984.
The audit coverage was adequate and the corrective action response is timely. A rollow up audit to verify implementation of corrective actions scheduled for August 30, 1985.
Except for the final QC review of Work Orders (see paragraph 4,5), the QA/QC staff is adequate to deal with the document control and records program transition from construction to opera-l tion, j
4.5 Paragraph 6.86 of procedure ACP-QA-2.02C, Work Orders, requires the QC/ Construction QA (QC/C0A) Department to review completed Category I, Fire Protection QA (FPQA) or Radwaste QA work order (WO) packages
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for final acceptance within four weeks of receipt of the WO.
The QC personnel are not reviewing the W0s within the four week time span, as evidenced by the sampling of 400 I&C and Production Test W0s sub-mitted to QC prior to May 30, 1985.
The sampled results indicated that 80 I&C records dating as far back as April 25, 1984, and 40 Production Test records dating back to December 19, 1984 had not received a final review by QC, CQA, however, has been conducting an audit of W0s (Audit No. 40975) since June 6,1985 with a schedule completion date of August 2, 1985.
The NRC inspector was advised that their auditor had identified the same problem (Finding F-01).
This is an unresolved item pending NRC review of the corrective ac-tions taken by the licensee to the Construction QA Finding.
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(50-423/85-36-01).
l 5.0 P_rocurement Con _ trol 5.1 References /Requj_roments
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Final Safety Analysis Report, Sections 3.2 and 17.2 l
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10 CFR 50, Appendix 0, Criteria IV, VII and VIII I
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ANSI N45.2.13-1976, Quality Assurance Requirements for Control of Procurement of Items and Services for Nuclear Power Plants 4.
ANSI N45.2-1977, Quality Assurance Requirements 5.
Regulatory Guide 1.123, Quality Assurance Requirements for Control of Items and Services for Nuclear Power Plants, Rev.1 6.
Northeast Utilities Quality Assurance Program Topical Report, Proposed Rev. 7 5.2 Program Review The inspector reviewed the procurement control program to determine that the Millstone Point, Unit 3 (MP-3) has established administra-tive controls for:
Identification of items purchased; identification of tests and,
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or special instructions, technical requirements and documenta-tion to certify the items; and assurance that the contractor or supplier has implemented a QA program consistent with 10 CFR 50, Appendix B, including the provision for reportability per 10 CFR 21.
l Initiation of procurements; review and approval of specifica-
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tions differing from the original design documents; review and approval of procurements, including changes there to; and designation of quality classification of procured items.
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l Assignment for evaluation and approval of bidders / suppliers
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including review and update of the listing of the approved suppliers; providing for right of access to suppliers facilities and records; and maintenance of records of suppliers qualifica-tion and audits.
The inspector reviewed the following Northeast Utility (NUSCO)
procedures as applicable to MP-3:
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l NE0-6.01, Material, Equipment and Parts List, Nuclear
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Engineering and Operation Procedure, for In-Service Nuclear Generation Facilities, Rev 0.A NE0-6.02, Preparation and Review of Quality Related Purchase
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Requisition, Rev. 1.A NEO-6.03, Transfer Material, Equipment and Parts, R.v. 0.8
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NE0-6.04, Review of Proposals, Rev. 0
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NUSCO Quality Assurance Branch Procedure (NQAP)-1.11, Supplier
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Evaluation, Rev. 2 l
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NQAP-1.12, Preparation, Issuance and Control of the NUSCO
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Quality Assurance Category I Contractor, Supplier and Engineering Service Organization List, Rev 2 NQAP-1.14, Conduct, Reporting and Followup of Audits, Rev. 5
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NQAP-1.15, Review an'd Approval of the QA Program /QA Survey of
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NUSCO Supplier, Rev. 2 NQAP-2.03, Procurement Document Review, Rev. 4
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NQAP-2.08, Conduct a'nd Reporting of NUSCO Quality Assurance
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Inspection NQAP-2.10, Performance, Reporting and Followup of Surveillance
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Activities, Rev. 3 ACP-QA-3.05, Review and Approval of Vendor-Procedures, Rev. 6
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'ACP-QA-4.02, Procurement, Contrcl and Identification of
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Materials, Rev. 20 ACP-QA-4.03, Classifying and Upgrading Spare Parts, Rev. 12
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ACP-QA-5.01, Non-Conforming Materials and Parts, Rev. 14
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MP-3, Station Procedure QA-1307, Purchase Requisition Processing
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and Receipt Inspection, Rev. 1 MP-3, Station Procedure QA-1308, SWEC Material Transfer (Unit
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3), Rev. 1 5.3 Program Implementation
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The inspector verified that the Northeast Utility Service Company
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(NUSCO) has established administrative control directives for preparing, reviewing and approving procurement documents as i
delineated in the Nuclear, Engineering and Operations Procedure, i
NEO-6.02, Administrative Control Procedure ACP-QA-4.02, and station l
procedure QA-1307.
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The inspector randomly selected nine recently purchased items as indicated in paragraph 6.3 and verified'that:
The procurement documents were complete and prepared in
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accordance with the NVSCO procurement procedures.
The items were purchased from qualified vendor listed in NUSCO
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Approved Supplier List (ASL).
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The procurement documents required the vendor to comply with the
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requirements delineated in the purchase order, such as, equipment quality classification, environment qualification, shelf-life program, QA program, applicability of 10 CFR 21 and 10 CFR 50.55(e), and purchaser right to access to supplier's facility and documents.
The inspector verified that NUSCO has established an Approved Sup-plier List (ASL).
Supplier performance is evaluated in accordance with procedure NQA-1.11 which is based on information of an accept-able supplier QA program as supported by the NRC White Book, CASE Register, A-E and other utilities recommendations, ASME/MM/MS certi-fication or QA originated vendor research and survey. Approved sup-plier performance is evaluated periodically and the ASL is updated monthly.
l NUSCO Nuclear QA Procurement conducts audit, surveillance and monitoring of quality control activities of vendors and engineering consultants providing safety-related material, equipment or service to NUSCO.
The records of supplier qualification and audits are maintained by the Nuclear QA Procurement group.
Nuclear Engineering and Operation Procedure NEO-6.01 and Administra-tive Control Procedure ACP-QA-4.03 provides guidance for safety classification of equipment, components and systems. Also, Northeast Utilities QA Program Topical Report, Appendix A, delineates criteria for Category I, Radwaste QA, Fire Protection QA fystems, structures and components.
NUSCO Material, Equipment and Fart List (MEPL)
engineers are engaged in developing a specific MP-3 MEPL in accord ance with above Procedures and Station Form SF-506. MEPLs for MP-1 and MP-2 are already in existence and inclusion of MP-3 MEPL would constitute NUSCO MEPL program completion.
5.4 Findings No violations were identified.
However, the inspector noted that Administrative Control and Nuclear Engineering and Operation procure-ment related procedures were not updated to reflect the inclusion of MP-3 in the program.
This is an unresolved item pending revision to ACP-QA-3.03, ACP-QA-4.01, ACP-QA-4.02, ACP-QA-4.03, NE0-6.01, and l
NE0-6.02, and subsequent NRC verification (50-423/85-36-02).
Nuclear Engineering and Operations Procedure, NE0-6.01 assures the preparation and maintenance of a Material, Equipment and Part List (MEPL) in compliance with 10 CFR 50, Appendix B, Criteria II, Regula-tory Guide 1.143, and procedure NE0-2.14.
The MEPL for MP-3 is not available for NRC inspection and, as such, the adequacy of MP-3 MEPL and the licensee's compliance to the governing requirements could not be determined.
The licensee estimated the readiness of the MP-3 MEPL by August 15, 1985.
This is an unresolved item pending generation of j
the MEPL and subsequent NRC inspection (50-423/85-36-03).
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6.0 Receipt, Storage and Handling of Equipment and Materials 6.1 References / Requirements 1.
10 CFR 50, Appendix B, Criteria VII, VIII, XIII, XV and XVI
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Final Safety Analysis Report Section 17.1 and 17.2 I
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ANSI N45.2-1971, Quality Assurance Program Requirements
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ANSI N45.2.2-1972, Packaging, Shipping, Receiving Storage and Handling of Items for Nuclear Power Plants 5.
Regulatory Guide 1.38, Quality Assurance Requirements for i
Packaging, Shipping, Receiving, Storage and Handling of Items for Water Cooled Nuclear Power Plants 6.2 Program Review The inspector reviewed the MP-3 Receipt, Storage and Handling programs for safety-related equipment and materials to verify the program compliance with the requirements referenced in paragraph 5.1, and to determine that the MP-3 has established administrative controls for:
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Identification and examination of materials, equipment and components for conformance with requirements specified in the original procurement documents Conduct of receiving inspection on all incoming safety-related
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materials, equipment and components including issued items being returned to storage
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Identification of materials, equipment and components requiring a certificate of quality of acceptance
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Control and disposition of received items, including tagging or marking for storage, holding or release for immediate use
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Disposition of non-conforming items, including marking and l
segregation, evaluation and dacumentation
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Prohibition of inadvertent installation and use of non-conform-ing items Conditional release of non-conforming items, including technical
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justification, documentation and authority for release
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Proper storage levels and appropriate environmental conditions
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Specification of storage controls, including access identifica-
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tion, arrangement, covering and preservation
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Periodic inspection of. storage areas
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Preventive maintenance and care of items in storage, including
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equipment shelf-life control.
The inspector reviewed the following NUSCO procedures as applicable
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to MP-3:
NE0-6.01, Material, Equipment and Parts Lists for In-Service
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j Nuclear Generating Facilities, Rev. 0.A
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NE0-6.03, Transfer of Material, Equipment and Parts, Rev. 0.B
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NE0-2.18, Corrective Action, Rev. 0.A
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- NUSCO QAP-2.03, Procurement Document Control, Rev. 4
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ACP-QA-4.01, Plant Housekeeping, Rev. 11 ACP-QA-4.02, Procurement, Control and Identification of
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Materials, Rev. 20 ACP-QA-4.04, Instruction for Packaging, Shipping, Receiving,
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Storage and Handling, Rev. 8
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ACP-QA-4.05, Product Acceptance Inspection and Testing, Rev. 3
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i ACP-QA-4.06, Procurement and Evaluation of Shelf-life Materials,
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Rev. I j.
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ACP-QA-4.07, Control of Weld Materials, Rev. 9 ACP-QA-5.01, Non-Conforming Materials and Parts, Rev. 14
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MP-3, Station Procedure QA-1311, Stone and Webster Receipt
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Procedure, Rev. O i
MP-3, Station Procedure QA-1309, Westinghouse Receipt i
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Procedure, Rev. 0 MP-3, Station Procedure QA-1308, SWEC Material Transfer (Unit
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3), Rev. 1
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MP-3, Station Procedure QA-1307, Purchase Requisition Processing
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l and Receipt Inspection, Rev. 1. and
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MP-3, Station Procedure STP-1702, Stores Department Shelf-life Tracking Procedure, Rev. O.
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6.3 Program Implementation The inspector toured the central receiving area and MP-3 spare part warehouse and discussed items with the storeroom supervisor,
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storeroom personnel and QC technicians regarding receipt, storage, handling and inspection of safety-related materials, equipment and parts.
The inspector randomly selected the following stored items to verify the adequacy of MP-3 storage, handling and inspection program:
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SN No. 384-108-11, Relay SN No. 384-108-13, Moulding
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SN No. 385-014-48, Piston (Colt)
SN No. 385-015-63, Switch (Reliance)
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SN No. 385-029-12, Solenoid Valve (Target Rock)
SN No. 385-029-17, 0-Ring (Target Rock)
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SN No. 385-030-18, Bearing SN No. 385-054-02, Temperature Control Switch (CVI)
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SN No. 385-090-12, Solenoid Valve ASCO The inspector reviewed the purchase documents for the above items to determine whether:
Receipt inspections were conducted in accordance with approved
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administrative control procedures
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Disposition of items was in accordance with the program requirement
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Tagging or marking allowed the tracing of items back to procure-ment documents, receipt documents and quality certification documents
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Preventive Maintenance was performed where necessary at the required intervals
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Documentation of non-conforming. items was transmitted to the appropriate organization for proper disposition, and
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An equipment shelf-life program was established and implemented 6.4 Findings The procurement packages reviewed were complete and documentation was adequate. A typical package contained a Material Receipt and In-spection report (MRIR), purchase specification, certificate of com-pliance, test data, invoice etcetra. The purchase order included the applicability of 10 CFR 21 requirements; access to the vendor facili-ty, audit and documentation; written vendor QA program; shelf-life program; certificate of compliance; and provision for reportability per 10 CFR 50.55(e).
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The MP-3 warehouse facility is not a level A storage facility. Pre-sently, level A items are stored in the Stone and Webster Warehouse.
Items included in the shelf-life program are identified. The store-room supervisor maintains an equipment shelf-life log-book which is updated every month.
Stored items requiring preventive maintenance are scheduled for and maintained by maintenance department or I&C department personnel.
The inspector reviewed the following procurement / receipt inspection related deficiency reports and verified that the corrective action and disposition was adequate:
Deficiency Nos.
UNS 3619 UNS 4110 UNS 4204 UNS 4206 UNS 4280
UNS 4558 UNS 4559 UNS 4584
UNS 4586 UNS 4588 Non-conforming materials and parts identified during the receipt inspection are put in the QA/QC hold area and dispositioned in i
accordance with technical evaluations and recommendations.
The expired shelf-life items are segregated and dispositioned according to technical justification and recommendation. There is a minimum 6
month time leeway to procure and replace a shelf-life item prior to it's expiration date.
The inspector also noted that the housekeeping, lighting, ventilation and fire protection at the MP-3 warehouse was adequate, and reflected the intent of station Administration Control Procedure ACP-QA-4.01.
No violations were identified.
7.0 Unresolved Items Unresolved items are matters about which more information is required in order to ascertain whether they are acceptable, deviation or violations.
Three unresolved items are discussed in Paragraphs 4.5 and 5.4.
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8.0 Management Meetings Licensee management was informed of the scope and purpose of the inspec-tion at an entrance meeting conducted July 22, 1985.
The findings of the inspection were discussed with licensee representatives during the course
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of the inspection. An exit meeting was conducted July 26, 1985, at the conclusion of the inspection (see Paragraph I for attendees) at which time the findings were presented to licensee management.
At no time during this meeting was written material provided to the licensee.
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