ML032130258

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Summary of Conference Call Between the U.S. Nuclear Regulatory Commission (NRC) Staff and Carolina Power & Light Company Representatives to Discuss the H.B.Robinson Nuclear Station (Hbrns) License Renewal Application (LRA)
ML032130258
Person / Time
Site: Robinson Duke Energy icon.png
Issue date: 07/31/2003
From: Mitra S
Division of Regulatory Improvement Programs
To:
Carolina Power & Light Co
Cora, MG, NRR/DRIP/RLEP, 415-3148
References
Download: ML032130258 (13)


Text

July 31, 2003 LICENSEE:

Carolina Power & Light Company FACILITY:

H. B. Robinson Nuclear Station

SUBJECT:

SUMMARY

OF CONFERENCE CALL BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION (NRC) STAFF AND CAROLINA POWER &

LIGHT COMPANY REPRESENTATIVES TO DISCUSS THE H. B. ROBINSON NUCLEAR STATION (HBRNS) LICENSE RENEWAL APPLICATION (LRA)

On June 4, 2003, the NRC staff and representatives from the Carolina Power & Light Company (CP&L) held a conference call to clarify the final response to RAI 3.6.1-2, submitted by the applicant on April 28, 2003. A follow-up conference call was held on June 5, 2003, with the objective of providing further clarification on the previous issues.

Enclosures 1 and 2 contain a written summary of the conference calls held on June 4, and June 5, 2003, respectively. The combined list of participants is provided in Enclosure 3. contains the list of questions prepared by the NRC staff that required clarification on the part of the applicant. Enclosure 5 is an email, which contains the list of questions prepared by the NRC staff and the answers provided by the applicant on May 29, 2003.

A draft of this conference call was provided to the applicant to allow them the opportunity to comment prior to being issued.

/RA/

Sikhindra K. Mitra, Project Manager License Renewal Section A License Renewal and Environmental Impacts Programs Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.: 50-261

Enclosures:

As stated cc w/enclosures: See next page

July 31, 2003 LICENSEE:

Carolina Power & Light Company FACILITY:

H. B. Robinson Nuclear Station

SUBJECT:

SUMMARY

OF CONFERENCE CALL BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION (NRC) STAFF AND CAROLINA POWER &

LIGHT COMPANY REPRESENTATIVES TO DISCUSS THE H. B. ROBINSON NUCLEAR STATION (HBRNS) LICENSE RENEWAL APPLICATION (LRA)

On June 4, 2003, the NRC staff and representatives from the Carolina Power & Light Company (CP&L) held a conference call to clarify the final response to RAI 3.6.1-2, submitted by the applicant on April 28, 2003. A follow-up conference call was held on June 5, 2003, with the objective of providing further clarification on the previous issues.

Enclosures 1 and 2 contain a written summary of the conference calls held on June 4, and June 5, 2003, respectively. The combined list of participants is provided in Enclosure 3. contains the list of questions prepared by the NRC staff that required clarification on the part of the applicant. Enclosure 5 is an email, which contains the list of questions prepared by the NRC staff and the answers provided by the applicant on May 29, 2003.

A draft of this conference call was provided to the applicant to allow them the opportunity to comment prior to being issued.

/RA/

Sikhindra K. Mitra, Project Manager License Renewal Section A License Renewal and Environmental Impacts Programs Division of Regulatory Improvement Programs Office of Nuclear Reactor Regulation Docket No.: 50-261

Enclosures:

As stated cc w/enclosures: See next page DISTRIBUTION:

See next page Accession no.: ML032130258 C:\\ORPCheckout\\FileNET\\ML032130258.wpd OFFICE PM:RLEP:DRIP LA:RLEP:DRIP PM:RLEP:DRIP SC:RLEP:DRIP NAME MCora YEdmonds SKMitra SLee DATE 7/18/03 7/24/03 7/30/03 7/31/03 OFFICIAL RECORD COPY

DISTRIBUTION: Summary of Conference Call with CP&L, Dated: July 31, 2003 Accession no.: ML032130258 HARD COPY RLEP RF S. K. Mitra M. Cora E-MAIL:

PUBLIC W. Borchardt D. Matthews F. Gillespie C. Grimes RidsNrrDe E. Imbro G. Bagchi K. Manoly W. Bateman J. Calvo C. Holden P. Shemanski H. Nieh H. Walker S. Black B. Boger D. Thatcher R. Pettis G. Galletti C. Li J. Moore R. Weisman M. Mayfield A. Murphy W. McDowell S. Smith (srs3)

S. Duraiswamy RLEP Staff C. Patel B. Desai C Julian (R II)

S. Uttal (OGC)

C. Munson A. Pal

Mr. J. W. Moyer H. B. Robinson Steam Electric Carolina Power & Light Company Plant, Unit No. 2 cc:

Mr. John Moyer, Vice President H. B. Robinson Steam Electric Plant Carolina Power and Light Company 3581 West Entrance Road Hartsville, SC 29550 Mr. William D. Johnson Vice President and Corporate Secretary Carolina Power & Light Company Post Office Box 1551 Raleigh, NC 27602 Ms. Karen E. Long Assistant Attorney General State of North Carolina Post Office Box 629 Raleigh, NC 27602 U.S. Nuclear Regulatory Commission Resident Inspectors Office H. B. Robinson Steam Electric Plant 2112 Old Camden Road Hartsville, SC 29550 Mr. T. P. Cleary Plant General Manager Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, SC 29550 Mr. Chris L. Burton Director of Site Operations Carolina Power & Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, SC 29550 Public Service Commission Post Office Drawer 11649 State of South Carolina Columbia, SC 29211 Mr. C. T. Baucom Supervisor, Licensing/Regulatory Programs Carolina Power & Light Company H. B. Robinson Steam Electric Plant Unit No. 2 3581 West Entrance Road Hartsville, SC 29550 Ms. Beverly Hall, Acting Director N.C. Department of Environment and Natural Resources Division of Radiation Protection 3825 Barrett Dr.

Raleigh, NC 27609-7721 Mr. Robert P. Gruber Executive Director Public Staff - NCUC 4326 Mail Service Center Raleigh, NC 27699-4326 Mr. Virgil R. Autry, Director South Carolina Department of Health Bureau of Land & Waste Management Division of Radioactive Waste 2600 Bull Street Columbia, SC 29201 Mr. Terry C. Morton, Manager Performance Evaluation and Regulatory Affairs CPB 7 Carolina Power & Light Company Post Office Box 1551 Raleigh, NC 27602-1551 Mr. John H. ONeill, Jr.

Shaw, Pittman, Potts & Trowbridge 2300 N Street, NW.

Washington, DC 20037-1128

Mr. B. L. Fletcher III Manager - Regulatory Affairs Carolina Power & Light Company H. B. Robinson Steam Electric Plant Unit No. 2 3581 West Entrance Road Hartsville, SC 29550-0790 Mr. Fred Emerson Nuclear Energy Institute 1776 I Street, NW., Suite 400 Washington, DC 20006-3708 Talmage B. Clements Manager - License Renewal Carolina Power and Light Company 410 South Wilmington Street Raleigh, NC 27602 Mr. Roger A. Stewart Carolina Power and Light Company H. B. Robinson Steam Electric Plant, Unit No. 2 3581 West Entrance Road Hartsville, SC 29550

SUMMARY

OF CONFERENCE CALL BETWEEN NRC AND CAROLINA POWER & LIGHT COMPANY JUNE 4, 2003 RAI 3.6.1-2 On May 28, 2003, the NRC staff requested clarification and electronically submitted several questions to the applicant for clarification (Enclosure 4). On May 29, 2003, the applicant submitted a draft response via email communication (Enclosure 5) for the NRC electrical engineering staff review. A conference call was held on June 4, 2003, to clarify Item 2, which relates to the types of cables used inside and outside containment. The response to Item 2 was incomplete since it did not include the type of cable used inside containment for wide range circuits. The NRC staff informed the applicant, that Rockbestos RSS-6-108/LE cables for source range, intermediate range, and power range circuits were not included in Section 4.4.1 of the LRA.

In addition, the NRC staff requested the applicant to modify the statement in the Operating Experience (OE) Section of Attachment 1, listed on page 275, of the RNP final RAI Response Document (April 28, 2003), to address the site specific and industry wide OE. The applicant agreed to make the requested modification.

SUMMARY

OF CONFERENCE CALL BETWEEN NRC AND CAROLINA POWER & LIGHT COMPANY JUNE 5, 2003 RAI 3.6.1-2 On June 5, 2003, the applicant requested a conference call with the technical reviewer to further clarify the discussion held the previous day between both parties. As a result of the staffs concern discussed during the June 4, 2003, conference call, the applicant stated that the response to Item 2 and 3 (Enclosure 5) were incorrect. Upon further discussion between both parties, the applicant agreed to revise their response to Items 2, 3, 4, and 7, listed in Enclosure

5. In addition, the applicant stated that they need to revise OE of Attachments 1 and 2 of the RAI 3.6.1-2 response submitted in April 28, 2003.

ATTENDANCE LIST CONFERENCE CALL BETWEEN NRC AND CAROLINA POWER & LIGHT COMPANY JUNE 4 & 5, 2003 NAME ORGANIZATION Amar N. Pal NRR/DE/EEIB SK Mitra*

NRC/NRR/DRIP/RLEP Mario G. Cora NRC/NRR/DRIP/RLEP Michael Heath CP&L

  • Member only participated in June 5, 2003, call Note: All members in the list participated via telephone call

Neutron Flux Instrumentation Circuits 1.

Detection of Aging Effects of Aging Management Program for Neutron Flux Instrumentation Circuits should cover both cables and connections and testing should include a combination of tests.

2.

Describe types of cables used inside and outside containment. Are the same cables types used inside and outside containment?

3.

Are any of these cables covered under EQ program? If so, what is the qualified life of the cables?

4.

Provide operating experience of these cables.

5.

How often are these cables inspected, tested, and replaced? Summarize the results of inspection, testing and replacement.

6.

What is I/V test? Is this a power factor or loss factor test? What is the test voltage for this test?

7.

What is the technical basis for the ten year frequency of this test.

From: "Heath, Mike" <mike.heath@pgnmail.com>

To: "SK Mitra (skm1@nrc.gov)" <skm1@nrc.gov>

Subject:

Neutron Flux Instrumentation Circuits.doc Date: Thu, 29 May 2003 12:17:43 -0400 This is my draft response concerning the questions on the alternate E2 program.

Neutron Flux Instrumentation Circuits 1.

Detection of Aging Effects of Aging Management Program for Neutron Flux instrumentation circuits should cover both cables and connections and testing should include a combination of tests.

Response

The purpose of GALL aging management program XI.E2 is to detect reduction in insulation resistance in circuits with low level signals, which is stated in the program description as follows:

"Exposure of electrical cables to adverse localized environments caused by heat or radiation can result in reduced insulation resistance (IR). Reduced IR causes an increase in leakage currents between conductors and from individual conductors to ground. A reduction in IR is a concern for circuits with sensitive, low-level signals, such as radiation monitoring and nuclear instrumentation since it may contribute to inaccuracies in instrument circuits."

Progress Energy proposed an alternate program to GALL XI.E2 to provide a more direct means of determining the condition of the cable system. Insulation resistance, time domain reflectometry (TDR), and current versus voltage (I/V) testing all provide direct indication of the condition of both cables and connections in neutron monitoring circuits and all represent valid tests for the cabling system. A program that performs any one of these tests is sufficient to provide indication of a reduction in insulation resistance. This program allows the plant to perform one or more of these tests, or some other appropriate test, which gives the plant the flexibility to apply the test (or tests), which best meet their needs.

2.

Describe types of cables used inside and outside containment. Are the same cable types used inside and outside containment?

Response

The source range, intermediate range, and power range circuits use Rockbestos RSS-6-108/LE triaxial cables both inside and outside containment. The wide range circuits outside containment use Gamma-metrics Part No. 200722-050 and 200749-101 cable assemblies. The Gamma-metrics cables used inside containment are fully qualified for a harsh environment.

3.

Are any of these cables covered under the EQ program? If so, what is the qualified life of the cables?

Response

The cables, connectors, and penetrations inside containment are in the EQ program and have been evaluated for a 60 year qualified life. While the EQ cables will typically remain connected to the non-EQ cables addressed by this program during testing, they are not required to be tested by this program.

4.

Provide operating experience for these cables.

Response

This program applies to the non-EQ neutron monitoring cables. No operating experience was identified that indicates these cables or connectors have experienced any age related degradation. These cables and connections are all located in mild environments.

5.

How often are these cables inspected, tested, and replaced?

Response

The cabling system for this instrumentation is not inspected, tested, or replaced on a routine basis.

6.

What is I/V testing? Is this a power factor or loss factor test? What is the test voltage for this test?

Response

Current versus voltage (I/V) testing evaluates the neutron monitoring cabling system and detector as a unit. This test injects voltage step changes typically from 0 volts to 500 volts, 800 volts, or 1000 volts, depending on the cable being tested, into the cable/detector system, and measures the resulting current. These results are charted, and the shape and slope of the curve are evaluated, to determine the condition of the cabling and detector system. This is not a power factor or loss factor test. This type of testing is not currently used at RNP but was included in the aging management program for completeness.

7.

What is the technical basis for the 10 year frequency of this test?

Response

This program is for non-EQ neutron monitoring cabling systems. These cabling systems are located in non-harsh environments and none have experienced age related degradation.

Existing operating experience for neutron monitoring cabling systems is associated with cables located in environments exposed to heat, radiation, or moisture. The cabling systems addressed by this program are not exposed to these harsh environments. The 10 year frequency is considered sufficient based on the absence of aging mechanisms or operating experience showing age related degradation.