IR 05000458/1988004
| ML20151A158 | |
| Person / Time | |
|---|---|
| Site: | River Bend  |
| Issue date: | 03/11/1988 |
| From: | Gagliardo J, Greg Pick NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20151A157 | List: |
| References | |
| 50-458-88-04, 50-458-88-4, NUDOCS 8804060323 | |
| Download: ML20151A158 (7) | |
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APPENDIX U.S. NUCLEAR REGULATORY C0lEISSION
REGION IV
NRC Inspec. ion Report:
50-458/88-04 uperating License:
NPF-47 i
Docket:
50-458 Licensee: Gulf States Utilities (GSU)
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P.O. Box 220 St. Francisville, Louisiana 70775 Facility Name:
River Bend Station (RBS)
Inspection At:
St. Francisville, Louisiana and RIV office InspectionConducthd:
January 25 through February 5, 1988
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Inspector:
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h p G. A.I, Pick, Reactor Inspector, Operational Date
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rob ams Section, Division of Reactor Safety
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f 0 N, Approved:
JS E.Qfgliardo, Chief,OperationalPrograms Date Sectfon, Division of Reactor Safety
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Inspection Summary Insoection Conducted January 25 through February 5, 1988 (Report 50-458/88-04)
Areas Inspected:
Routine, unannounced inspection of design changes and modifications.
Results: Within the area inspected, no violations or deviations were identified, a
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0804060323 880401 PDR ADOCK 05000458
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L DETAILS f
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Persons Contacted
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GSU
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- J. C. Deddens, Senior Vice President
- J. E. Spivey, Senior Quality Assurance (QA) Engineer
- T. F. Plunkett, Plant Manager
- P. O. Graham, Assistant Plant Manager, Operations
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- J. E. Booker, Manager, Plant Oversight
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- D. E. Thomas, Supervisor, Engineering Administration
- A. D. Kowalcziak, Plant Oversight i
- 0. L. Andrews, Director, Nuclear Training
- R. W. Froyer, Director, Projects
- D. R. Derbonne, Assistant Plant Manager
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- H. F. Sankovich, Manager, Engineering Department
- J. H. McQuirter, Licensing Engineer
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J. G. Morris, Mechanical Engineer J. F. Mead, Supervisor, Electrical Engineering H. L. Litherland, Design Ent neer i
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- J. R. Boardman, Reactor Inspector
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- 0. D. Chamberlain, Senior Resident Inspector J
- Attended exit interview.
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Design, Design Changes, and Modifications (37700)
During this inspection, the NRC inspector reviewed activities related to
the modification of RBS structures and/or components.
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i The NRC inspector reviewed procedures related to design change activities.
l Procedures reviewed by the inspector are summarized below:
l ENG-3-006, Revision 3, "River Bend Station Design and Modification l
Request Control Plan," dated April 27, 1987 - establishes
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instructions for initiating, controlling, and documenting actions
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ENG-3-004, Revision 0, "Safety and Environmental Evaluations," dated
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October 23, 1987 - provides the methodology for preparing written
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safety evaluations as required by 10 CFR 50.59.
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i ENG-3-003, Revision 0, "Repair / Replacement Program," dated July 31, t
1987 - describes the overall repair / replacement program for RBS, l
which assures that the rules of ASME Section XI are implemented.
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ENG-3-010, Revision 0, "ASME Section XI Pressure Test Procedure,"
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dated July 30, 1987 - establishes pressure testing requirements
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including frequency, examination method, and acceptance criteria for all pressure retaining components pressure tested to the rules of
ASME Boiler ana Pressure Vessel Code,Section XI.
- ADM-0028, Revision 8, "Maintenance Work Order," dated June 26, 1987 -
provides administrative instructions for identifying, controlling, and documenting maintenance and maintenance-related activities.
This procedure does not apply to environmental qualification or preventive meintenance-related tasks.
- EDP-AA-54, Revision 8, "Engineering Department Guidelines and Instructions for Processing Modification Requests," dated January 20,
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1987 - establishes guidelines and instructions for processing modification requests (MRs) by engineering personnel.
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EDP-AA-55, Revision 1, "Design Walkdown," dated March 9, 1987 -
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provides for conducting walkdowns associated with davelopment of modification requests, piping and instrument diagrams (P& ids), and
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electrical drawings to assist in cbtaining initial information and i
verifying the existing design.
- l EDP-AA-58, Revision 2, "Design Verificatien," dated March 9,1987 -
provides for verification of design work through the use of der.ign
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review, calculations, and/or testing to confirm adequacy of design.
- EDP-AA-64, Revision 6 "Control and Approval of Field Change Notices (FCN)," dated March 24, 1987 - provides for preparation, l
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review, approval, and control of RBS FCN.
l EDP-AA-20, Revision 6. "Enginaering Calculations," dated November 2,
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i 1987 - describes methods to be used in the preparation, review, j
approval, control, and distribution of engineering calculations.
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j EDP-AA-21, Revision 2 "Control Room Document Redline and Review
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Process," dated December 15, 1987 - defines responsibilities and actions to be used to ensure that composite P& ids and the cable block
diagrams (CBD) for RBS depict the design /as-built configuration.
The NRC inspector selected the MRs from the Master Systems Status Report (MSSR).
The sort requested was "Q Class 1 MRs Work Completed Since
j 9/1/86." The MRs selected are listed below:
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i MR Number Subject System 86-0775 Load lists requested for 120/240 vac Electrical
distribution panels and alter panel
cabling.
86-0875 Install blowout panels to stop Containment exfiltration from auxiliary building pressure relief dampers.
86-1107 Replace 3 port cage with 4 port cage Habitability on chiller valves to increase Cv to 120.
86-1133 Install 4 port cage with 4 extra Habitability l
machined ports on system outlet of control building chilled water condensers (related to 86-1107).
86-1585 Reverse direction of inboard Containment Containment Isolation Valves ICMS*S0V35A, -B, and -0
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so that they seal against flow out of
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87-0103 Reroute RHR/RCIC steam line flow-high Instrumentation
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instrumentation sensing line and fill j
with water to correct negative drift.
87-0267 Add drain valve and accumulator at low Electrical /
point to prevent moisture from dripping Containment into H2 analyzer.
I 87-0598 Delete as many snubbers as possible from Reactor Coolant recirculation Loops A and B and frorn RHR System shutdown cooling suction line.
87-0641 Replace 3-inch, 3 port cage control Habitability valves on outlet of control building chilled water chiller condensers with
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l 6-inch control valves (related to HR 86-1133).
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87-0655 Install additional anti-siphoning device Refuel on spent fuel cooling suction line.
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87-0773 Replace Valve 1G33*MOVF031.
Existing Reactor Coolant
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valve was fermanited and repair was System ineffective.
i The modifications were selected because of their potential for requiring functional testing, recalculation, and unresolved safety question determination (USQD).
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The NRC inspector verified for selected design changes that:
MRs were reviewed and approved in accordance with Technical Specifications (TS);
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calculations and design change activities were conducted in accordance
with appropriate specifications, drawings, and other requirements; ASME Section XI repairs and/or testing were conducted in accordance with technically adequate and approved procedures; appropriate controls such as work travelers, weld data sheets, radiation work permits, and Hot Work permits were utilized; and maintenance work orders utilized to implement the MR contained sufficient information to accomplish the task required.
The MRs were reviewed / evaluated to determine that; they were reviewed and
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approved in accordance with 10 CFR 50.59; test results were within established acceptance criteria; any change which altered the safety analysis report was assigned a licensing change notice number and was tracked for inclusion in the 10 CFR 50.59 annual report; and the design cnange scope, installation and inspection requirements, and testing requirements / acceptance criteria were detailed and sufficient to describe the modifications impact on the plant and explicit for field work
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implementation.
The NRC inspector reviewed the calculation related to MR 86-0875.
This MR
installed eight blowout panels, four to a side, to prevent the loss of nonfiltrated air from the auxiliary building roof vent as a result of
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leakage through the dampers.
The NRC inspector expressed concern that the
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calculation was not correct.
During subdivision of the four panels to get a standard panel section for the calculation, there was no accounting made l
for the bolts alon each side of the end panels.
This is an open item
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(458/8804-01) pend ng the licensee's reevaluation.
MR 87-0262 required the installation of accumulators and drains to prevent the accumulation of water in the hydrogen analyzers.
A procedure had not
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been developed nor had steps been added to an existing procedure to require draining of the accumulators.
This is an open item (458/8804-02)
pending subsequent verification and review by the NRC.
The changes in the service water supply to the control building chilled water chiller condensers was an ongoing modification.
The six-inch control valves had been installed by MR 87-0641.
The change of the chiller condensers from 50 to 100 percent capacity will be accomplished via MR 87-0719.
The licensee intends to use two of the chiller condensers
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at 100 percent capacity instead of four chiller condensers at 50 percent
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Followup to confirm the implementation of MR C7-0719 is an open
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item (458/8804-03).
MR 86-1585 reversed the direction of three inboard containment isolation
valves, ICMS*SOV35A, -B, and -D.
The valves had failed their local leak l
rate tee (LLRT) and they were discovered to be installed backwards.
Valve ICMS*S0V3bC and the four outboard containment isolation valves
passed their LLRT and were operable.
Each valve is located on a 3/4-inch sampling line which leads to a hydrogen analyzer.
The hydrogen analyzer i
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samples the containment and drywell atmosphere.
The valves are solenoid I
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operated and remote manually isolated.
Subsequent inspection by the senior resident inspector determined that the sampling process is a closed loop from the building atmosphere to the analyzer and back to the building.
The valvos were designed to remain open under accident conditions to allow continuous monitoring of the conibustible hydrogen content of the building atmosphere.
Upon a loss of power the valves fail
"as is," which is the open or partially open position per their design.
The valves can still be manually closed locally to isolate containment if the situation requires this type of response.
The successful leak rate testing of other valves supported the assumption that no other valves which could result in a loss of containment integrity have been installed backwards.
The NRC inspector reviewed the licensee's process for redlining control room drawings.
From discussions with RBS personnel, the NRC inspector determined that a weakness exists in the verification of redline drawings by the field engineer within the time frame required by Procedure EPP-AA-21.
This is documented in Que.lity Assurance Surveillance Report ES-87-11-41.
Based on the response to the above surveillance report and from discussions vith the Supervisor, Engineering Administration, the NRC inspector was informed that all corrective actions should be completed by the end of Ma-ch 1988. The response, however, did not specify how Engineering plans to prevent recurrence of the concerns specified in Surveillance Report ES-87-11-41. This is an open item (458/8804-04)
pending verification of the licensee's corrective actions.
While reviewing the sample of design changes, the NRC inspector determined that there were no activities required to be implemented as documented on the Departmental Work Responsibility Checklists.
However, if an item needed to be revised / updated (i.e., Station Operating Manual) before the system could be declared operable, a work tracking FCN was issued to assure completion of the activity.
A good practice implemented administratively, although not proceduralized, is the periodic routing of the MR log to maintenance and operations.
This identifies to these departments which MR checklists are outstanding and which need to be addressed. This should aid in preventing any department from delaying MR closecut due to paperwork problems.
No violations or deviations were identified during the review of tnis program area.
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Exit Interview The NRC inspector summarized on January 29, 1988, the inspection scope and findings with those persons identified in paragraph '
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The licensee did not identify as proprietary any of the materials provided to or reviewed by the NRC inspector during the inspection.
A telecon was conducted on February 5, 1988, with Mr. D. E. Thomas, Supervisor, Engineering Administration.
The NRC inspector summarized the changes in the NRC findings identified during the exit held January 29, 1988.
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