ML20247G937

Application for Amends to Licenses NPF-68 & NPF-81,revising TS 5.5.7, RCP Flywheel Insp Program, by Specifying Alternate Flywheel Insp Once Every Ten Years

ML20247G937
Person / Time
Site:	Vogtle
Issue date:	05/08/1998
From:	Woodard J SOUTHERN NUCLEAR OPERATING CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247G940	List: ML20247G937 ML20247G947
References
RTR-REGGD-01.014, RTR-REGGD-1.014 LCV-1180, NUDOCS 9805210015
Download: ML20247G937 (6)

Text

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J. D.Woodard Southern Nuclear Executive Mce President Operating Company. inc.

40 invemess Center Parkway Post Office Box 1295 Birmingham. Alabama 35201 Tel 205992.5086 SOUTHERNk h COMPANY Energy to Serve YourWorld*

May 8, 1998 LCV-1180 Docket Nos.: 50-424 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington D. C. 20555-0001 Ladies and Gentlemen:

VOGTLE ELECTRIC GENERATING PLANT PROPOSED CHANGE TO TECliNICAL SPECIFICATION 5.5.7 i REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM l

l In accordance with 10 CFR 50.90, Southem Nuclear Operating Company (Southern Nuclear) requests that Appendix A of Facility Operating Licenses NPF-68 and NPF-81 be amended to modify the Vogtle Electric Generating Plant (VEGP) Units I and 2 Technical Specifications (TS).

The purpose of the proposed license amendments is to revise TS 5.5.7, " Reactor Coolant Pump

, Flywheel Inspection Program,"in accordance with the Safety Evaluation Report (SER) recommendations included in a letter dated September 12,1996 from the Nuclear Regulatory Commission (NRC) to Duquesne Light Company - Beaver Valley Power Station, " Acceptance for Referencing of Topical Report WCAP-14535, ' Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination'."

The current technical specification specifies inspection of the reactor coolant pump (RCP) flywheels in accordance with Regulatory Position C.4.b of Regulatory Guide (RG) 1.14, Revision 1, August 1975. This regulatory position requires: (1) An in-place ultrasonic volumetric examination of the areas of higher stress concentration at the bore and keyway at approximately 3-year intervals and (2) A surface examination of all exposed surfaces and complete ultrasonic volumetric examination at approximately 10-year intervals. The proposed TS change specifies an alternate flywheel inspection once every 10 years which the SER states'to be acceptable relief from the requirements of RG 1.14, Regulatory Position C.4.b.

The next required RCP flywheel inspections are to be performed during the Unit I and Unit 2

- refueling outages scheduled for February and September of 1999, respectively. Therefore, Southern Nuclear requests approval of the proposed amendments by September 1,1998.

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9805210015 900508 l PDR ADDCK 05000424 , t\ 0 0\ i P PDR \^ l l

U. S. Nuclear Regulatory Commission Page 2 A description of the proposed technical specification change along with a supporting Safety Evaluation is provided in Enclosure 1. Southem Nuclear has determined that the proposed license amendments do not involve a significant hazards consideration pursuant to 10 CFR 50.92 (see Enclcsure 2). Enclosure 3 provides the revised technical specification pages, and the Environmental Impact Determination is included as Enclosure 4.

In accordance with 10 CFR 50.91(b)(1), a copy of these proposed license amendments is being forwarded to Mr. L. C. Barrett, the designee for the State of Georgia.

Mr. J. D. Woodard states he is executive vice president of Southem Nuclear and is authorized to execute this oath on behalf of Southern Nuclear, and to the best of his knowledge and belief, the facts set forth in this letter and enclosures are true.

Please contact this office if you have any questions.

Sincerely, N

D. oodard Sworn to and subscribed before me this FM dayof //7a4 / ,1998

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M0A0rn" Notary Public EmmW 3,2m My Commission Expires:

1 Enclosures  !

xc: Southern Nuclear Operatina Comnany Mr. J. B. Beasley Mr. M. Sheibani l SNC Document Management 1

i U. S. Nuclear Regulatory Commigii n l Mr. L. A. Reyes, Regional Administrator j l

Mr. D. H. Jaffe, Licensing Project Manager, NRR j Mr. J. Zeiler, Senior Resident inspector, Vogtle i l

State of Geornia I l Mr. L. C. Barrett, Commissioner, Department of Natural Resources l l

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a ENCLOSUREI VOOTLE ELECTRIC GENERATING PLANT PROPOSED CHANGE TO TECilNICAL SPECIFICATION 5.5.7 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM DESCRIPTION OF PROPOSED LICENSE AMENDMENT AND SAFETY EVALUATION Description of Proposed Change This license amendment request proposes to revise the Vogtle Electric Generating Plant (VEGP)

Umts I and 2 Technical Specification (TS) 5.5.7, Reactor Coolant Pump Flywheel Inspection  ;

Program, to provide an exception to the examination requirements of Regulatory Position C.4.b of '

Regulatory Guide (RG) 1.14, Revision 1, August 1975. The revised TS 5.5.7 would read as follows:

This program shallprovidefor the inspection ofeach reactor coolant pumpfl> wheel at least once every 10 years by conducting either:

a. An in-place ultrasonic examination over the volumefrom the inner bore oftheflywheel to the circle ofone-halfthe outer radius; or

b. A surface examination (magneticparticle and'or liquidpenetrant) ofexjx>sedsurfaces of the disassembledfl> wheel.

The provisions ofSR 3.0.2 andSR 3.0.3 are applicable to the Reactor Coolant Pump Flywheel inspection Program.

Safety Evaluation WCAP-14535, " Topical Report on Reactor Coolant Pump Flywheel Inspection Elimination,"

developed by the Westinghouse Owners Group (WOG) presents the basis for relief from the RCP flywhcci inspections required by RG 1.14 Regulatory Position C.4.b. This report was submitted to the NRC for review on January 24,1996 by Duquesne Light Company for application to Beaver Valley Power Station Units I and 2. On September 12,1996, the NRC issued a Safety Evaluation Report (SER) documenting its approval of WCAP-14535. The SER states that the evaluation

methodology described in WCAP-14535 is appropriate and the criteria are in accordance with the design criteria of RG 1.14. The naal NRC accepted version of WCAP-14535 was issued as revision A which compiles all of the relevant correspondence for this matter.

The SER requires that for those plants who plan to submit a plant-specific application of the topical report, the RCP flywheel material must be confirmed. The material used for all nine RCP motor flywheels at VEGP (including I spare pump motor)is A533 Grade B, Class 1 steel plate.

The proposed resision to TS 5.5.7 is consistent with the inspection program outlined in the SER which the NRC concludes to be acceptable relief from the requirements of RG 1.14, Regulatory Position C.4.b.

ENCLOSURE I (continued)

VOGTLE ELECTRIC GENERATING PLANT PROPOSED CHANGE TO TECHNICAL SPECIFICATION 5.5.7 REACTOR COOLANT PUMP FLYWIIEEL INSPECTION PROGRAM DESCRIPTION OF PROPOSED LICENSE AMENDMENT AND SAFETY EVALUATION As documented in WCAP-14535A, of the 729 examination results reported no indica *. ions which would affect the integrity of the flywheels were found. VEGP has performed 19 RCP flywheel inspections with no indications found.

In addition, the proposed license amendment will reduce personnel radiation exposure and minimize the possibility of damage to the RCP flywheel due to the disassembly and reassembly required to perform the currently required examination.

Summary The basis for the requested license amendments is formed by the technicaljustification presented in WCAP-14535A, VEGP's prior RCP flywheel inspection results, and the goal to minimize  ;

personnel radiation exposure to as low as reasonably achievable. Therefore, Southern Nuclear has j determined that the proposed change to TS 5.5.7 for VEGP Units I and 2 does not adversely affect or endanger the health and safety of the general public.

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ENCLOSURE 2 l VOGTLE ELECTRIC GENERATING PLANT

[ PROPOSED CHA~NGE TO TECHNICAL SPECIFICATION 5.5.7 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION l

Description of Proposed Channe This license amendment request proposes to revise the Vogtle Electric Generating Plant (VEGP)

Units 1 and 2 Technical Specification (TS) 5.5.7, Reactor Coolant Pump Flywhcci inspection Program, to provide an exception to the examination requirements of Regulatory Position C.4.b of Regulatory Guide (RG) 1.14, Revision 1, August 1975. The revised TS 5.5.7 would read as follows:

This program shallprovidefor the inspection ofeach reactor coolant pumpflywheel at least once every 10 years by conducting either:

a. An in-place ultrasonic examination over the volumefrom the inner bore oftheflywheel to the circle ofone-halfthe outer radius; or

b. A surface examination (magnetic particle and 'or liquidpenetrant) ofexposed surfaces of the disassembledflywheel.

The provisions ofSR 3.0.2 and SR 3.0.3 are apphcable to the Reactor Coolant Pump Rywheel Inspection Program.

Introduction The NRC has provided standards for determining whether a significant hazards consideration exists in 10 CFR 50.92. A proposed amendment to an operating license for a facility involves no significant hazards consideration if operation of the facility in accordance with the proposed amendment would not: (1) involve a significant increase in the probability or consequences of an l accident previously evaluated; or (2) create the possibility of a new or different kind of accident

from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety.

Each standard is discussed below for the proposed amendments.

IliK9A 29.i (1) Operation of the facility in accordance with the proposed amendment would not involve a significant increase in the probability or consequences of an accident previously evaluated.

The safety function of the RCP flywhcci is to provide suflicient rotational inenia to ensure reactor

coolant flow through the core during coastdown following a loss of offsite power and subsequent reactor trip. FSAR Chapter 15 analysis for a complete loss of forced reactor coolant flow demonstrates that the reactor trip together with the flow sustained by the inertia of the RCP j impeller will be sufficient to prevent the most limiting fuel assembly from exceeding the DNBR  !

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l ENCLOSURE 2 (continued) j VOGTLE ELECTRIC GENERATING PIANT I PROPOSED CHANGE TO TECHNICAL SPECIFICATION 5.5.7 REACTOR COOLANT PUMP FLYWHEEL INSPECTION PROGRAM NO SIGNIFICANT HA2,ARDS CONSIDERATION DETERMINATION n.

The maximum mechanical loading on the RCP motor flywheel results from overspeed following a LOCA. The analysis presented in WCAP-14535 A demonstrates that the mised inspection program proposed by this license amendment will ensure the integrity of the RCP flywheels will be maintained.

Based upon the findings of WCAP-14535A, the ability of the RCP flywheel to perform its intended safety function will be unaffected by the license amendment and the FSAR Chapter 15 analysis will remain valid. Therefore, these proposed changes do not involve a significant increase in the probability or consequences of an accident previously evaluated.

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1 (2) Operation of the facility in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previously evaluated.

The proposed license amendment will not change the physical plant configuration nor the modes of operation of any plant equipment. Based upon the results of WCAP-14535A, no new failure l' mechanism will be inaoduced by the revised RCP flywheel inspection program. Therefore, the proposed amendment will not create the possibility of a new or different kind of accident from any accident previously evaluated.

(3) Operation of the facility in accordance with the proposed amendment would not involve a significant reduction in a margin of safety.

The operating limits and ftmetional capabilities of the affected systems, structures, and components will be unchanged by the proposed amendment. The results of the RCP flywheel inspections l performed throughout the industry and at VEGP have identified no indications which would affect l its integrity. As presented in WCAP-14535A, detailed stress analysis and risk assessments have been completed with the results indicating that there would be no clumge in the probability of failure for RCP flywheels if all inspections were climinated. Therefore, these changes do not involve a significant reduction in a margin of safety.

Conclusion l Based on the above discussion, it has been determined that the requested technical specification l revision does not involve a significant hazards consideration.

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