IR 05000482/1987029
| ML20236X722 | |
| Person / Time | |
|---|---|
| Site: | Wolf Creek  |
| Issue date: | 12/03/1987 |
| From: | Hunnicutt D, Greg Pick, Seidle W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20236X716 | List: |
| References | |
| 50-482-87-29, NUDOCS 8712100173 | |
| Download: ML20236X722 (7) | |
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APPENDIX U.S. NUCLEAR REGULATORY COMMISSION
REGION IV
I NRC Inspection Report:
50-482/87-29 Operating License:
NPF-42 Docket:
50-482 Licensee:
Wolf Creek Nuclear Operating Corporation (WCN0C)
P.O. Box 411 Burlington, Kansas 66839 Facility Name: Wolf Creek Generating Station Inspection At:
Burlington, Kansas Inspection Conducted:
October 26-30, 1987 Inspectors:
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G. A. Pi :k eactor Inspector, Operational Date Prog ms ection, Division of Reactor
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D.(M. H6hnicutt, Chief, Test Programs Section Date'
Operations Branch, Division of Reactor Safety Approved:
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W. C. Seidl O Chief, 0.lerational Programs Date Section, Operations Branch, Division of Reactor Safety inspection Summary Inspection Conducted October 26-30, 1987 (Report 50-482/87-2M Areas Inspected:
Routine, unannounced inspection of design changes and modifications.
Results:
Within the areas inspected, no violations or deviations were Identified.
8712100173 871207 PDR ADOCK 0500
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DETAILS 1.
Persons Contacted WCNOC
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D. Withers, President
- F. T. Rhodes, Vice President, Nuclear Operations
- R. M. Grant, Vice President, Quality
- J. M. Pippin, Manager, Nuclear Plant Engineering'(NPE)
- G. D. Boyer, Plant Manager
- W. J. Rudolph.II, Manager, Quality Assurance (QA)
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- 0. Maynard, Manager, Licensing
- A. A. Freitag, Manager, NPE-WC
- B. E. Bergstrom, Acting Manager, NPE-Systems
- C. M. Estes Operations Superintendent
- M. G. Williams, Superintendent, Regulatory, Quality, and Administration
- G. J. Pendergrass, Licensing Engineer
- S. R. Sparks, Licensing Engineer Others - Construction contractor supervisor, quality control (QC),
instrument and control (I&C) technicians, electricians, mcchanics, health physics technicians, operators, senior reactor operators, shift supervisor, engineers, and other contractor personnel.
NRC
- W. F. Smith, Senior Resident Inspector, Waterford 3
- M. E. Skow, Reactor Inspector
- B. L. Bartlett, Resident Inspector
- J. E. Cummins, Senior Resident Inspector
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- Denotes those present at the exit interview.
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Design Changes and Modifications The NRC inspector conducted this inspection to ascertain whether design changes and modifications that were determined not to require NRC approval were in conformance with licensee programs and 10 CFR 50.59.
The NRC inspector reviewed the design change program as described in overall plant procedures -KGPs and selected procedures from plant operations -ADMs, nuclear plant engineering -KPNs, including Bechtel Power Corporation (Bechtel) -EDPIs, and configuration management -KPs.
The procedures selected and reviewed, which describe and implement the design change progrant, are summarized below:
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KGP-1131, " Plant Modification Process," Revision 5, dated June 5, i
1987.
This procedure provided the mechanism for initiating a Plant Modification Request (PMR) and for obtaining the required approvals and closeout of the PMR.
l KGP-1135, " Configuration Verification," Revision 2, dated March 7,
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1986. This procedure established the methods for acceptance of modified structures, components and/or systems and to verify that the modified, "as-built," configuration conformed to the approved i
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documentation.
' ADM 01-042, " Plant Modification Request Implementation," Revision 10, dated May 19, 1987.
This procedure specified the means and mechanism for implementing a PMR from distribution for planning until the modification is complete.
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KPN-C-300, " Plant Modification Process," Revision 4, dated July 13,
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1987. This procedure provided an overview of NPE activities and established responsibilities, i
KPN-C-301, " Initiation of Plant Modifications," Revision 6, dated July 10, 1987. This procedure prescribed the initiation of the PMR by NPE.
KPN-C-302, " Engineering Study for Plant Modification Request,"
Revision 7, dated July 13, 1987.
This procedure prescribed the guidelines for the performance of an engineering study for a PMR.
KPN-C-305, " Initiating Procurement Activities Associated with Plant Modifications," Revision 2, dated April 17, 1987.
This procedure prescribed the initiation of the procurement for engineering material associated with a PMR.
KPN-C-306, " Preparing the Plant Modification Request for Release,"
Revision 2, dated July 10, 1987. This procedure prescribed the method for verifying that a required detailed design is complete and for preparing the PMR for release to the field.
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KPN-C-308, "Closecut of Completed Plant Modification Request,"
i Revision 2, dated July 10, 1987.
This procedure prescribed the steps
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for closeout of PMRs by NPE.
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KPN-C-309, " Plant Modification Design Development," Revision 1, dated
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July 10, 1987. This procedure prescribed the engineering activities I
associated with development of the design for PMRs.
KPN-D-302, " Engineering Study," Revision 4, dated April 17, 1987.
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This procedure outlined the requirements for the initiation, j
development and approval of engineering studies and reports.
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KPN-D-304, " Licensing Review and Safety Evaluation," Revision 1,- dated July 10, 1987.
This procedure prescribed the methods to be used to ensure that all design changes are reviewed and evaluated per the requirements of 10 CFR 50.59.
KPN-D-306, " Requesting Changes to the FSAR and Technical Specifications," Revision 2, dated February 7, 1986.
This procedure described the methods for requesting changes to the USAR and the-Technical Specifications (TS).
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KPN-E-301, " Design Interfaces," Revision 4, dated May 23. 1986.. This procedure established measures to identify, control, and coordinate the responsibilities and functions of organizations that are participating in design activities.
KPN-E-302, " Design Input," Revision 2, dated November 27, 1985.
This procedure defined the requirements which ensure that design input is identified, documented, approved, and controlled; provided guidelines for establishing design input; and established the mechanism to collect design input documents.
KPN-E-303, " Calculations," Revision 4, dated April 10, 1987. This
procedure defined the requirements to ensure that design calculations are identified, documented, approved, and controlled; provided guidelines for establishing design calculations; and was used for calculations related to engineering activities.
KPN-E-308, " Interdisciplinary Reviews," Revision 5, dated April 17, 1987.
This procedure provided for the interdisciplinary review of design documents to determine the impact, compatibility, and control interfaces on structures, systems, and components.
KPN-E-309, " Design Verification - Safety-Related," Revision 3, dated Arpil 17, 1987 This procedure defined the measures applied to verify the adequacy of the design for u fety-related systems, structures, and components.
KPN-E-310 " Design Verification - Special Scope." Revision 4 dated
April 10. 1987.
This procedure defined the measures to verify the adequacy ot the design for special scope structures systems, and components.
KPN-F-313, 'Nsign Document Change Notice," Revision 2, dated March 18, 1986.
This procedure defined the methods of preparation, review and approvo' of tSe Design Document Change Notice (DDCN).
I KPN-E-314. " Disposition of Nonconformance Reports, Engineering
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Evaluation Requests, Field Change Requests and Corrective Work Requests," Revision 5, dated April 22, 1987. This procedure prescribed the methods and responsibilities for processing
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5 Nonconformance Reports (NCRs). Engineering Evaluation Requests (EERs),
Field Change Requests (FCRs) and Corrective Work Requests (CWRs) and the method to be used in providing technical evaluations.
Bechtel Procedure 3.lf.(A)-30, " Criteria and Instructions for Performing 10 CFR 50.59 Safety Evaluations FSAR Changes / Technical Specifications (NUREG - 1136 - Wolf Creek Generating Station, Unit No. 1) Changes," Revision 3, dated March 14, 1986. This procedure applies to the performance of licensing and safety reviews by Bechtel engineering personnel for all changes, tests, or experiments.
associated with WCNOC requests for a new design or design changes..
Bechtel Procedure 3.16(B)-30, " Criteria and Instructions for
Performing and Documenting ALARA Reviews," Revision 2, dated March 14, 1986. This procedure applies to design changes requested of Bechtel engineering by WCN0C.
Bechtel is responsible to ensure that radiation exposures to plant operating personnel will be'ALARA for that portion of design changes assigned to Bechtel.
.Bechtel Procedure 3.16(E)-30, " Fire Protection Reviews," Revision 2,
dated March 14.-1986. This procedure described the methods'to be used in reviewing.ducuments that apply to fire protection reviews by engineering personnel for design chances to systems, components, or structures which are safety-related,'and design changes which could affect the results of the fire hazards analysis previously performed.
KP-1011. "PMR Tracking and Status Accounting," Revision 2, dated November 11, 1986. This procedure establishes configuration
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management responsibilities and methods for PMR tracking and closeout verification.
Also, reviews were conducted of WCNOC quality assurance audits / surveillance and of Bechtel QA audits.
WCN0C Audit / Surveillance Numbers Title TE:
50140-K112 Modifications TE:
50140-K149 Bechtel Site Activities TE:
50140-K153 Modifications TE:
53359 S-1553 Configuration Management TE:
53359 S-1555 Design Control (Bechtel)
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WE-31/85 Design Control / Document Control WE-31/86 Design Control / Document Control
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Based on a review of the design change program, as described in the saa1 pled procedures and the QA audits, the NRC inspector was satified that the licensee conducts changes and modifications per these procedures, and that the procedures adequately describe the design change and modification process. The procedures reviewed encompass the activity as purposed.
For example, Procedure KPN-E-303, " Calculations," provides sufficier.t detail to allow the engineer to properly document his activities.
The NRC inspectors selected four safety-releted biodification packages in which the activity was finished to verify their implementation. The NRC
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. inspector verified that:
the changes had been reviewed and approved in accordance with 10 CFR 50.59, Technical Specifications, and QA/QC controls; tests were conducted and test results were reviewed / evaluated, if required; operator procedures and as-built drawings were changed; discipline training was modified, as needed; work requests required appropriate controls in welding, ALARA (radiation work pennits), plant mode restraints and system operability, security system and ASME Section XI; the design changes selected were listed on the 10 CFR 50.59(b) annual report to the NRC; and for partially completed modifications system boundaries were controlled to prevent inoperability of plant systems.
The design change packages reviewed are summarized below:
l PMR 00657, Revision 3, " Boric Acid Storage Tank Diaphragms," was i
originated to alter the attachment configuration of the diaphragm, dust cover, to the boric acid tanks.
PMR 00358, Revision 3, " Transformer No. 7 Control, Indication and Metering," was originated to install a transformer in the switchyard and to provide control room control and indication.
This is an alternate power supply to engineered safety feature Transformer No. One.
PMR 01518, Revision 1, " Diesel Generator Lube Oil Keep Warm Pumps,"
was implemented to meet licensing commitments and upgrade the commercial grade pumps to ASME Section III pumps.
PMR 01911, Revision 0, "CRDM and Reactor Cavity Ductwork Rework,"
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provided necessary steps to implement a "backout" field change request providing the necessary control of system boundaries until the modification could be reimplemented, j
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The NRC inspector confirmed that work requests provided information for implementing the plant modification package, testing requirements, i
supporting organization activities, RWPs, welding permits, and any TS
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requirements.
No. violations or deviations were identified.
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Exit' Interview The inspection scope and findings were sumarized on October 30, 1987, with'
those persons indicated in paragraph 1.
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