IR 05000267/1986005
| ML20140B340 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 02/20/1986 |
| From: | Jaudon J, Skow M NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20140B336 | List: |
| References | |
| 50-267-86-05, 50-267-86-5, NUDOCS 8603240036 | |
| Download: ML20140B340 (4) | |
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% . . t > APPENDIX s U.S. NUCLEAR REGULATORY COINISSION ' ' ' ' ' REGION IV ,
, ., i .NRC Inspection Report: 50-267/86-05 License: DPR-34 ' Docket: 50-267.- ' ' ' ' Lii:ensee: Public' Service Company of Colorado ~ - - - '
- P. 0. Box 840 ? ' Denver, CO 80201 ._
, ' Facility. Name: Fort St.-Vrain' Nuclear Generating Station - ' ' ' - Inspection At: Fort.St. Vrain Nuclear Generating Station, Platteville, - Colorado _ ' ' ' sInspection Conducted: January 27-31, 1986 ' Ins'pectors: M![[ 2//r/S% .,- M. E. Skow, Project Engineer, Project Date Section A, Reacto Projec ranch Approved: _ z2,4/ M M /d J./P. @u o,~Ibief, Prtrject S~ection A,- Dats (Reactor rojects Branch Inspection Sumary Inspection Conducted January 27-31, 1986 (Report 50-267/85-06) Areas Inspected:. Routine, unannounced inspection of design changes. The inspection involved 36 inspector-hours onsite by one NRC inspector.
Results: ~ Within the area inspected, no violations or deviations were Tdentified.
8603240036 060307 PDR ADOCK 05000267 O PDR , k
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Persons Contacted
- J. W. Gahm, Manager, Nuclear Production
'
- C. L. Fuller, Station Manager
- L. W. Singleton, Manager, Quality Assurance
- D. Warembourg, Manager,' Nuclear Engineering
- R. L. Craun, Nuclear Site Engineering Manager
- M. H. Holmes, Nuclear Services Manager
- M. J. Ferris, QA Operations Manager
.
- F. J. Borst, Support Services Manager L
- F. J. Novachek, Technical / Administrative Services Manager
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- T. Prenger, QA Services Manager T. Johnson, Results Senior Engineer J. Gawlik, NED Senior Technician
- Denotes those present at the exit interview.
2.
Design Changes The purpose of this inspection was to ascertain that design changes and modifications that were determined by the licensee to not require approval by the NRC are in conformance with the requirements of the Technical Specifications.and 10 CFR 50.59.
The NRC inspector reviewed the following procedures and documents: Procedure Issue Date Title
_ ENG-1
08-28-85 Control of Changes and Modifications ENG-2
08-28-85 Change Notice (CN) Design Output Packages . ! .ENG-3
01-08-86 Control of Design Documents Q-3
09-23-85 Design Control System TASMAP-7
01-10-86 Fort St. Vrain Work Review Committee Guidelines Change Notices Controlled Work Procedures 1298 1298A 2037 85-922 2110 85-656 2058 85-553 1576 ' 1391 83-117, 83-135 , L
7.. - - _ , __ - _.. s ~ > .- .. . _ b-3- , Temporary Configuration Report 8221102 (associated with Change Notice 1576) Some of th C'hange Notices (CNs) were selected for review from the licensee's-report to the NRC of changes,' tests, and experiments not requiring prior Commission approval, as required by 10CFR50.59(b). Others ' were' selected that were being performed under revised licensee procedures ' but which had~not necessarily been included in an annual 10CFR50.59(b) report to the NRC. As a result, not all of the CNs had actually been installed and completed.
The NRC inspector reviewed the selected Change Notices (CNs) to verify that they had been reviewed and approved in accordance with regulations, technical specifications, and procedures. The safety evaluations were also reviewed to ensure that the licensee examined potential consequenses of system or component-failure. Controled Work Procedures (CWPs) are the - licensee's means of~controling the actual installation and testing of the CN. Where CWFs had been prepared for completed CNs, the NRC inspector . included the CWPs in the CN review. This overall review also ascertained r', the adequacy of post modification test and records, as-build drawings, and-appropriate controls of the work process.
Control Room drawings and other ' controlled drawings were checked to verify that they had been revised and . properly distributed.
' While most of those items that the NRC inspector reviewed appeared ": satisfactory, one CN was noted for further discussion. CN 1576 was a modification to the Plant Protective System (PPS) to' prevent a Loop Dump - below 20% feedwater flow.
(This was the original GA design.)
The functional test that was perfomed on CN 1576, tested only that there t a was 'an inhibit to the Loop Dump signal below 20% feedwater flow. The ~ ' acceptance criteria was the " contacts are open, resistance [ greater than] ' 0[ ohms]." The functional' test did not verify that the inhibit was defeated above 20% feedwater flow or that the inhibit came on and off , within a specified tolerance of 20% feedwater flow. The NRC inspector ' also questioned the zero ohms limit in the acceptance criteria.
It is , normal that some small line resistance would be observed with closed . . contacts.. These closed contacts as well as dirty open contacts could then pass the acceptance criteria. During discussions with the licensee, the licensee stated that they would reevaluate the functional test and perform i < appropriate additional' tests. The NRC inspector also noted that the CN ' ' 'was issued for document update only and that the Temporary Configuration ', . Report, TCR 821102, covered the physical change and functional testing.
i The. evaluation of the older TCRs and ' adequate functional testing was discussed in previous NRC~ inspection reports. NRC Inspection , - Report 50-267/85-33 cited inadequate safety evaluations of TCRs.
NRC ' Inspection Report 50-267/85-31 discussed post-modification tests in CNs.
- NRC Inspection Report 85-31 noted that procedure TASMAP-7 was being revised to ensure the adequacy of test procedures.
The apparent -
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.e-inadequatefunc'tionaltestbfTCR 821102 an'd CN'1576 appears similar to ' the. cases noted in the earlier reports. ; In the. opinion of the NRC - . ' inspector, the revision to TASMAP-7 that was recently i~ssued provided . - '~ controls'that would have ameliorated the functional test of TCR 821102 and-CN 1576.
, - . Since th'e function test situation ofI TCR 821102 and.CN 1576 was similar to previous NRC findings and because ' corrective action has been taken to
preclude future recurrences, no violation'is being issued. However, the reevaluation of the functional test and performance of the appropriate-i.
, ' additional tests is, considered an Open Item (50-267/8605-01).
.. . 3. - Exit Interview h- - . 31, 1986, with those personnel- . ' -An exit interview was' held on January , denoted in paragraph'luof this report. The NRC senior resident inspector .also attended this meeting. -At the meeting, the scope of the inspection .and findings were summarized.
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