ML073180716

Request for Information MOD/50.59 Baseline Inspection and Temporary Instruction 2515/166, Pressurized Water Reactor Containment Sump Blockage.

ML073180716
Person / Time
Site:	Byron
Issue date:	11/14/2007
From:	Dave Hills NRC/RGN-III/DRS/EB1
To:	Crane C Exelon Generation Co, Exelon Nuclear
References
IR-08-006
Download: ML073180716 (5)

Text

November 14, 2007 Mr. Christopher M. Crane President and Chief Nuclear Officer Exelon Nuclear Exelon Generation Company, LLC 4300 Winfield Road Warrenville, IL 60555

SUBJECT:

BYRON STATION, UNITS 1 AND 2 INFORMATION REQUEST FOR AN NRC TRIENNIAL PERMANENT MODIFICATIONS, 10 CFR 50.59 (MOD/50.59) BASELINE INSPECTION AND TEMPORARY INSTRUCTION 2515/166, PRESSURIZED WATER REACTOR CONTAINMENT SUMP BLOCKAGE

Dear Mr. Crane:

On January 14, 2008, the NRC will begin a Modifications, 10 CFR 50.59 (MOD/50.59) baseline inspection at the Byron Station, Units 1 and 2. In addition, we intend to complete Temporary Instruction (TI) 2515/166, Pressurized Water Reactor Containment Sump Blockage. This inspection will be performed in accordance with the NRC baseline Inspection Procedures (IP) 71111.02, IP 71111.17 and TI 2515/166. However, please note that in accordance with recent Reactor Oversight Process inspection program realignment results, IP 71111.02 and IP 71111.17 are planned to be combined into a new revised procedure. This procedure is currently under development, but will likely be issued in time for implementation for this inspection. The on-site portions of the inspection will take place on January 14 through January 18, 2008 and January 28 through February 1, 2008.

Experience has shown that these baseline inspections are extremely resource intensive, both for the NRC inspectors and the licensee staff. In order to minimize the inspection impact on the site and to ensure a productive inspection for both parties, we have enclosed a request for documents needed for the inspection. These documents have been divided into four groups. The first group is necessary to ensure that the inspection team is adequately prepared for the inspection. This information should be available to the Regional Office no later than December 10, 2007. The inspection team will review this information and, by December 21, 2007, will request specific items that should be available for review by January 7, 2008, i.e., the second group of documents. The third group of requested documents contains items that the team will review, or need access to, during the inspection and should be available by the first day of the on-site inspection, January 14, 2008. The fourth group lists information necessary to aid the inspection team in tracking issues identified as a result of the inspection. It is requested that this information be provided to the lead inspector as the information is generated during the inspection. It is important that all of these documents are up to date and complete in order to minimize the number of additional documents requested during the preparation and/or the on-site portions of the inspection.

The lead inspector for this inspection is Mr. Langstaff. We understand that our contacts with your organization for this inspection are Mr. Perchiazzi and Ms. Hubert, for technical and regulatory areas, respectively. If there are any questions about the inspection or the material

C. Crane requested, please contact the lead inspector at (301) 415-1082 (through December 7, 2007, or at (630) 829-9747 thereafter) or via e-mail at RAL4@nrc.gov.

In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66

Enclosure:

Modification and 50.59 Inspection Document Request (Information for Preparation Week and Information Available On-site During Inspection) cc w/encl: Site Vice President - Byron Station Plant Manager - Byron Station Regulatory Assurance Manager - Byron Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer, State of Illinois State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission B. Quigley, Byron Station

C. Crane In accordance with 10 CFR 2.390 of the NRC's "Rules of Practice," a copy of this letter and its enclosure will be available electronically for public inspection in the NRC Public Document Room or from the Publicly Available Records System (PARS) component of NRC's Agencywide Documents Access and Management System (ADAMS), accessible from the NRC Web site at http://www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).

Sincerely,

/RA/

David E. Hills, Chief Engineering Branch 1 Division of Reactor Safety Docket Nos. 50-454; 50-455 License Nos. NPF-37; NPF-66

Enclosure:

Modification and 50.59 Inspection Document Request (Information for Preparation Week and Information Available On-site During Inspection) cc w/encl: Site Vice President - Byron Station Plant Manager - Byron Station Regulatory Assurance Manager - Byron Station Chief Operating Officer Senior Vice President - Nuclear Services Vice President - Operations Support Vice President - Licensing and Regulatory Affairs Director Licensing Manager Licensing - Braidwood and Byron Senior Counsel, Nuclear Document Control Desk - Licensing Assistant Attorney General Illinois Emergency Management Agency State Liaison Officer, State of Illinois State Liaison Officer, State of Wisconsin Chairman, Illinois Commerce Commission B. Quigley, Byron Station DOCUMENT NAME: G:\DRS\Work in Progress\Ltr. 11__07 Byron RFI RAL.doc Publicly Available Non-Publicly Available Sensitive Non-Sensitive To receive a copy of this document, indicate in the concurrence box "C" = Copy without attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII RIII RIII NAME DEH for RLangstaff: ls RSkokowski DHills DATE 11/14/07 11/14/07 11/14/07 OFFICIAL RECORD COPY

Letter to Mr. C. Crane from Mr. J. Lara dated November 14, 2007.

SUBJECT:

BYRON STATION, UNITS 1 AND 2 INFORMATION REQUEST FOR AN NRC BIENNIAL PERMANENT MODIFICATIONS, 10 CFR 50.59 (MOD/50.59) BASELINE INSPECTION AND TEMPORARY INSTRUCTION 2515/166, PRESSURIZED WATER REACTOR CONTAINMENT SUMP BLOCKAGE DISTRIBUTION:

RAG1 TEB RFK RidsNrrDirsIrib MAS KGO JKH3 RML2 SAM9 SRI Byron CAA1 LSL CDP1 DRPIII DRSIII PLB1 TXN

INITIAL DOCUMENT REQUEST MODIFICATIONS AND 50.59 INSPECTION DOCUMENT REQUEST Inspection Reports: 05000454/2008006; 05000455/2008006 Inspection Dates: January 14 through February 1, 2008 Inspection Procedures: IP 71111- 02, Changes, Tests, or Experiments IP 71111- 17, Permanent Plant Modifications TI 2515/166, Pressurized Water Reactor Containment Sump Blockage (NRC Generic Letter 2004-02)

Lead Inspector: R. Langstaff, Reactor Inspector (301) 415-1082 through December 7, 2007 (630) 829-9747 after December 7, 2007 I. Information Requested for In-Office Preparation Week The following information is requested by December 10, 2007, or sooner, to facilitate the selection of specific items that will be reviewed during the on-site inspection week. The team will select specific items from the information requested below and submit a list to your staff by December 21, 2007. We will request that certain items be made available to the regional office during the week prior to the inspection (by January 7, 2008). We request that the remaining items selected from the lists be available and ready for review on the first day of inspection. All requested information should cover the time frame from the receipt of information from the last Permanent Modification inspection (February 1, 2006) to the present. If you have any questions regarding this information, please call the lead inspector as soon as possible.

(1) List of permanent plant modifications to systems, structures or components that are field work complete (For the purpose of this inspection, permanent plant modifications include permanent: plant changes, design changes, set point changes, equivalency evaluations, suitability analyses, and commercial grade dedications.)

The list should contain the number of each document, the title, the revision (or date), and the affected system. In addition to the list, please provide a description of each modification and a list of associated calculations and affected procedures.

(2) List of all 10 CFR 50.59 completed evaluations involving: (a) calculations; (b) procedure revisions; (c) changes to the facility (modifications); (d) non-routine operating configurations; or (e) departures in methods of analyses. This list should be limited to calculations, procedure changes, and departures in methods of analysis which have been approved for use; and changes to the facility which are field work complete.

The list should contain the number and title of each document, a brief description of the change, and the corresponding number and type of the affected document 1

Enclosure

INITIAL DOCUMENT REQUEST (i.e., the modification or procedure to which the evaluation applies). The list should NOT include any evaluations in which prior NRC approval was sought and obtained.

(3) List of all 10 CFR 50.59 changes that have been screened out as not requiring a full evaluation involving: (a) calculations; (b) procedure revisions; (c) changes to the facility (modifications); (d) non-routine operating configurations; or (e) departures in methods of analyses.

The list should contain the number and title of each document, a brief description of the change, and the corresponding number and type of the affected document (i.e., the modification or procedure to which the evaluation applies).

(4) List of calculation changes that have been issued for use.

(5) List of corrective action documents (open and closed) that address plant permanent modification or 10 CFR 50.59 issues, concerns, or processes. These documents should also include corrective action documents associated with modification and 50.59 change implementation.

The list should contain the number, title and revision (or date) of each document, the affected system and corresponding documentation (if applicable), and should be sorted in order of significance.

(6) Copies of procedures addressing the following: modifications, design changes, set point changes, equivalency evaluations or suitability analyses, commercial grade dedications, post-modification testing, 10 CFR 50.59 evaluation and screenings, and Updated Final Safety Analysis Report (UFSAR) updates.

(7) UFSAR updates submitted in accordance with 10 CFR 50.71(e)(4). Provide copies of the complete submittal.

(8) Changes including any modification, procedure changes, training, and UFSAR changes that resulted from commitments made in response to Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors.

(9) Names and phone numbers for the regulatory and technical contacts.

(10) Description of system designators/abbreviations used in lists provided.

2 Enclosure

INITIAL DOCUMENT REQUEST II. Information Requested to be Available the Week Prior to Inspection (January 14, 2007 - Request will be made by December 21, 2007)

(1) Copies of all selected items from Section I. This includes copies of associated documents such as calculations, post-modification test packages, 10 CFR 50.59 evaluations or screenings, and any corrective action documents.

III. Information Requested to be Available on First Day of Inspection (January 14, 2008)

(1) Copies of these documents do not need to be solely available to the team as long as the inspectors have easy and unrestrained access to them.

a. UFSAR;

b. Original Final Safety Analysis Report (FSAR) Volumes;

c. Original SER and Supplements (for Original FSAR);

d. FSAR Question and Answers;

e. Quality Assurance Plan;

f. Technical Specifications;

g. Latest IPE/PRA Report; and

h. Vendor Manuals.

(2) Please ensure that other supporting documents for the selected items have been located and are readily retrievable as the team will likely be requesting these documents during the inspections. Examples of supporting documents are:

a. Drawings supporting the modifications;

b. Procedures affected by the modifications; and

c. UFSAR change papers generated due to a 10 CFR 50.59 evaluation.

(3) Current management and engineering organizational chart.

(4) Site phone list.

IV. Information Requested to be provided throughout the inspection (1) Copies of any corrective action documents generated as a result of the teams questions or queries during this inspection.

(2) Copies of the list of questions submitted by the team members and the status/resolution of the information requested (provide daily during the inspection to each team member).

If you have questions regarding the information requested, please contact the lead inspector.

3 Enclosure