ML072070591
| ML072070591 | |
| Person / Time | |
|---|---|
| Site: | Beaver Valley |
| Issue date: | 08/22/2007 |
| From: | Nadiyah Morgan NRC/NRR/ADRO/DORL/LPLI-1 |
| To: | Sena P FirstEnergy Nuclear Operating Co |
| Morgan N, NRR/DORL, 415-3650 | |
| References | |
| TAC MD5595, TAC MD5600, TAC MD5602, TAC MD5603 | |
| Download: ML072070591 (7) | |
Text
August 22, 2007 Mr. Peter P. Sena III Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077
SUBJECT:
BEAVER VALLEY POWER STATION, UNIT NO. 2 - REQUEST FOR ADDITIONAL INFORMATION REGARDING THE INSERVICE TESTING PROGRAM THIRD 10-YEAR INTERVAL RELIEF REQUESTS (TAC NOS.
MD5595, MD5600, MD5602, AND MD5603)
Dear Mr. Sena:
By letter dated May 11, 2007, FirstEnergy Nuclear Operating Company (FENOC, licensee) requested approval of proposed alternatives and relief requests associated with the inservice testing (IST) program third 10-year interval update for Beaver Valley Power Station, Unit No. 2 (BVPS-2).
The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has determined that additional information is needed to complete its review for relief requests PRR1, PRR6, PRR8, and PRR9. The specific questions are found in the enclosed request for additional information (RAI). The licensee staff indicated that a response to the RAI would be provided within 30 days of receipt.
Please contact me at (301) 415-1016, if you have any questions on this issue.
Sincerely,
/ra/
Nadiyah S. Morgan, Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-412
Enclosure:
RAI cc w/encl: See next page
- See memo dated July 16, 2007 OFFICE LPLI-1/PM LPLI-1/LA SRXB/BC LPLI-1/BC NAME NMorgan SLittle JMcHale*
MKowal DATE 8/22/07 8/9/07 7/16/2007 8/10/07
Beaver Valley Power Station, Unit Nos. 1 and 2 cc:
Joseph J. Hagan Senior Vice President of Operations and Chief Operating Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 James H. Lash Senior Vice President of Operations and Chief Operating Officer FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Danny L. Pace Senior Vice President, Fleet Engineering FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 Jeannie M. Rinckel Vice President, Fleet Oversight FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 76 South Main Street Akron, OH 44308 David W. Jenkins, Attorney FirstEnergy Corporation Mail Stop A-GO-18 76 South Main Street Akron, OH 44308 Manager, Fleet Licensing FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, OH 44333 Ohio EPA-DERR ATTN: Zack A. Clayton P.O. Box 1049 Columbus, OH 43266-0149 Peter P. Sena III Site Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-SEB1 P.O. Box 4, Route 168 Shippingport, PA 15077 Director, Fleet Regulatory Affairs FirstEnergy Nuclear Operating Company Mail Stop A-GO-2 76 South Main Street Akron, Ohio 44333 Manager, Site Regulatory Compliance FirstEnergy Nuclear Operating Company Beaver Valley Power Station Mail Stop A-BV-A P.O. Box 4, Route 168 Shippingport, PA 15077 Richard Anderson Vice President, Nuclear Support FirstEnergy Nuclear Operating Company Mail Stop A-GO-14 Akron, Ohio 44308 Commissioner James R. Lewis West Virginia Division of Labor 749-B, Building No. 6 Capitol Complex Charleston, WV 25305 Director, Utilities Department Public Utilities Commission 180 East Broad Street Columbus, OH 43266-0573 Director, Pennsylvania Emergency Management Agency 2605 Interstate Dr.
Harrisburg, PA 17110-9364
Beaver Valley Power Station, Unit Nos. 1 and 2 (continued) cc:
Dr. Judith Johnsrud Environmental Coalition on Nuclear Power Sierra Club 433 Orlando Avenue State College, PA 16803 Director Bureau of Radiation Protection Pennsylvania Department of Environmental Protection Rachel Carson State Office Building P.O. Box 8469 Harrisburg, PA 17105-8469 Mayor of the Borough of Shippingport P.O. Box 3 Shippingport, PA 15077 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident Inspector U.S. Nuclear Regulatory Commission P.O. Box 298 Shippingport, PA 15077
Enclosure REQUEST FOR ADDITIONAL INFORMATION RELATED TO THE INSERVICE TESTING PROGRAM, THIRD 10-YEAR INTERVAL FIRSTENERGY NUCLEAR OPERATING COMPANY FIRSTENERGY NUCLEAR GENERATION CORP.
OHIO EDISON COMPANY THE TOLEDO EDISON COMPANY BEAVER VALLEY POWER STATION, UNIT NO. 2 DOCKET NO. 50-412 By letter dated May 11, 2007, Agencywide Documents Access and Management System (ADAMS) accession number ML071370347, FirstEnergy Nuclear Operating Company (FENOC, the licensee) requested approval of proposed alternatives and relief requests associated with the inservice testing (IST) program third 10-year interval update for the Beaver Valley Power Station, Unit No. 2 (BVPS-2). There was a total of 10 requests submitted. The Nuclear Regulatory Commission (NRC) staff is reviewing the submittal and has the following questions:
Relief Request PRR1 1.
The licensee stated, Lieu of double frequency test requirements specified in ISTB-6200(a) an evaluation and analysis shall be performed per the guidelines provided in ISTB-6200(c). ISTB-6200(c) specifically states, In cases where the pumps test parameters are within either the alert or required action ranges....., a new set of reference values may be established. Therefore, the use of ISTB-6200(c) is applicable to both alert and required action ranges. Please clarify the need for Relief Request PRR1.
Relief Request PRR6 2.
NUREG-1482, Guidelines for Inservice Testing at Nuclear Power Plants, Revision 1, Section 5.5.2, Use of Tank Level to Calculate Flow Rate for Positive Displacement Pumps is the basis for the proposed alternative in the relief request. However, the relief request does not indicate if the diesel fuel oil transfer pumps are positive displacement pumps. Are the diesel fuel oil transfer pumps positive displacement pumps? Please provide another basis for the proposed alternative in the relief request, if the pumps are not positive displacement pumps.
Relief Request PRR8 3.
In the last paragraph of the American Society of Mechanical Engineers (ASME) Code Components Affected Section, the licensee stated, This Request for Relief may also be applied to any pump in the Inservice Test (IST) Program scope should a vibration reading of <0.05 in/sec be obtained as a new reference value subsequent to repair or replacement and for pumps that demonstrate a vibration reading of <0.05 in/sec for new comprehensive tests. NUREG/CP-152, "Smooth-Running Pumps," Session 4, Pages 4-32, July 1996, states, If licensees intend to submit alternative requests to use minimum reference values, the requests should be pump specific and include justification as to how the current inservice testing methodology will detect pump degradation. The NRC staffs position is to review relief requests on a case-by-case basis for a specific requirement of the Code. Generic relief for all pumps cannot be authorized. Generic changes to Code requirements can be achieved through the ASME Code for Operation and Maintenance of Nuclear Power Plants Committee. Therefore, please revise the relief request to delete the last paragraph from the ASME Code Component(s) Affected Section. Also, future relief requests may be submitted to NRC, if historical data of the pump shows that the reference value of vibration is less than 0.05 in/sec.
4.
The relief request does not address pump operating speed. Pump operating speed is a critical component in the vibration acceptance criteria. Please provide the operating speed of each pump listed in the relief request.
Relief Request PRR9 5.
The licensee stated, Since suction pressure is typically a small value, it has minimal impact on pump differential pressure. Please provide the typical service water pump suction pressure, discharge pressure, and pressure instrument accuracy.
6.
Explain why replacing river level recorder and transmitter with level indication calibrated to 0.5% is considered a hardship or unusual difficulty. Are there any temporary flow instruments that have the accuracy required for the comprehensive test?
7.
Please provide a comparison of the Code required values and the proposed values, including the following information: (1) pressure instrument range, (2) referenced value range (established), and (3) effective and actual accuracies of instruments. Provide justification as to why the proposed alternative is acceptable.