ML20141K884

Provides Comments on AP600 TS (08/96 Amend 0) Included W/Rev 9 to AP600 SSAR Related to Administrative Controls

ML20141K884
Person / Time
Site:	05200003
Issue date:	05/21/1997
From:	Quay T NRC (Affiliation Not Assigned)
To:	Liparulo N WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
NUDOCS 9705300250
Download: ML20141K884 (4)

Text

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e N y 21, 1997 Mr. Nicholas J. Liparulo, Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P. O. Box 355 h')

Pittsburgh, Pennsylvania 15230

SUBJECT:

COMMENTS ON THE AP600 TECHNICAL SPECIFICATIONS RELATED TO ADMINISTRATIVE CONTROLS

Dear Mr. Liparulo:

The NRC staff is reviewing the Westinghouse AP600 Technical Specifications (TS) (08/96-Amendment 0) which were included with Revision 9 to the AP600 SSAR. After the staff's initial comments to Westinghouse dated December 24, 1996, there were several sets of responses from Westinghouse.

Now the Civil Engineering and Geosciences Branch has completed its review of the AP600 TS.

Their comments.are as follows:

" Westinghouse Owner's Group Standard Technical Specifications (STS)", NUREG-1431 contains a program in Section 5.5.5 entitled " Component Cyclic or Transient Limit." This same program is included in the STS for B&W, BWR, and CE owner's Groups and in the ABWR and CE 80+ Technical Specifications.

!iowever, this program is not included in the AP600 TS.

In a letter dated October 11, 1996, Westinghouse stated that it is not included because the number of cycles for the transients that are listed in the SSAR exceed the actual number of cycles that will occur during the life of the plant.

The staff does not disagree with this statement, however, it does not justify the exclusion of the programmatic requirement in the STS.

In addition, the letter also stated that periodic inservice inspection (ISI) of the RCS pressure boundary is considered to provide adequate assurance of pressure boundary integrity.

The staff does not consider ISI to be a substitute for assuring that a component's fatigue design limits have not been exceeded. Although licensees probably maintain records of most plant transients, the staff's position is that the TS requirement to track the cyclic and transient occurrences to ensure that applicable components be maintained within their design limits should not be deleted.

Therefore, the requirement in Section 5.5.5 in NUREG-1431 should be include in the AP600 TS.

If you have any questions, please contact TSB lead reviewer, Angela T. Chu at (301) 415-2937.

Sincerely, Original Signed By Theodore R. Quay, Director Standardization Project Directorate a#

Division of Reactor Program Management b'N r' L/

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• May 21, 1997 Mr. Nicholas.J. Liparulo," Manager Nuclear Safety and Regulatory Activities Nuclear and Advanced Technology Division Westinghouse Electric Corporation P. O. Box 355 Pittsburgh, Pennsylvania 15230

SUBJECT:

COMENTS ON THE AP600 TECHNICAL SPECIFICATIONS RELATED TO ADMINISTRATIVE CONTROLS

Dear Mr. Liparulo:

The NRC' staff is reviewing the Westinghouse AP600 Technical Specifications (TS) (08/96-Amendment 0) which were included with Revision 9 to the AP600 SSAR. After the staff's initial connents to Westinghouse dated December 24, 1996, there were several sets of responses from Westinghouse.

Now the Civil Engineering and Geosciences Branch has completed its review of the AP600 TS. Their comments are as follows:

" Westinghouse Owner's Group Standard Technical Specifications (STS)", NUREG-1431.contains a program in Section 5.5.5 entitled " Component Cyclic or Transient Limit." This same program is included in the STS for B&W, BWR, and CE owner's Groups and in the ABWR and CE 80+ Technical Specifications.

However, this program is not included in the AP600 TS.

In a letter dated October 11, 1996, Westinghouse stated that it is not included because the number of cycles for the transients that are listed in the SSAR exceed the actual number of cycles that will occur during the life of the plant. The staff does not disagree with this statement, however, it does not justify the exclusion of the programmatic requirement in the STS.

In addition, the letter also stated that periodic inservice inspection (ISI) of the RCS pressure boundary is considered to provide adequate assurance of pressure boundary integrity.. The staff does not consider ISI to be a substitute for assuring that a component's fatigue design limits have not been exceeded. Although licensees probably maintain records of most plant transients, the staff's position is that the TS requirement to track the cyclic and transient occurrences to ensure that applicable components be maintained within their design limits should not be deleted. Therefore, the requirement in Section 5.5.5 in NUREG-1431 should be include in the AP600 TS.

1 If you have any questions, please contact TSB lead reviewer, Angela T. Chu at (301) 415-2937.

Sincerely,

$d~4 h Theodore R. Quay, Director i

Standardization Project Directorate Division of Reactor Program Management

}

Office of Nuclear Reactor Regulation i

Docket No.52-003 cc: See next page

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Mr. Nicholas J. Liparulo Docket No.52-003 Westinghouse Electric Corporation AP600 l

cc: Mr. B. A. McIntyre Mr. Ronald Simard, Director l

Advanced Plant Safety &

Advanced Reactor Program l

Licensing Nuclear Energy Institute Westinghouse Electric 1776 Eye Street, N.W.

Corporation Suite 300 Energy Systems Business Unit Washington, D.C. 20006-3706 P.O. Box 355

.Pittsburgh, PA 15230 Ms. Lynn Connor i

Doc-Search Associates Mr. John C. Butler P.O. Box 34 Advanced Plant Safety &

Cabin John, MD 20818 i

Licensing Westinghouse Electric Mr. James E. Quinn, Corporation Projects Manager Energy Systems Business Unit LMR and SBWR Programs P.O. Box 355 GE Nuclear Energy Pittsburgh, PA 15230 175 Curtner Avenue, M/C 165 San Jose, CA 95125 Mr. M. D. Beaumont Nuclear and Advanced Technology Mr. John E. Leatherman, Manager i

Division SBWR Design Certification Westinghouse Electric GE Nuclear Energy, M/C 781 Corporation San Jose, CA 95125 One Montrose Metro 11921 Rockville Fike Barton Z. Cowan, Esq.

Suite 350 Eckert Seamans Cherin & Mellott l

Rockville, MD 20852 600 Grant Street 42nd Floor l

Pittsburgh, PA 15219 Mr. Sterling Franks U.S. Department of Energy Mr. Ed Rodwell, Manager NE-50 PWR Design Certification 19901 Germantown Road Electric Power Research Germantown, MD 20874 Institute 3412 Hillview Avenue Mr. S. M. Modro Palo Alto, CA 94303 Nuclear Systems Analysis Technologies Mr. Charles Thompson, l

Lockheed Idaho Technologies Nuclear Engineer l

Company AP600 Certification P. O. Box 1625 NE-50 Idaho Falls, ID 83415 19901 Germantown Road Germantown, MD 20874 l

Mr. Frank A. Ross l

U.S. Department of Energy, l

NE-42 Office of LWR Safety and l

Technology 19901 Germantown Road Germantown, MD 20874 i

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DISTRIBUTION:

Letter to Mr. Nicholas J. Lioarulo. Date:

May 21. 1997 l

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TSB R/F SCollins/FMiraglia, 0-12G18 TMartin, 0-12G18 RZimmerman, 0-12G18 MSlosson l

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CIGrimes GBagchi JBrammer 4

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TKenyon JSebrosky WDean, 0-17G21 ACRS (11)

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