ML20080H583

Submits Relief Request 94-012 Re Snubber Insp Intervals for NRC Review & Approval,Per GL 90-09

ML20080H583
Person / Time
Site:	Mcguire, McGuire
Issue date:	02/13/1995
From:	Freeman D DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20080H586	List: ML20080H583 ML20080H595
References
GL-90-09, GL-90-9, NUDOCS 9502220381
Download: ML20080H583 (6)

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..DukeIbuerCornpany T C McMaxa McGuire Nuclear Generation Deparanent . Vice President 12700Hagers fenyRoad(MG0lVP) (7M)8754800 \

Hurdenvulle, NC28078M5 (TN)8754809 Fax \

. i February 13, 1995 1

I Document Control Desk l U.S.' Nuclear Regulatory Commission f Washington, D.C. 20555  !

Subject:

McGuire Nuclear Station Docket Nos: 50-369 and 370  !

Relief Request 94-012: Snubber Inspection Intervals for  ;

Unit 2 -

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Dear Sir:

Pursuant to 10 CFR 50. 55a (g) (5) (iii) , I am submitting the i attached relief request for NRC review and approval. Per NRC Generic Letter 90-09 dated December 11, 1990 on ' Alternative Requirements fcr Snubber Visual Inspection Intervals and  :

Corrective Actions

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...the staff has developed an alternate schedule for visual i inspections that maintains the same confidence level as the existing schedule and generally will' allow the licensee to  :

perform visual inspections and corrective actions during l plant outages. Because this line item TS improvement will '

reduce future occupational radiation exposure and is. highly ,

cost effective, the alternate inspection schedule is l consistent with the Commission's policy statement on TS improvements. '

The attached relief request seeks relief from impractical snubber  :

inspection frequencies and till invoke the snubber testing l frequency as reflected in the current McGuire Nuclear Station  !

Technical Specifications 3.7.8, Table 4.7-2 which are the same as those reflected in the referenced GL 90-09.

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Should there be any questions regarding' this matter, please 1 contact James E. Snyder at (704) 875-4447.

Very truly yours,

/P/A T. C. McMeekin 1 l

1 9502220381 950213 PDR ADDCK 05000369 I l P PDR '  !

j wome I

U . S, . Nuclear Regulatory Commission February 13, 1995 Page 2/3 xc: Mr. S. D. Ebneter Administrator, Region II U.S. Nuclear Regulatory Commission l 101 Marietta St., NW, Suite 2900 Atlanta, Ga. 30323 i

Mr. Victor Nerses j U.S. Nuclear Regulatory Commission  !

Office of Nuclear Reactor Regulation  !

Mail Stop 14H25 ,

Washington, D.C. 20555  ;

Mr. Robert E. Martin j U.S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation Washington, D.C. 20555 Mr. George F. Maxwell NRC Resident Inspector  ;

McGuire Nuclear Station >

Dayne Brown, Chief i Sivision of Radiation Protection 1 O. Box 27687 >

Ra2*tgh, N. C. 27611-7687 i

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I February 13, 1995 U.S,. Nuclear Regulatory Commission Page 3/3 bxc:

Jesse O. Barbour (EC07J)

Jerry Goodman (EC07J)

G. A. Copp (EC050)

Z. L. Taylor (CN01RC) '

E. Burchfield (ON01RC)

W. R. Cross Kay L. Crane  ;

Dwin E. Caldwell s P. T. Vu John M. Washam i

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DUKE POWER COMPANY MCGUIRE NUCLEAR STATION l l

Request for Relief From  :

ASME Code Section XI Requirements I. Component for Which Relief is Requested A. Name and Identification Number j All Unit 2 safety-related snubbers.  ;

B. Function Snubbers are designed to prevent pipe motion under dynamic loads.

C. ASME Section XI Code Class Provides support for Class 1,2,3 systems.

D. Valve Category i

Not applicable.

II. ASME Code Section Requirement that has been determined to be ,

impractical.

ASME Boiler and Pressure Vessel Code Section XI, Article IWF-5000. +

III. Basis for Requesting Relief The 1989 ASME Boiler and Pressure Vessel Code Section XI, Article IWF-5300 (a) states: " Inservice examinations shall be performed in accordance with the first Addenda to ASME/ ANSI OM-1987, Part 4 (published 1988), using the VT-3 visual examination method described in IWA-2213." Paragraph 2.3.2.2 of the first Addenda to ASME/ ANSI OM-1987, Part 4 states that examinations shall be conducted at 18 month intervals +25%.

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If" unacceptable snubbers are revealed, the interval for. )

subsequent inspections shall be reduced in accordance with l the following table:

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i Number of Unacceptable Months to Subsequent i Snubbers Examination {

0 18 f 1 12 l 2 6  !

3,4 4 [

5,7 2 i

>8 1  !

s McGuire Unit 2 Technical Specifications 3/4.7.8, SNUBBERS has a surveillance frequency not to exceed 48. months which is altered i based on the number of unacceptable snubbers found during the previous inspection in proportion to the sizes of the various i snubber populations or categories. See the attached copy of the subject TS Table 4.7-2, SNUBBER VISUAL INSPECTION INTERVAL.

The examination interval requirements in the McGuire Unit 2 TS Table 4.7-2 are based on NRC Generic Letter 90-09, ' Alternative  !

Requirements for Snubber Visual Inspection Intervals and l Corrective Actions.' Prior'to the incorporation of GL 90-09 into '

the TS, the examination inspection interval in the TS was identical to that in the first Addenda to ASME/ ANSI OM-1987, Part t

4. NRC GL 90-09 acknowledged that licensees having a large l number of snubbers find that the 18 month visual inspection i schedule in the first addenda to ASME/ ANSI OM-1987, part 4 is  !

excessively restrictive and that some licensees have spent a i significant amount of resources and have subjected plant  !

personnel to unnecessary radiological exposure to comply with the  !

visual examination requirements without increasing the confidence level in snubber operability. i McGuire Unit 2 has 335 snubbers subject to the inservice  !

inspection per IWA-5000. McGuire Unit 2 is currently on a fuel cycle length of approximately 18 months. In order to comply with  !

the current ASME requirements of IWF-5000, Duke Power would be l required to perform VT-3, visual examinations on all 359 snubbers- .

within the inservice inspection program at every refueling j outage. This examination frequency is twice that presently  ;

required by the approved TS 3/4.7.8 and significantly greater l than that required under Section XI codes through the 1986 t edition. As indicated in NRC GL 90-09, this increased inspection per ASME requirements does not increase the confidence level in  :

snubber operability above that obtained by the requirements of l NRC GL 90-09.

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. 1 IVs Alternate Testing l As an alternative to the requirements of ASME Section XI, IWF-5000, paragraph IWA-5053 (e) which invokes the inspection l frequency in paragraph 2.3.2.2 of the first Addenda to ASME/ ANSI i OM-1987, Part 4 (published in 1988), VT-3, visual inspection of snubbers within the Section XI inservice inspection boundaries shall be examined on a schedule as provided by McGuire Nuclear l Station TS 3/4.7.8, Table 4.7-2. For the purposes of determining inspection frequency, the snubbers within the inservice boundaries shall be considered part of the total population of snubbers inspected under TS 3/4.7.8. t 1

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