ML20199B356
| ML20199B356 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 11/13/1997 |
| From: | Powers D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| To: | Hutchinson C ENTERGY OPERATIONS, INC. |
| References | |
| NUDOCS 9711180285 | |
| Download: ML20199B356 (7) | |
Text
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4 ARLINGTON TE XAS 76011806d November 13,1997._
C. Randy Hutchinson, Vice President Operations iArkansas Nuclear One
.Entergy Operations, Inc.
1448 S.R. 333 Russellville, Arkansas 72801-0967
SUBJECT:
NRC INSPECTION REPORT 50 313/98-01; 50-368/98-01
Dear Mr. Hutchinson:
The purpose of this letter is to announce our Maintenance Rete Baseline Team inspection
- at your Arkansas Nuclear One, Units 1 and 2, reactor facilities. We have scheduled this inspection for January 26-30,1998. The designated inspection team leader, Mr. Paul C. Gage, of this office, will make arrangements with your staff to telephonically
. discuss the inspection plans in more detail.
The inspection objective will be to evaluate the effectiveness of your initial activities establishing baseline conditions to support compliance with the requirements of 10 CFR 50.65. The inspection will be conducted using Inspection Procedure 62706,
" Maintenance Rule." This inspection willinvolve a team of about nine NRC and contractor personnal.
The inspection team will require information about your program and its implementation for t1eir in office prepcration for the inspection. A description of the material that may be needed is in the enclosure to this letter. Our designated team leader will be contacting your staff and arranging for specific material to be available to the team by January 5,1998.
If you have any questions concerning this inspection, please contact Mr. Gage at 817/860 8273 or myself at 817/860-8195.
Sincerely, bh W
Dr. Dale A. Powers, Chief Maintenance Branch Division of Reactor Safety I l Docket No.: 50-313; 50-368 i
License'No.:- DPR 51; UPF-6 9711195285971113 i
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. Entergy O'perations, Inc. -
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Enclosure:
l As Stated i
cc w/ enclosure:
-Executive Vice Presicant & Chief Operating Officer i Entergy Operations, inc:
P.O. Box 31995 i
Jackson, Mississippi 39286-19951
= Vice President -
. Operations Support Entergy Operations, Inc.
. P.O. Box 31995-EJackson, Mississippi 39286 Manager, Washington Nuclear Operations ABB Combustion Engineering Nuclear Power 12300 Twinbrook Parkwa;, Suite 330 Rockville, Maryland 20852 County Judge of Pope County Pope County Courthouse-
'Russellville, Arkansas.72801
- Winston & Strawn 1400 L Street, N.W.
Washington, D.C. 20005 3502 David D. Snellings, Jr., Director-
. Division of Radiation Contre,! and Emergency Management Arkansas Departme'it of Health 4815 West Markham Street,- Mail Slot 30
. Little Rock, Arkansas 72205 3867
- Manager.
Rockville Nuclear Licensing Framatome Technologies
-1700 Rockville Pike, Suite 525 Rockville, Maryland -20852
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o-Entergy Operations, Inc... E-Mail report to T. Frye (TJF)-
L E-Mail report to T. Hiltz (TGH)
E-Mail report to NRR Event Tracking System (IPAS)
~ E-Mail report to Document Control Desk (DOCDESK)
E Mail report to Richard Correia (RPC)
' E Mail report to Frank Talbot (FXT) bec to DCD (IE01) bec distrib, by RIV:
Regional Administrator Resident inspector DRP Director MIS System Branch Chief (DRP/C)
R:V File Project Engineer (DRP/C)
DRS-PSB Branch Chief (DRP/TSS)
' DOCUMENT NAME: R:\\ ANO\\AN801LT.PCG To receive copy of document, Indicate in box:"C" = Copy without enclosures "E" = Copy with enclosures "N" = No copy -
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OFFICIAL RECORD COPY.
O Entergy Operations, Inc. E-Mail eport to T. Frye (TJF)
E-Mail report to T. Hiltz (TGH)
E-Mail report to NRR Event Tracking System (IPAS)
E-Mail report to Document Control Desk (DOCDESK)
E-Mail report to Richard Correia (RPC)
E-Mail report to Frank Talbot (FXT) bec to DCD (IE01) bec distrib. by RIV:
Regional Administrator Resident inspector DRP Director MIS System Branch Chief (DRP/C)
RIV File Project Engineer (DRP/C)
DRS-PSB Branch Chief (DRP/TSS)
DOCUMENT NAME: R:\\_ANO\\AN801LT.PCG To receive copy of document. indicate in box:"C" = Copy without enclosures "E" = Copy wrth enclosures "N" = No copy RIV:RI l
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-ENCLOSURE-PREINSPECTION REQUESTED ITEMS LIST t
1.
- Copy of Maintenance Rule program 2.
- Copies of proc'edures that directly relate to and support the Maintenance Rule program
- 3.
List of acronyms and alpha-numeric designations of equipment within the scope of the Maintenance Rule (computer printout or computer disk is acceptable)-
4.
- List of structuress systems, and r:omponents (SSCs), or functions, within the scope.
of tH Maintenance Rule - this list should identify thoso SSCs, or functions, that have been ' designated as risk / safety significant and their current performance criteria / goals 5'
List of SSCs, or functions, that were excluded from the scope of the Maintenance Rule, including justifications for exclusions-6.
List of SSCs, or functions, placed within (a)(1) and (a)(2) categories of the Maintenance Rule 7.
Background explanation for SSCs, or functions, currently assigned tn the (a)(1) category 8.
Results and/or information on historical performance review used to initially identify (a)(1) category SSCs, or functions, for July 10,1996, effective date of Maintenance Rule G.
Risk reduction worth, risk achievement worth, and core damage frequency survey results for SSCs, or functions 10.
Listing of top 20 nonrisk-significznt SSCs, or functions, which were not classified as risk-significant and rationalization for nonrisk-significant classification -
11.
Any updated material to the initial individual plant examination 12.
Updated risk ranking of SSCs, or functions, including the numericalimportance-measure (s) for each SSC, or functions, and the criteria utilized to establish the risk significance of these SSCs, or functions, fnr the Maintenance Rule program 13.
List of.SSCs, or functions, within the probabilistic risk assessment that were -
downgraded / changed to nonrisk significant or excluded from the Maintenance Rule program and the rationale for the changes 14.
. Listing of reliability and availability basic events in the probabilistic risk assessment
- used for risk ranking compared to the performarce criteria established for those
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--SSCs,~ or functione, under the Maintenance Rule program 15.
Criteria or bases used by the expert panel to determine risk significance of S$Cs. or functions,'when the plant is not in Mode 1 16.
- The shutdown safety assessment tool / chart / matrix showing which systems are used _for maintaining decay heat removal, reactor coolant system inventory control, electric power availability, reactivity control, and containment integrity while shutdown 17.
The on-line maintenance procedure / tool / chart / matrix including the bases for risk level determination 4
18.
Current Maintenance Rule program trending data 19.
List of items, events, and conditions that were evaluated for maintenance preventable functional failures (MPFFs) for the previous two fuel cycles, and specific-identification of MPFFs and repetitive MPFFs 20.
Current program performance criteria and goals: also, a list of SSCs, or functions, that are currently classified as " inherently reliable" or "run to f ailure" 21.
Copies of any internal and external Maintenance Rule assessments or related audits 22.
Current organization chart depicting key personnelinvolved in the Maintenance Rule
-implementation and a list of their office telephone numbers 23.
Any add.. 'onal information on organizational (engineering, opt. rations, quality assurance, planning /schedulingi work control and maintenance) Maintenance Rule functional responsibilities 24, Qualification and background of each expert panel member IN ADDITION, THE.INFORMATION BELOW SHOULD BE AVAILABLE TO THE INSPECTION TEAM UPON THEIR ARRIVAL ONSITE 1.
Minutes of expert panel meetings 2.
Copies of corrective action documents and/or proposed corrective actions associated with identification of problems during implementation of the Maintenance Rule
_ program, including probabilistic risk assessment aspects 3.
Listing of spray shields, doors / hatches, and detection alarms assumed operationalin the probabilistic risk assessment for internal flooding
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Copies of senior reactor operator and reactor cperator logs for the last 6 months and copies of any equipment status documents (limiting condition for operation logs, equipment tagging logs, etc.), which provide information what equipment (balance-of plant and safety-related) was out-of-service for the last 6 months l'
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