ML20034B202
| ML20034B202 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/19/1990 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20034B199 | List: |
| References | |
| NUDOCS 9004260160 | |
| Download: ML20034B202 (2) | |
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NUCLEAR REGULATORY COMMISSION t
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULAT FLORIDA POWER CORPORATION, ET AL.
CRYSTAL RIVER UNIT NO. 3JUCLEAR GENERATING PLANT 1
00CKET NO. 50-302 INTRODUCTION By letter dated March 22, 1990, _ Florida Power Corporation (the licensee) requested tnat the staff approve a revised capsule withdrawal and insertion l
l schedule for Crystal River 3 (CR-3), which is a host reactor for the Babcock & Wilcox Master Integrated Surveillance Program (BWMISP).
As a host reactor, the CR-3 reactor is used to irradiate surveillance materials for plants r
participating in the BWMISP.
The capsule withdrawal schedule for the BWMISP is documented in Babcock & Wilcox (BW) Topical Report BAW-1543.
Revision 3 to this topical report was submitted for staff review in a letter from J.H. Taylor to T.E. Murley, dated October 12, 1989.
Errsta Table E-1 to BAW-1543, Revision 3 was submitted for staff review in a letter from 0.L. Howell to B.J. Elliot dated January 10, 1990.
The errata table documents the changes to the insertion i
and withdrawal schedule for the BWMISP surveillance capsules in the CR-3 reactor.
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DISCUSSION Appendix H, 10 CFR Part 50, indicates that the surveillance capsule withdrawal schedule should comply with ASTM E 185-82 unless an alternative schedule is
.i approved by the staff.
ASTM E 185-82 recommends that surveillance capsules should be withdrawn from the reactor when the neutron fluence received by the capsule reaches a specified amount.
The revised program documented in Tables 3-19 and errata E-1 will withdraw the third capsule (OC2-B) for Oconee Unit 2 (OC-2) and the fourth capsule (OC3-0) for Oconee Unit 3 (OC-3).
The neutron fluence for capsule OC2-B corresponds approximately to the end of life (32 effective full power years) neutron fluence for the limiting OC-2 beltline weld at the 1/4 thickness of the reactor vessel. 'The neutron fluence for capsule OC3-D corresponds approximately to the end of life. neutron fluunce for the limiting beltline weld at the inside surface of OC-3.
These capsules will be withdrawn during the CR-3 seventh refueling outage.
The early removal of these capsules is necessary because the plants had implemented " Low Leakage" core configurations.
" Low Leakage" core configurations reduce the neutron fluence at the inside surface of the limiting beltline weld.
i Since the revised core configuration reduces the neutron fluence, the capsules must be withdrawn earlier to reduce their neutron fluence.
During the CR-3 seventh.
l refueling outage, capsules A2, A4 and OC3-E will be inserted into the CR-3 t
reactor vessel.
The A2 and A4 capsules contain weld metal with high copper 6
content, which will be used to supplement the neutron irradiation material l
data for plants participating in the BWMISP.
Capsule OC3-E will be used to i
monitor neutron irradiation embrittlement of the materials in the 0C-3 reactor l
vessel.
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CONCLUSIONS 1.
With withdrawal of capsules 0C2-B and OC3-0 during the CR-3 of neutron fluence to satisfy the recommendations of ASTM E 2.
is acceptable to withdraw capsules OC2-B and OC3-0 A2, A3 and OC3-E during the CR-3 seventh refueling outage.
Dated:
April 19, 1990 Principal Contributor B. Elliot O
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