ML18066A165

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Notifies That Region III Will Be Conducting Engineering & Technical Support & Corrective Action Insp & Request for Documentation on 980610-10 & 20-24
ML18066A165
Person / Time
Site: Palisades 
Issue date: 06/01/1998
From: Jeffrey Jacobson
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To: Thomas J. Palmisano
CONSUMERS ENERGY CO. (FORMERLY CONSUMERS POWER CO.)
References
NUDOCS 9806050295
Download: ML18066A165 (7)


Text

June 1, 1998 Mr. Thomas J. Palmisano Site Vice President and General Manager Palisades Nuclear Generating Plant 27780 Blue Star Memorial Highway Covert, MI 49043-9530

SUBJECT:

NOTICE OF FORTHCOMING ENGINEERING & TECHNICAL SUPPORT AND CORRECTIVE ACTION INSPECTION AND REQUEST FOR DOCUMENTATION

Dear Mr. Palmisano:

NRC Region Ill will be conducting an engineering and technical support and corrective action inspection at the Palisades Nuclear Generating Plant. The onsite weeks of this inspection will be July 6 -1 O and July 20 - 24, 1998. This inspection, which addresses NRC inspection procedures 37550 and 40500, is required to be performed once each SALP cycle.

The inspection will consist of five people: four Region Ill staff and one contractor. The minimum staffing necessary to perform the 37550 and 40500 inspection procedures is three people for two and one half weeks; however, an additional inspector was in order to allow review of the numerous items opened in previous NRC reports.

These inspections have previously been found to be rather resource intensive. In order to ensure a productive inspection for both sides, we have enclosed a request for documents needed for.the inspection. These have been divided into three groups: the first we would appreciate being mailed or faxed to Region Ill as expediously as possible. This will allow the inspectors to determine which modifications they will review in more detail and allow your staff time to obtain copies of those modifications and supporting documents. The second group we would like to have available to be picked up on site on June 25. These documents will then be reviewed in the Region Ill office during the week of June 29, prior to the first onsite week. The final group are procedures and other documents which the team will need access to during the inspection.

We have also enclosed a list of items previously opened in NRC inspection reports or discussed in licensee event reports.

  • We would appreciate it if you would review this list and determine which items have all corrective actions completed and are ready for closure. The list should be marked up with this information, along with the name of a cognizant individual and returned with
  • the modifications list.

9806050295 980601 PDR ADOCK 05000255 Q

PDR

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The team leader for this inspection is Ms. Patricia Lougheed. She can be reached at (630) 829-9760. We understand that the Palisades contact is Mr. Kerry Toner and will be dealing with him as the date of the inspection draws closer.

We appreciate yo.ur cooperation with this inspection.

Sincerely, John M. Jacobson, Chief Lead Engineers Branch Division of Reactor Safety Docket No. 50-255 License No. DPR-20

Enclosures:

1. Required Document List
2. List of Previously Opened Items and Licensee Event Reports cc w/encls:

Robert A. Feriech, Senior Vice President, Nuclear, Fossil and Hydro Operations Nathan L. Haskell, Director Licensing Richard Whale, Michigan Public Service Commission Michigan Department of Environmental Quality

. Department of Attorney General (Ml)

Emergency Management Division, Ml Department of State Police DOCUMENT NAME: G:DRS\\PAL05298.DRS' (SEE PREVIOUS CONCURRENCE)

To* receive a co OFFICE Riii Riii NAME Lougheed:sd Burgess DATE 06/ /98 06/ /98 OFFICIAL RECORD COPY

The team leader for this inspection is Ms. Patricia Lougheed. She can be reached at (630) 829-9760. We understand that the Palisades contact is Mr. Kerry Toner and will be dealing with him as the date of the inspection draws closer.

We appreciate your cooperation with this inspection.

Sincerely, John A. Jacobson, Chief Lead Engineers Branch Division of Reactor Safety Docket No.: 50-255 License No.: DPR-20

Enclosures:

1. Required Document List
2. List of Previously Opened Items and Licensee Event Reports cc w/encls:

Robert A. Fenech, Senior Vice President, Nuclear, Fossil and Hydro Operations Nathan L. Haskell, Director Licensing Richard Whale, Michigan Public Service Commission

Emergency Management Division, Ml Department of State Police DOCUMENT NAME: G:DRS\\PAL05298.DRS To receive a co OFFICE Riii NAME Lougheed:sd DATE 0512.1\\/98

' OFFICIAL RECORD COPY

,_,....... e T. Palmisano Distribution:

CAC (E-Mail)

Project Mgr., NRR w/encls C. Paperiello w/encls J. Caldwell w/encls B. Clayton w/encls SRI Palisades w/encls DRP w/encls TSS w/encls DRS w/encls RI 11 PRR w/encls PUBLIC IE-01 w/encls Docket File w/encls GREENS i r.::. {) 0 1 8 I.

Palisades E& TS Inspection System Emphasis and Information Request Information Requested Expeditiously The following information is requested to be provided as soon as possible. This is necessary to facilitate the team selection of modifications, temporary modifications, or setpoint changes to review during the inspection so that that the licensee has time to make copies.

List of facility changes performed during last refueling outage or planned for next refueling outage List of setpoint changes performed during last refueling outage or planned for next refueling outage List of open temporary modifications, including estimated closure date II.

Information Requested by June 25 The following general information is requested to be available to be picked up during a one day trip for badging and document picku*p (probable June 25)

Engineering training program documentation (course requirements and outlines)

List of open/closed operability evaluations for the last year List of open corrective action items List of any open engineering-related operator "work-arounds" List of current TS interpretations or clarifications List of 50.59s/50.59 screenings or safety evaluations, that are not associated with modifications, and were completed in the last year List of root cause analyses performed in last year List of self-assessments in engineering, or other areas, performed in the last year Ill.

Information Requested to be Available on-July 6 We request that the following information be available to the team once it arrives onsite.

Documents such as the updated final safety analysis report (UFSAR) or technical specifications (TS) do not need to be solely available to the team (i.e., they can be located in a reference library) as long as the team has ready access to them.

Current organization chart UFSAR including Questions and Answers Technical Specifications Engineering procedures, especially related to facility changes, temporary alterations, and safety evaluations Surveillance procedures System operating procedures IPE/PRA report Vendor manuals

  • System descriptions or design basis documents, if available

. 't System P&IDs, electrical schematics, and other drawings List of system and design engineers, including assigned systems or design specialty List of pre-established engineering meetings Generic correspondence (INs/GLs/SILs/etc) over last 2 years and documentation of how handled by plant Vendor or industry operational experience feedback (such as SERs, SOER or

  • SILs) documents, along with resolution of the issue as applicable to Palisades NPAD audits related to the corrective action process ISEG (or equivalent) reports for last year On and offsite safety committee meeting minutes and schedul~

Schedule of surveillance and maintenance activities for the weeks of July 6 and July 20 (second week may be provided at begining of second week onsite)

Copies of modifications, temporary modifications, or setpoint changes, including associated screening or safety evaluation, as chosen by the E& TS team from the originally provided lists List of calculations that support the modifications chosen from item 1 above (licensee should be prepared to provide copy of calculations, if requested)

Please note that the E& TS team will review the lists obtained on June 25 during the inspection preparation week and may request copies of documents to be available during the week of July 6th. Should the documents requested be longer than one or two pages, please inform the inspector of the time that will be necessary to photocopy or otherwise provide the document.

Additional requests for information will probably be made, especially during the first week of inspection.

2

Previously Open Items and Licensee Event Reports The E& TS team would like to review the following items to determine if the issues have been resolved such that the items could be closed. In order to facilitate this review, the team requests that "closure packages" be prepared that describe what actions were taken to resolve the issue and which provide appropriate documentation to substantiate those actions (i.e., copies of procedures; training records, etc.)

Previously Opened Items 93026-01 93026-02 93026-05

. 93029-01 94002-01 94011-01 94014-27 94014-~8 94014-46 94014-53 94014-55 94104-58 94014-60 94014-61 94014-62 94014-63 94014-64 95010-01 95010-02 95010-03 96017-05 96018-01 Inadequate Design Control Fan Motor Thermal Overload (Escalated violation)

Inadequate Design Control Undersized Coil (Escalated violation)

No Design Control During Breaker Modification (Violation)

Uncontrolled Withdrawal of a Control Rod (Inspection Followup Item (IFI))

Five Examples of SWSOPI Inadequate Corrective Action (Escalated violation)

Cable Separation Issues (Unresolved Item)

  • Relief Valve Data Sheets Accurately Reflect Design Requirements (IFI)

EOG Slow Start Root Cause Evaluafion (IFI)

PCS Cooled Below 70°F Temperature Limit (IFI)

Over Realiance on Operator Actions (IFI)

Temporary Modification Process Wasn't Always Used (IFI)

Lack of Design Basis Information/ No Clear Roles & Responsibilities (IFI)

Plant Configuration Control Weaknesses (IFI)

Electrical Load Growth Program Weaknes~es (IFI)

Fuse Control Program Weaknesses (IFI)

Vendor Manual Control Weaknesses (IFI)

Failure to Use Updated & Controlled Wiring List (Escalated violation)

Inadequate Post-Modification Test (Escalated violation)

Failure to Demonstrate Operability Per TS 3.17 (Escalated violation)

Review Methodology for Analyzing Cable Ampacities & Cable Tray Fill (IFI)

DC Moided Case Circuit Breaker Failures (Unresolved Item)

Licensee Event Reports91-017 93-004 93-007 93-012 93-014 94-005 94-007 94-008-01 94-012 94-015 95-006 96-002&-01

  • Potential Inter-system LOCA with Primary Coolant Pump Fuel Rod-Failure Boraflex Degradation Containment High Pressure & High Radiation Relays Inoperable Nitrogen Supply to Electrical Penetrations Lack of Physical Cable Separation for Redundant Channels EOG Fuel Oil Supply Doesn't Meet Design Basis Lack of Separation or Isolation between 1 E & Non-1 E Thermal Margin Monitor Internal Ground Unqualified Cable Inadequate AFW Low Suction Pressure Setpoints Initiation of TS Required Shutdown Due to Safeguards Cable Fault