ML16138A609
| ML16138A609 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 10/19/1987 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML16138A610 | List: |
| References | |
| NUDOCS 8710270362 | |
| Download: ML16138A609 (3) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D. C. 20555 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 162 TO FACILITY OPERATING LICENSE NO. DPR-38 AMENDMENT NO. 162 TO FACILITY OPERATING LICENSE NO. DPR-47 AMENDMENT NO. 159 TO FACILITY OPERATING LICENSE NO. DPR-55 DUKE POWER COMPANY OCONEE NUCLEAR STATION, UNITS 1, 2, and 3 DOCKET NOS. 50-269, 50-270 AND 50-287 INTRODUCTION By letter dated July 29, 1985, Duke Power Company (the licensee) proposed changes to the Technical Specifications (TSs) of Facility Operating Licenses No. DPR-38, DPR-47 and DPR-55 for the Oconee Nuclear Station, Units 1, 2 and
- 3. These amendments would consist of changes to the Station's common TSs.
The licensee requested the Director, Office of Nuclear Reactor Regulation approve for Oconee the integrated surveillance program documented in Babcock and Wilcox (B&W) Topical Report, BAW-1543, Revision 2 and 2A "Integrated Reactor Vessel Material Surveillance Program," February 1984. The proposed revision would delete those TSs related to the Reactor Vessel Material Surveillance Program. By letter dated July 3, 1986, the licensee 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 Part 50.
DISCUSSION The proposed amendment would delete from the licenses an exemption from 10 CFR 50, Appendix H and delete Sections 4.2.4, 4.2.5, Table 4.2-1, and supporting bases from the Oconee Units 1, 2, and 3 Technical Specifications.
These sections of the Technical Specifications contain the reporting re quirements and schedule for withdrawal of the Oconee Units 1, 2, and 3 reactor vessel surveillance capsules. In lieu of the Technical Specifi cations requirements, the licensee indicates that their surveillance program will comply with the requirements in B&W Topical Report BAW-1543, Rev. 2 and 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.
ThTe requirements for an integrated surveillance program are documented in Section II.C of this revision of Appendix H. This section of Appendix H requires that each surviefiance program be approved on a case-by-case basis by the Director, Office of Nuclear Reactor Regulation.
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-2 Oconee Units 1, 2, and 3 are participating in the B&W Integrated Reactor Vessel Surveillance Program which is documented in B&W Topical Report BAW-1543, Rev. 2 and 2A. This topical report contains the surveillance capsule withdrawal sche dule for Oconee Units 1, 2, and 3. The staff's review of the Topical Report is documented in a March 13, 1986 letter from C. 0. Thomas to J. H. Taylor. The staff concluded that the B&W integrated surveillance program, documented in Topical Report BAW-1543, Rev. 2 meets the criteria in Section II.C. of 10 CFR 50, Appendix H and after approval of the integrated surveillance program by the Director, Office of Nuclear Reactor Regulation, exemptions to 10 CFR 50, Appendix H, will no longer be required.
Regulatory Guide 1.99, Rev. 2, "Radiation Damage to Reactor Vessel Materials,"
which has been reviewed by the staff and has been issued for public comment, indicates that radiation dama ge is a function of neutron fluence.and the amounts of residual elements (copper and nickel) in the material.
Hence, an acceptable surveillance program must include withdrawal of capsules at neutron fluence intervals representing the lives of Oconee Units 1, 2, and 3, respectively, and must contain material that can monitor the amount of radiation damage to the limiting material in each of the Oconee Units 1, 2, and 3 reactor vessel beltlines. The required amount of neutron fluence to be received by each capsule in the surveillance program is documented in ASTM E 185-82.
According to B&W Topical Report BAW-1543, Rev. 2 and 2A, there will be six surveillance capsules per Oconee unit. They will be irradiated in the Crystal River Unit 3 Nuclear Reactor, j9d theq will be wi draw at neutron fluences (E'1MeV) varying from 5.7 x 10 n/cm to 1.3x 10 n/cm.
The withdrawal schedule for the Oconee Units 1, 2, and 3 capsules in B&W Topical Report BAW-1543, Rev. 2 meets, to the extent practical, the requirements in ASTM E 185-82. The weld metal in the capsules is identified as WF112 for Unit 1 and WF 209-1 for Units 2 and 3. The limiting material in the Unit 1 reactor vessel beltline is identified as weld metal SA1430, Unit 2-WF25, and Unit 3-WF67. Weld metals in the capsules and reactor vessel's beltlines were prepared using the same type of flux and filler wire but different heats and 6
lots. Since these weld metals are from different heats and lots, the amounts of residual elements for each of the weld metals is reported in Babcock &
Wilcox Topical Report BAW-1799, "B&W 177-FA Reactor Vessel Beltline Weld Chemistry Study," dated July 1983. By comparing the amounts of radiation damage predicted by Regulatory Guide 1.99 to that observed for the capsule material, we will be able to effectively monitor radiation damage to the Oconee Units 1, 2, and 3 reactor vessel beltlines.
EVALUATION The capsule withdrawal schedule meets, to the extent practical, the require ments in ASTM E 185-82 and the respective Oconee Units 1, 2, and 3 capsule weld metals can be used to monitor radiation to the Oconee Units 1, 2, and 3 reactor vessel beltlines.
-3 Based on the staff's approval of B&W Topical Report 1543, Rev. 2 and 2A and previous conclusions, we determined it acceptable for Oconee Units 1, 2, and 3 to use the integrated surveillance program that was documented in B&W Topical Report BAW-1543, Rev. 2 and 2A for Oconee Units 1, 2, and 3. Also upon approval by the Director, Office of Nuclear Reactor Regulation, the exemption from Appendix H1 will be nullified.
Since the licensee has agreed to comply with B&W Topical Report BAW-1543, Revisions 2 and 2A, and with the requirements in 10 CFR 50, Appendix H, we find it acceptable to delete the current reporting requirements and schedule for withdrawal of the respective Oconee Units 1, 2, and 3 reactor vessel surveillance capsules from Technical Specification Sections 4.2.4, 4.2.5, Table 4.2-1 and supporting bases.
ENVIRONMENTAL CONSIDERATION These amendments involve a change in the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and changes in reporting requirements. We have determined that the amendments involve no significant increase in the amounts, and no significant change in the types, of any effluents that may be released offsite, and that there is no significant increase in individual or cumulative occupational radiation exposure.
The Commission has previously issued a proposed finding that these amendments involve no significant hazards consideration, and there has been no public comment on such finding. Accordingly, these amendments meet the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9).
Pursuant to 10 CFR 51. 22(b), no environmental impact statement or environmental assessment need be prepared in connection with the issuance of these amendments.
CONCLUSION The Commission made a proposed determination that the amendments involve no significant hazards consideration which was published in the Federal Register (52 FR 43024) on October 23, 1985, and consulted with the staT eoiSouth a
Carolina. No public comments were received, and the state of South Carolina did not have any comments.
We have concluded, 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 manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of these amendments will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributors: K. Wichman H. Pastis Dated:
October 19, 1987