IR 05000267/1984032
| ML20129A768 | |
| Person / Time | |
|---|---|
| Site: | Fort Saint Vrain  |
| Issue date: | 05/21/1985 |
| From: | Ireland R, Johnson E NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | |
| Shared Package | |
| ML20129A737 | List: |
| References | |
| 50-267-84-32-MC, NUDOCS 8506040728 | |
| Download: ML20129A768 (10) | |
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' , , ' APPENDIX- - . ' U. S. NUCLEAR REGULATORY COMMISSION REGION IV-i - - '
< , , l ' NRC Inspecti^on. Report: 50-267/84-32 License: ~ DPR-34 - ' Docket: -50-267 - - , . '
y , . , ~ ~ ' ' ,, Licensee: -Public Service Company of: Colorado P.-0. Box 840.1 ~ ' '. ~ ' ' , - Denver, Colorado,80201
.. . > Facility Name: Fort'St. Vrain Nuclear Generating-Station + , ,
- ;r Conference Conducted
November 14, 1985 ' t . Report prepared by: " r Y b. O h Y-5/M.Ars ' R. E. Ireland, Chief, Spec'ial Projects and D&te' Engineering Section s , ,
. LApproved: 4' b IK +zw- - E. H. Johnson, Chief, Reactor Projects Branch 1 Date
- Conference Summary
~ .A management conference was held at~.the NRC Region IV offices in Arlington,. , :t Texas; on November 14, 1984, with officials of the Public-Service Company of Colorado to discuss a number of issues related to restart and continued s operation of the Fort St.' Vrain Nuclear Generating Station (FSV). The
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' , discussions covered (a).the major conclusions-of NRC's'0ctober 1984" Assessment Report transmitted to PSC on October 16, 1984, by the Director, Office of.
' Nuclear Reactor Regulation, (b) NRC persp~ectives on management and operation of .the FSV facility, and'(c) current licensing items.
The slides used during- ~ hese' discussions are' attached'to.this report.
t , Results: The. licensee stat'ed that,the Public Service Company of Colorado will.- - sdo whatever is necessary to correct any outstanding problems and that the ' ' company will apply those resources necessary to put the facility in a safe and ' reliable' operating condition.
The NRC staff stated that,' in. addition to issues ' E -
- already. identified, the problems with the reserve shutdown system and the
- control rod suspension cables would have to be resolved prior to restart of the
' B506040728 850522 PDR ADOCK 05000267 O PDR L . - W . 'u _ _ _
_._ . [, - ' ' i E 4,3 ,, . s , , ' t g-2 , reactor. The ' staff also stated that it had not yet determined whether any . specific enforcement actions would be taken as a result of.the problems identified in the assessment report.
Further inspection effort lwould be needed-to make this determination.
. c . It was emphasized that NRC would need a documented commitment from.the < licensee, in the near future, which could be used to form the basis for - 1,' scheduling and planning those NRC. inspection and technical review activities
which would be necessary in connection with supporting a decision to allow the z facility to resume power operations.
The licensee agreed that such information ~would be provided.
, The NRC staff stated that PSC should consider the Assessment Report as examples of_ NRC ~ findings that warrant attention but not-as a necessarily complete compilation.
Each of the Assessment Report actions that would need to be completed prior to restart was briefly summarized.
It was emphasized that PSC ' ~ would need to provide timely and complete documentation for, review by NRC with respect to each of these actions if delays were to be avoided.owing to the need for NRC to request additional information.
It was agreed that a meeting between PSC and NRC technical staff should be scheduled in the near future to discuss actions in greater detail.
-With respect to ongoing licensing actions, the staff emphasized that' PSC should see;early resolution of matters related to the PCRV tendons and that the work ~ related to fire. protection issues.(Appendix R) should get moving.. It was noted that PSC has the lead on resolving technical questions in connection with LC0 4.1.9 and that PSC should either commit to carryout the 100% load rejection test or justify why it need not be done. - With respect to Building 10 structural design criteria and electrical modifications,-the' staff stated that further review was to be done.
> -A number.of items concerning plant management, plant operations and PSC/NRC communication, were discussed.
It was agreed the scope ~and schedule for the management review being carried out for PSC by.the NUS Corporation would be submitted for NRC comment in the.immediate future..PSC also agreed that NUS 1should submit its reports to NRC and PSC simultaneously.
PSC's schedule and ' plans for implementation of any recommendations would be submitted soon thercafter.
~ With respect to. improvement'in communications between PSC and NRC, the staff _ stated that operiness and candor were need to assure that misunderstandings do not occur regarding identification of requirements which must be met and 'the ~ . nature and relevance 'of' commitments made by PSC in meeting those requirements.
It was. stated that, if misunderstandings do arise,L they should be brought to NRC management ~ attention so that clear, singular resolution could be achieved.
~ The staff stated thatlthe forthcoming management audit and the resolution of - technical issues could be' separated.
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., -3. ' ~ 'It was agreed by NRC and PSC~ that'the' e would be need for ' additional meetings r u L at'both1 technical and nanagement levels to assure that. problems needi:iy eresolutionlare. clearly defined and answered and that schedules are established.
'The staff l stated that~its= inspection actiitties would likely be increased to follow PSC activities prior to resumption of reactor operations.
' . , Persons' Participating in:the Conference: . 'NRC: , RIV:1 R. D.1 Martin, Regional Administrator - P.'S..Che'ck, Deputy Regional. Administrator E;iH. Johnson,' Chief,~ Reactor Projects Branch.1
Rn A. Cooley, Chief,' Operator Licensing Section _ - R.' E. ' Ireland, Chief, Special' Projects and Engineering Section - P.C.: Wagner, Project Manager.
D.- A. Powers,1 Technical Reviewer - : , . n :_ J.[T.. Collins.
.NRR: G.-C. Lainas,; Assistant. Director, Operating Reactors, ' Division of Licensing LJ. R. Millen,l Chief, ORB-3 > . i> Licensee: R. F. Walker, President C.'K.1 Millers. Senior 1Vice President, Operations ~ . 0. -R. Lee, Vice President,; Electric Production " 1s.
J.. W. ' Gahm, Manager Nuclear Product ' H. L. Brey, Executive Staff Assistant.
' B. W.1 Diest, Licensee Consultant (NUS) - . State of Colorado: . . . . L :c.
- A. J. Hazle,; Colorado' Department of Health'
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