ML20206H434

Safety Evaluation Supporting Amend 98 to License DPR-51 & Approval to Use B&W Integrated Reactor Vessel Matl Surveillance Program

ML20206H434
Person / Time
Site:	Arkansas Nuclear
Issue date:	05/20/1986
From:	Office of Nuclear Reactor Regulation
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ML20206H415	List: ML20206H412 ML20206H431 ML20206H434
References
NUDOCS 8606260073
Download: ML20206H434 (3)

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• ,' a SAFETY EVALUATION BY THE OFFICE OF NUCLFAR REACTOR REGULATION SUPPORTING AMENDFENT N0.98 TO FACILITY OPEPATING LICENSE NO. DPR-51 AND SUPPORTING APPROVAL OF THE USE OF THE B&L' INTEGPATED REACTOR VESSEL MATERIAL SURVEILLANCE PROGPAM APVANSAS POWER AND LIGHT COMPANY l

ARKANSAS f:UCLEAR Of:F, UNIT NO.1 DOCKET NO. 50-313 INTRODUCTION By letter dated September 3,1985, Arkansas Power and Light Company (APf4L or the licensee) requested approval by the Director, Office of Nuclear Peactor Regulation, for the use of the Babcock and Wilcox (B&W) Integrated Material Surveillance Program documented in B&W Topical Report BAW-1543, Revision 2A,

" Integrated Peactor Vessel Material Surveillance Progran", for Arkansas Nuclear One, Unit No. 1 (ANO-1) and amendment to the Technical Specifications (TSs) appended to Facility Operating License No. DPR-51 for ANO-1. The proposed changes would change the TSs by removing the TSs related to the Reactor Vessel Material Surveillance Program. The licensee also requested withdrawal of the exemption from the requirement for a continuing in-vessel material surveillance program, as set forth in Appendix H to 10 CFR 50, which was granted by letter dated April 4, 1977, and extended by letter dated April 30, 1982.

DISCUSSION The proposed amendment would delete Sections 4.2.7, 4.2.8, Table 4.2-1, and supporting bases from the AN0-1 TSs. These sections of the AN0-1 TSs contain the reporting requirements and schedule for withdrawal of the ANO-1 reactor vessel surveillance capsules. In lieu of the TS requirements, the licensee indicates that the ANO-1 surveillance program will comply with the requirements in B&W Topical Report BAW-1543, Rev. 2A, and 10 CFR 50, Appendix H.

10 CFR 50, Appendix H, was revised in the Federal Register on May 27, 1983, and became effective on July 26, 1983. The requirements for an integrated surveillance program are documented in Section II.C of this revision of Appendix N. This section of Appendix H requires that each surveillance ,

program be approved on a case-by-case basis by the Director, Office of Nuclear Reactor Regulation.

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l ANO-1 is participating in the B&W Integrated Reactor Vessel Material Surveillance Progran, which is documented in B&W Topical Report BAW-1543, Rev. 2A. In a Farch 13, 1985 letter from C. O. Thomas to J. H. Taylor, the NRC staff accepted the Tcpical Report. We concluded that the B8W integrated surveillance program, documented in Topical Report BAW-1543, Rev. 2A, meets the criteria in Sect' ion II.C of 10 CFR 50, Appendix H, and after approval of the integrated program by the Director, Office of Nuclear Reactor Regulation, exemptions to 10 CFR 10, Appendix H, will no longer be required.

Draft Regulatory Guide 1.99, Rev. 2, " Radiation Damage to Reactor Vessel Materials," which has been reviewed by the NRC staff and is being prepared for public comment, indicates that radiation damage is a function of neutron fluence and the amounts of residual elements (copper, nickel and phosphorus) in the material. Hence, an acceptable surveillance program must withdraw capsules at neutron fluence intervals representing the life of ANO-1 and must contain material that is representative of the limiting material in the ANO-1 reactor vessel. The required amount of neutron fluence to he received by each capsule in the surveillance program is documented in ASTM E 185-82.

According to B&W Topical Report BAW-1543, Fev. 2A, there will be six ANO-1 surveillance capsules that will be irradiated in the Davis-Besse Nuclear Power Station, Unit No.1, and gey wjll be withdrgn at neutron fluences (E IVeV) varying from 7.27 X 10 n/cm to 1.4 X 10 n/cm2. The withdrawal schedule for the ANO-1 capsules in B&W Topical Report BAW-1543, Rev. 2A, meets, to the extent practical, the requirements in ASTf1 E 185-82. The weld metal in the capsules is identified as WF 193. The limiting weld metal in the ANO-1 reactor vessel beltline is identified us WF 112. Weld metals WR 193 and WF 112 were prepared using the same heatc of filler wire, same type of flux but different heats of flux. Since the amounts of residual elements in weld metal is governed by the weld wire and not the flux, the weld metal in the ANO-1 surveillance capsules is representative of the limiting weld metal in the ANO-1 reactor vessel beltline.

EVALUATION Since the capsule withdrawal schedule meets, to the extent ~ practical, the requirements in ASTM E 185-82, and the ANO-1 capsule weld metal is representative of the limiting weld metal in the AN0-1 reactor vessel beltline, the AND-1 surveillance capsules will effectively monitor the neutron irradiation to the ANO-1 reactor vessel materials.

Based on the NRC staff's approval of the B&W Topical Report 1543, Rev. 2A, and the above conclusion, we have determined it acceptable for ANO-1 to use the integrated reactor vessel material surveillance program as documented in B&W Topical Report BAW-1543, Rev 2A, and upon approval by the Director, Office of Nuclear Reactor Regulation, the exemption from Appendix H, which was granted by letter dated April 4,1977, and extended by letter dated April 30, 1982, will be nullified. , ,

Since the licensee has agreed to comply with B&W Topical Report BAW-1543, Rev.

2A, and the requirements in 10 CFR 50, Appendix H, it is acceptable to delete the reporting requirements and schedule for withdrawal of the ANO-1 reactor vessel surveillance capsules from ANO-1 TS Sections 4.2.7, 4.2.8, Table 4.2-1 and supporting bases.

EMVIRONFENTAL CONSIDEP.ATIONS This amendment involves a change in the surveillance requirements and a change in reporting requirements. We have determined that the amendment involves no significant increase in the amounts, and to significant change in the types, of any effluents tha't may be released offsite, and that there is no significant increase in individual or cuculative occupational radiation exposure. The Commission has previously issued a proposed finding that this amendment involves oc significant hazards corsideration and there has been nn public comment on such finding. Accordingly, this amendnent meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10). Pursuant to 10 CFR 51.22(b), no environrental impact statement nr environmental assessment need be prepared in connection with the issuance of this amendment.

CONCLUSIONS We have ccocluded, based on the considerations discussed above, that (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed nanner, and (2) such activities will be corducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the connon defense and security or to the health and safety of the public.

Date: May 20, 1986 Principal Contributors: Parry Elliot, Cuy Vissing i

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