ML20209A890

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SER Accepting Licensee Proposed Alternative to Use Code Case N-573 for Remainder of 10-year Interval Pursuant to 10CFR50.55a(a)(3)(i)
ML20209A890
Person / Time
Site: Pilgrim
Issue date: 06/28/1999
From:
NRC (Affiliation Not Assigned)
To:
Shared Package
ML20209A881 List:
References
NUDOCS 9907060178
Download: ML20209A890 (3)


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M j NUCLEAR REGUL TORY COMMISSION

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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION INVOLVING A REQUEST TO USE AN ALTERNATIVE TO ASME CODE. SECTION XI. IWA-4000 PlLGRIM NUCLEAR POWER STATION BOSTON EDISON COMPANY DOCKET NO. 50-293

1.0 INTRODUCTION

Inservice inspection and testing of the American Society of Mechanical Engineers (ASME)

Code Class 1,2, and 3 components shall be performed in accordance with Section XI of the ASME Boiler and Pressure Vessel Code and applicable Addenda as required by Tit!e 10 of the Code of Federal Reaulations (10 CFR) 50.55a(g), except where specific written relief has been granted by the Commission pursuant to 10 CFR 50.55a(g)(6)(i). Section 50.55a(a)(3) states that alternatives to the requirements of paragraph (g) may be used, when authorized by the Nuclear Regulatory Commission (NRC), if (i) the proposed alternatives would provide an acceptable level of quality and safety or (ii) compliance with the specified requirements would result in hardship or unusual difficulties without a compensating increase in the level of quality and safety.

Pursuant to 10 CFR 50.55a(g)(4), ASME Code Class 1,2, and 3 components (including supports) shall meet the requirements, except the design and access provisions and the preservice examination requirements, set forth in the ASME Code,Section XI," Rules for l

Inservice Inspection of Nuclear Power Plant Components," to the extent practical within the  !

limitations of design, geometry cnd materials of construction of the components. The I reguistions require that inservice examination of components and system pressure tests corsducted during the first 10-year inspection interval and subsequent intervals comply with the

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requirements in the latest edition and addenda of the date 12 months prior to the start of the 120-month interval, subject to the limitations and modifications listed therein. The applicable i Editbn of Section XI of the ASME Code for the Pilgrim Nuclear Power Station is the 1989 I Edition.

2.0 LICENSEE'S REQUEST l

In a letter dated March 17,1999, Boston Edison Company (BECo) submitted a relief request pursuant to 10 CFR 50.55a(a)(3)(i) to use ASME Code Case N-573, dated March 12,1997,

" Transfer of Procedure Qualification Records Between Owners,"Section XI, Division 1, as an alternative to ASME Code Section XI, Article IWA-4000. l l

9907060178 990628 ENCLOSURE PDR ADOCK 05000293 P PDR

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2 The 1989 Edition of the ASME Code,Section XI, IWA-4400(a) requires that "all welding shall be performed in accordance with welding procedure specifications that have been qualified by the owner or repair organization in accordance with the requirements of the codes specified in the Repair Program in accordance with IWA-4120."

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The licensee stated the following alternative testing requirements will be implemented as l defined by Code Case N-573:

1. BECo anticipates incorporation of Yankee Atomic Weld procedures into the BECo weld program complying with the provisions (a) to (h) of Code Case N-573. These weld procedures were used at NRC licensees, Vermont Yankee, Seabrook, Maine Yankee, and Yankee Rowe,in accordance with their Quality Assurance Programs. I
2. BECo will complete the documentation and obtain information as stated in paragraphs (c), (d), and (e) of Code Case N-573, if required. Also, BECo will demonstrate technical competence in the application of each procedure qualification record by completing a performance qualification test using the parameters of the resulting weld procedure specification.
3. The use of the Code Case will be documented on NIS-2 Form specifying any weld repair / replacement performed using the Code Case.

3.0 STAFF EVALUATION The licensee is obligated at this time to follow IWA-4400(a) which requires that all welding be performed in accordance with welding procedure specifications (WPS) that have been qualified l

l by the owner or repair organization in accordance with the requirements of the codes specified '

in the repair program, per IWA-4120. The licensee has proposed the use of Code Case N-573,

" Transfer of Procedure Qualification Records Between Owners," as an alternative to this requirement. The code case allows for the use of a welding or brazing procedure qualification record (PQR) qualified by one owner to be used by another owner for the development of the WPS. The specific requirements listed in Code Case N-573 shall be met by the owner that performed the procedure qualification, and by the owner intending to use the POR. These requirements are:

(a) The owner that performed the procedure qualification test shall certify, by signing the j POR, that testing was performed in accordance with Section IX.

(b) The owner that performed the procedure qualification test shall certify, in writing, that ,

I the procedure qualification was conducted in accordance with a Quality Assurance Program that satisfies the requirements of IWA-1400.

(c) The owner accepting the completed POR shall accept responsibility for obtaining any l supporting information needed for WPS development.

(d) The owner accepting the completed POR shall document, on each resulting WPS, the parameters applicable to welding. Each WPS shall be supported by all necessary POR's.

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(e) The owner accepting the completed PQR shall accept responsibility for the PQR.

Acceptance shall be documented by the owner's approval of each WPS that references the POR.

(f) The owner accepting the completed POR shall demonstrate technical competence in application of the received PQR by completing a performance qualification test using l the parameters of a resulting WPS. i (g) The owner may accept and use a POR only when it is receive directly from the Owner ,

that certified the PQR.

1 (h) Use of this Code Case shall be shown on the NIS-2 Form documenting welding or brazing.

The staff considers the qualification of a procedure for the purpose of joining materials by either j l welding or brazing may be performed by any owner provided the applicable requirements for l l procedure qualification are maintained, in addition, the staff finds it acceptable that owners may l use procedures qualified by other owners provided the conditions / requirements listed in Code l Case N-573 are met. Therefore, the staff concludes that the licensee's proposed alternative '

provides an acceptable level of quality and safety by providing reasonable assurance of i j structural integrity. The use of this alternative is, therefore, authorized pursuant to 10 CFR l 50.55a(a)(3)(i) for the current interval at Pilgrim Nuclear Power Station.

4.0 CONCLUSION

1 The staff concludes that the licensee's proposed alternative provides an acceptable level of l

quality and safety. Therefore, the licensee's proposed alternative to use Code Case N-573 is authorized for the remainder of the 10-year interval pursuant to 10 CFR 50.55a(a)(3)(i).

Principa; Contributor: A. Keim i Date: June 28, 1999

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