IR 05000498/1989032
| ML19325D955 | |
| Person / Time | |
|---|---|
| Site: | South Texas  |
| Issue date: | 10/13/1989 |
| From: | Singh A, Stetka T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML19325D951 | List: |
| References | |
| 50-498-89-32, 50-499-89-32, NUDOCS 8910270225 | |
| Download: ML19325D955 (8) | |
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APPENDIX
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i U.S. NUCLEAR REGULATORY C0lellSS10N
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i NRC Inspection Report: 50-498/89-32 Operating Licenses: NPF-76
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50-499/89-32 NPF-80 j
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Dockets: '50-498
50-499
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Licensee: Houston Lighting & Power Company (HL&P)
i P.O. Box 1700
,i Houston,= Texas 77001 j
Facility Name: South Texas Project, Units'1 and 2 (STP)
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t Inspection At: STP, Matagorda County, Texas
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Inspection Conducted: September 11-15, 1989
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by lo IMD inspector:
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,T A. Singh, HeK tor Inspector, Plant Systems Datit *
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Section, 61 vision of Reactor Safety.
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Approved:.
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T. F. 5tetk6, Chief. Plant'5ystems Section Vate'
i Division of Reactor Safety l
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inspection Sumary'
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- Inspection Conducted September 11-15, 1989 (Report 50-498/89-32)
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Areas Inspected:. Routine, unannounctd inspection of the licensee's program i;
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for accomplishing both permanent and temporary plant design changes and
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modifications. This. inspection also included a review of the licensee's actions on previous inspection findings.
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Results: _ Within the areas inspected, no violations or deviations were l
identified. Overall, the licensee has a comprehensive design change and plant
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modifications program. The plant modifications program is considered to be a
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strength because of the aggressive and comprehensive program implementation and
L the lack of a modification backlog.
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8910270225 891017 c
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PDR ADOCK 05000498 L
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inspection Conducted September 11-15, 1989 (Report 50-499/89-32)
- Areas-Irispected: Routine, unannounced inspection of the licensee's actions on l
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previous inspection findings.
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Results: Within the areas inspected, no violations or deviations were
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identified. The previous inspection findings were reviewed and found to be'
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adequate.
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f DETAILS
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Persons Contacted'
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HLAP j
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- *R. W. Chewning, Vice President. Nuclear Operations I
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- D. M. Chamberlain, Plant Engineering l
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'C. A. Ayak, Supervisor Engineer i
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- V. A. Simons, Plant Operations Manager i
- J. W. Loesch, Plant Operations Manager
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- A. W. Harrison, Supervising Licensing Engineer
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- W. H. Kinsey, Plant Manager
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- W. J. Jump, Maintenance Manager
- A. K. Khosla, Senior Licensing Engineer
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- J. T. Minor. Construction Ennineer
- R. C. Munter, Division Manager Electrical
- P.'R. Desai, Quality Engineer i
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- W. S. Blair, Maintenance Support Manager l
- M. R. Wisenburg, General Manager i
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- M. A. McBurnett, Licensing Manager
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- S. K. Hubbard, Quality Control Supervisor i
- J. D. Green, Manager, Inspection and Surveillance
- A. C. Mantyre. Manager, Support Engineer
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- S. M. Dew, Manager, Operations Support i
- T. J. Joroan, Manager, Plant Engineering
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- G. L. Parkey, Manager, Integrated Planning and Scheduling
- J. R. Lovell, Technical Services Manager NRC l
- J. E. Bess, Senior Resident Inspector (SRI), Unit 1
- R. J. Evans, Resident Inspector, Unit 1
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I. Tapia, SRI Unit 2
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- D. Hunnicutt Senior Project Engineer
- M. Murphy, Reactor Inspector, Region IV
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- J. P. Jaudon, Deputy Director, Division of Reactor Safety, Region IV
- H Bundy, Reactor Inspector, Region IV
- R. Azua, Reactor Inspector, Region IV
- W. McNeill, Reactor Inspector, Region IV i
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- W. C. Seidle, Chief. Test Programs Section, Region IV
- Denoted personnel attending exit meeting September 15, 1989.
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2.
Licensee Actions on Previously identified Items
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(Closed)Openitem(498/8763-01): This issue addressed the fact that the preventive maintenance (PM) program, especially for the Class IE batteries was not being performed on the scheduled due dates.
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E The inspector noted that the licensee has aggressively pursued improvenents in the preventive maintenance program such that the i
completion of preventive maintenance for safety-related components are i
meeting due dates. Therefore, this item is considered to be closed.
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Design. Design Changes, and Modifications (37700)
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The purpose of this inspection was to astess the licensee's aerformance in
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the area of design changes. Specifically, selected design c1anges were i
reviewed to detemine if they were made in accordance with the requirements
,i of 10 CFR 50.59 and therefore did not compromise plant safety.
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Plant Modifications Program i
The licensee has a very comprehensive plant t.odification program and
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process;.1he plant modification process is administered in accordance-i with Procedure I.P.3.1.0, Revision 6. " Plant Modification." dated
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July 28, 1989. A modification request can be initiated by anyone in j
the plant and submitted to the imediate supervisor for preliminary evaluation. The preliminary evaluation is performed by the engineering
modification coordinator who verifies that the suggested change has
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not been previously initiated, assigns the priority, and issues the
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modification to an appropriate engineering design discipline for the i
preparation of the nodification package.
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The modification package is the document which describes the total
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modification and provides a listing of all documents and components affected.
It also summarizes the description, the justification, the
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safety analysis report, and the priority of.the modification and
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associated drawings.
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All the modification packages are reviewed by the Modification Review
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Connittee, Management Review Board, end Nuclear Plant Operations F
Department. The cognizant engineer is responsible to assure that all required testing, procedure changes, and return to service activities are performed. When all modification closeout reviews'and actions
are completed the modification package is returned to support engineering for final engineering review and closure of the package.
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Interviews with different organizations onsite indicated that they l
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were knowledgeable of the modification process. The inspector
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followed the process through these various organizations and found l
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l that it appears to be functioning properly from initiation of the package to closeout.
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Procedure Review
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The inspe'ctor reviewed the licensee's procedures concerning permanent
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and temporary design changes and modifications. These procedures e
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i established administrative controls and responsib'ilities for the
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design change / modification progrem for the South Texas Project,
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Unit 1 ($1P-1).
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The licensee's procedures relating to the control of design changes I
and niodifications are in conformance with regulatory requirements,
commitments, and industry guides and standards. These procedures are i
listed in the Attachment A.
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Review and Observations of plant Modification packages The inspector selected six pemanent and three temporary modification packages for review. Four of these modifications were verified by
walkdown in the field with the latest revised documents. The modification packages reviewed are listed in the Attachment B.
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During this review, the inspector examined the modification packages
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to verify proper implenentation and adequate technical content.
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These packages included independent review, approval and design
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verifications by the eppropriate organizations and indicat6d proper adherence to approved procedures. All the packages reviewed were l
approved by Nuclear Plant Operations Department Modification Review i'
Committee and Management Review Board. The inspector also verified that the operator training programs were revised to incorportte the
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modification changes. The inspector noted that the operator training
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was conducted prior to the modifications being declared operable.
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The licensee also has procedures in place to coordinate with support
engineering on reviews of the modification packages for impact on the
sinulator design and the plant training program. Review of packages
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.also indicated that arior to the design change / modification being declared operable, tie controlled copies of es-built docunents were revised and distributed.
In addition, the control room drawings were
" red lined" in a timely manner to indicate the modification change.
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the Final Safety Analysis Report. The packages reviewed contained
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detailed 10 CFR 50.59 reviews.
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Conclusion The Plant Modification Program is comprehensive, and all the licensee
organizations responsible for initiation and implementation of the program fully understand the process. The inspector's review concluded that the Plant Modification Program is functioning properly as indicated by the lack of a backlog in this program.
No violations or deviations were identified.
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Exit Interview l
An exit interview was held on September 15, 1989, with the personnel
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l indicated in paragraph 1 of this report. At this meeting. the scope of the inspection and findings were sumarized. The licensee did not
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identify as proprietary any information provided to or reviewed by the l
inspector.
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ATTACHMENT A
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Procedure No.
Title Date OPGP03-ZE-0031 Design Change Inglementation May 28, 1089
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IP-3.10 Plant Modifications July 28, 1989 Revision 6
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IP-1,38 Plant Integrated Living Schedule November 9, 1987
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Revision 0
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OPGP03-ZO-003 Temporary Modifications and June 15. 1988 Revision 9 Alterations OPGP03-ZE-0001 Database and I/O List Control May 2, 1989 Revision 1 IP-3.28Q Maintenance of Key Drawings Revision 0
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ATT/sCHMENT B
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MOD.88188, " Relocate the Loose Parts Monitoring Systems (LPMS)
Accelerometer Sensors Located on the Main Access Hatches of the Stema i
Generators" MOD 88246, " Rerouting the Suction Line From Refueling Water Storage Tank
to the Centrifugal Charging Pumps to Eliminate High Point" t
Mod 88276, "To Install Nonsafety-Related Limit Switches on the Contairment Purge Sample Valves" i
MOD 88336, "To Remove Valve CV-0215 from Service and Abandon the Boric
Acid Flush Line, Which is No longer Required Due to Lower Required Boric Acid Concentration"
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MOD 88161, " Replace Valves. Fittings, and Pipes in the Essential Cooling Water System (ECWS) Small Bore Train B"
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l MOD 88174, ' Install Piping Fittings, and Pumps to Allow Condenser
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Waterbox Draindown to Alternate Waterbox"
TI-EH-89-018. " Swap Servo Amp Cards to Allow Governor Valve-1 (GV-1) to be the Controlling Valve at Full Turbine Load"
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TI-EH-89-022. " Essential Chilled Water Electro-Hydraulic Control Valves Actuators are to be Removed" f*
TI-SI-89-044, " Cut the Chemical and Volume Control System (CVCS) Suction Line to Centrifugal Charging Pumps and Install Temporary Caps Plates"
- Indicates field verification
- 1ndicates temporary modifications l
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