ML20206J795

Submits Addl Info Re 861020 Relief Requests 3,4 & 5 Re Inservice Insp Program,Per 870302 Telcon.Relief Requests 4 & 5 Withdrawn

ML20206J795
Person / Time
Site:	Yankee Rowe
Issue date:	04/10/1987
From:	Papanic G YANKEE ATOMIC ELECTRIC CO.
To:	Mckenna E NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM), Office of Nuclear Reactor Regulation
References
FYR-87-038, FYR-87-38, NUDOCS 8704160183
Download: ML20206J795 (2)

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TLCphone (617) 872-8100 TWX 7103807619 YANKEE ATOMIC ELECTRIC COMPANY

.f.Ah 1671 Worcester Road, Framingham, Massachusetts 01701

'YANKEF

' *# April 10, 1987 FYR 87-038 United States Nuclear Regulatory Commission Document Control desk Washington, DC 20555 Attention: Ms. Eileen McKenna, Project Manager Project Directorate #1 Division of PWR Licensing - A

References:

(a) License No. DPR-3 (Docket No. 50-29)

(b) Yankee Letter to USNRC dated October 2, 1981 (c) Yankee Letter to USNRC, dated October 20, 1986

Subject:

Inservice Inspection Program Changes

Dear Ms. McKenna:

Pursuant to our telephone conversation on March 2, 1987, the following information is provided for Relief Requests No. 3, 4 and 5 of Reference (c).

Relief Request No. 3 During the NRC Staff review of relief request No. 3 and our subsequent telephone conversation some concern was expressed over Yankee's proposed alternative examination. Specifically that the proposed alternative did not include appropriate supervision and administration of ASME Section XI Safety Valve Testing. Yankee would like to clarify this issue; it is our intention that the person who supervises the safety valve set point testing shall be a plant engineer who has received formal training and education in Safety Valve Set Point testing. In addition to these qualifications the individual will have had experience in test supervision. It is our belief that these qualifications meet the intent of the Performance Test ,

Code 25 3 Section 3 0.2.

Relief Request No. 4 Based upon our recent discussion, Yankee requests that relief request No. (4) be withdraun at this time. As agreed upon during our teleconference this valve does not fall within the scope of ASME Section XI, IWV-1100; therefore, it is our opinion that no relief request is necessary. However, based upon the safety significance of this valve it is Yankee's intention to include CH-V-773 in the Inservice Testing Program and full cycle the valve open during refueling outages. Inservice testing of this valve will commence during the next refueling outage scheduled for May 2, 1987 8704160183 870410 PDR ADOCK 05000029 lgIO O PDR

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US Nuclear Regulatory Commission April 10, 1987 Page 2 FYR 87-038 Relief Request No. 5 Similiarly to item No. 4, Yankee requests that relief request No. 5 be withdrawn at this time. As agreed during our teleconference this valve does not fall within the scope of ASME Section XI, IWV-1100, and therefore it is our opinion that no relief request is necessary. However, based upon the safety significance of this valve, it is Yankee's intention to incorporate VD-V-ll57 into the Inservice Testing Program and full cycle the valve open during refueling outages. Inservice testing of this valve will commence during the next refueling outage scheduled for May 2, 1962.

We trust you will find this information satisfactory; however, should you have any quesitons please contact us.

Sincerely YANKEE ATOMIC ELECTRIC COMPANY w

George panic, J .

Senior Project Engineer Licensing