ML021010493

From kanterella
Jump to navigation Jump to search
Ltr Dtd 04/10/02 to G Campbell Informing That NRC Will Begin a Biennial Safety System Design and Performance Capability Inspection on 06/10/2002
ML021010493
Person / Time
Site: Perry FirstEnergy icon.png
Issue date: 04/10/2002
From: Jeffrey Jacobson
Division of Reactor Safety III
To: Campbell G
FirstEnergy Nuclear Operating Co
References
Download: ML021010493 (8)


Text

April 10, 2002 Mr. Guy Campbell Vice President - Nuclear FirstEnergy Nuclear Operating Company P. O. Box 97, A200 Perry, OH 44081

Dear Mr. Campbell:

On June 10, 2002, the NRC will begin a required biennial safety system design and performance capability inspection at your Perry Nuclear Power Plant. This inspection will be performed in accordance with the NRC baseline inspection procedure 71111.21. The systems to be reviewed during this baseline inspection are the emergency service water and emergency closed cooling water systems.

Experience has shown that the baseline design inspections are extremely resource intensive both for the NRC inspectors and the utility staff. In order to minimize the impact that the inspection has on the site and to ensure a productive inspection for both sides, we have enclosed a request for documents needed for the inspection. The documents have been divided into two groups. The first is information necessary in order to ensure the inspection team is adequately prepared for the inspection. This information should be available to the Regional Office by no later than May 20, 2002.

The second group of documents requested are those items which the team will review or need access to during the inspection. It is important that these documents be as complete as possible, in order to minimize the number of documents requested during the preparation week or during the onsite inspection.

The lead inspector for this inspection is Patricia Lougheed. We understand that the regulatory contact for the inspection is Kenneth Russell of your organization. If there are any questions about the material requested, or the inspection, please call the lead inspector at 630-829-9760.

G. Campbell In accordance with 10 CFR 2.790 of the NRCs "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 (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/NRC/ADAMS/index.html (the Public Electronic Reading Room).

Sincerely,

/RA/

John M. Jacobson, Chief Mechanical Engineering Branch Division of Reactor Safety Docket No. 50-440 License No. NPF-58

Enclosure:

As stated cc w/encl:

B. Saunders, President - FENOC T. Rausch, Director, Nuclear Maintenance Department G. Dunn, Manager, Regulatory Affairs K. Ostrowski, Director, Nuclear Services Department J. Powers, Director, Nuclear Engineering Department W. Kanda, General Manager, Nuclear Power Plant Department Public Utilities Commission of Ohio Ohio State Liaison Officer R. Owen, Ohio Department of Health

April 10, 2002 Mr. Guy Campbell Vice President - Nuclear FirstEnergy Nuclear Operating Company P. O. Box 97, A200 Perry, OH 44081

Dear Mr. Campbell:

On June 10, 2002, the NRC will begin a required biennial safety system design and performance capability inspection at your Perry Nuclear Power Plant. This inspection will be performed in accordance with the NRC baseline inspection procedure 71111.21. The systems to be reviewed during this baseline inspection are the emergency service water and emergency closed cooling water systems.

Experience has shown that the baseline design inspections are extremely resource intensive both for the NRC inspectors and the utility staff. In order to minimize the impact that the inspection has on the site and to ensure a productive inspection for both sides, we have enclosed a request for documents needed for the inspection. The documents have been divided into two groups. The first is information necessary in order to ensure the inspection team is adequately prepared for the inspection. This information should be available to the Regional Office by no later than May 20, 2002.

The second group of documents requested are those items which the team will review or need access to during the inspection. It is important that these documents be as complete as possible, in order to minimize the number of documents requested during the preparation week or during the onsite inspection.

The lead inspector for this inspection is Patricia Lougheed. We understand that the regulatory contact for the inspection is Kenneth Russell of your organization. If there are any questions about the material requested, or the inspection, please call the lead inspector at 630-829-9760.

G. Campbell In accordance with 10 CFR 2.790 of the NRCs "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 (PARS) component of NRCs document system (ADAMS). ADAMS is accessible from the NRC Web site at http://www.nrc.gov/NRC/ADAMS/index.html (the Public Electronic Reading Room).

Sincerely,

/RA/

John M. Jacobson, Chief Mechanical Engineering Branch Division of Reactor Safety Docket No. 50-440 License No. NPF-58

Enclosure:

As stated cc w/encl:

B. Saunders, President - FENOC T. Rausch, Director, Nuclear Maintenance Department G. Dunn, Manager, Regulatory Affairs K. Ostrowski, Director, Nuclear Services Department J. Powers, Director, Nuclear Engineering Department W. Kanda, General Manager, Nuclear Power Plant Department Public Utilities Commission of Ohio Ohio State Liaison Officer R. Owen, Ohio Department of Health ADAMS Distribution:

AJM DFT DVP1 RidsNrrDipmIipb GEG HBC RJP C. Ariano (hard copy)

DRPIII DRSIII PLB1 JRK1 DOCUMENT NAME: G::DRS\\PER03 02DRS.WPD To receive a copy of this document, indicate in the box "C" = Copy w/o attach/encl "E" = Copy with attach/encl "N" = No copy OFFICE RIII:DRS RIII:DRS NAME PLougheed:aa JJacobson DATE 03/29/02 04/10/02 OFFICIAL RECORD COPY

1 Initial Document Request I.

Information Requested Expeditiously The following information is requested to be provided as soon as possible, but no later than May 20, 2002. All items requested apply only to the selected system(s):

1.

One copy of the system descriptions and design basis documents 2.

One copy of the normal and abnormal operating procedures 3.

Two half-size copies of the piping and instrument drawings 4.

One half-size copy of the functional block diagrams 5.

Two half-size copies of the electrical schematics 6.

Two half-size copies of the single-line and key diagrams 7.

Name and phone numbers of the technical contact, a regulatory contact, and the design and system engineer(s).

8.

List of analyses that either support or take credit for operation of the system(s).

For each analysis, besides the number and title, include the purpose of the calculation, the date, and a technical contact. Clarify any abbreviations or acronyms and give word titles for any numbers (e.g., "residual heat removal inner containment isolation valve" rather than "RH-2301-45B").

Specifically identify (by number) the following calculations. If a calculation cannot be identified for a particular bullet, provide an explanation of why there are no calculations for that area :

Acceptance criteria calculations for all Technical Specification surveillances Breaker coordination calculations Check valve leakage criteria calculations Design basis (flow rates, levels, pressures, temperatures) confirmation calculations (including NSSS calculations)

Diesel loading calculations Electrical separation calculations Heat exchanger calculations NPSH and TDH calculations Operability determination support calculations Pressure transient/ water hammer evaluations Pump minimum recirculation calculations Room temperature environmental qualification calculations for major equipment Relay setting calculations Setpoint calculations for all Technical Specification or Emergency Operation Procedure equipment Tank over-pressurization or relief valve sizing calculations

2 Time delay calculations (for any component incorporating time delay features)

Voltage drop calculations for all major electrical components (motors, MOVs)

Pressure transient/ wWater hammer evaluations 9.

List of all major modifications made to the system since pre-operational testing.

Major changes are those that significantly affected the way the system operated, for example, replacement of major components. Please include the number and title, include the modification purpose, the date, and a technical contact. Spell out abbreviations, or acronyms and give word titles for any numbers. Include setpoint changes in this listing or provide separately.

10.

List of condition reports (corrective action documents) that are in one of the following categories. For each condition report, besides the number and title, clearly designate the status (open/ closed), the importance ranking, the date initiated, the date closed (if applicable), the status of corrective actions, and a technical contact.

Any open condition report initiated more than 2 years prior to the inspection Any condition report (open or closed) initiated in the last 2 years and requiring an apparent or root cause analysis (include analysis)

Any condition report (open or closed) initiated in the last 2 years and requiring an operability determination (include determination)

Any condition report (open or closed) initiated in the last 2 years and relating to engineering problems II.

Information Requested to be Available on First Day of Inspection We request that the following information be available to the team once it arrives onsite.

Some documents, such as the UFSAR or 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.

1.

Copies of the calculations indicated by subject area in item I.8. Please review the calculations and also provide copies of referenced material (such as drawings, engineering requests, vendor letters.)

2.

Copies of all MAJOR design changes or modifications performed since plant startup as indicated in item I.9. Please review the modifications and ensure that any supporting material (such as calculations, drawings or post-modification tests) is also copied and provided.

3.

Copies of any open temporary modifications.

4.

Copies of all condition reports (corrective action documents) indicated in item I.10.

3 5.

Copies of the last two years worth of completed surveillances for ALL Technical Specification equipment.

6.

List of all maintenance, surveillance, and annunciator response procedures related to the system. Include name as well as number. For the surveillance procedures, provide a cross-reference which shows how each technical specification requirement is being met.

7.

One copy of each major equipment drawing (valves, pumps, tanks, strainers),

including pump head curves (1/2 size) 8.

Copies of isometric drawings for major flow paths (1/2 size) 9.

Copies of elementary diagrams (1/2 size) 10.

Copies of wiring diagrams (1/2 size) 11.

Copies of P&IDs referred to on the system P&ID (1/2 size) 12.

Copies of control and instrumentation drawings (1/2 size) 13.

A copy of any self-assessments and associated corrective action documents generated in preparation for the inspection 14.

Reference materials:

Equipment qualification binders General set of plant drawings IPE/PRA report Pre-operational tests, including documents showing resolution of deficiencies Procurement documents for major components in each system (verify retrievable)

Relevant operating experience information (such as vendor letters or utility experience)

Standards used in system design (such as IEEE, ASME, TEMA)

System procedures Technical Specifications Technical Data Book Updated Final Safety Analysis Report Vendor manuals