ML20086S131
| ML20086S131 | |
| Person / Time | |
|---|---|
| Site: | Palisades  |
| Issue date: | 02/28/1984 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20086S130 | List: |
| References | |
| NUDOCS 8403010373 | |
| Download: ML20086S131 (3) | |
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION SUPPORTING AMENDMENT NO. 79 TO PROVISIONAL OPERATINp LICENSE NO. DPR-20 CONSUMERS ?0WER COMPANY DOCKET NO. 50-255
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1.0 INTRODUCTION
By letter dated August 3,1983, Consumers Power Company (the licensee) proposed changes to the Technical Specifications for the Palisades' Plant. These changes would (1) delete Capsule A-60 from the Reactor Vessel Surveillance Capsule Program, and (2) modif Surveillance Coupon Removal Schedule (Table 4.3.3)y the Reactor Vessel to provide the option of removing either a primary capsule or its equivalent counter-part located on the opposite side of the reactor core.
A Notice of Consideration of Issuance of /cendment and Proposed No Significant Hazards Consideration Determination and Opportunity for Hearing related to the requested action was published in the Federal Reoister on October 26, 1983 (48 FR 49583).
A, request for heiring and public consnents were not received.
2.0 DISCUSSION AND EVALUATION The Palisades reactor vessel surveillance p ogram must provide material test data that can be used to determine the effect of neutron radiation on Palisades reactor vessel beltline materials throughod the plants operating life of 32 cffective full power years (EFPY). The Palisades end-of-life (EOL)peakneutronfluenceattheinsidesurfqqeofghe reactor vesse.1 is predicted by the licensee to be 3.55x1019 n/cm (E>1MeV).
.The Palisades reactor vessel material surveillance program contains 2 cap-sules that are located cutside the core barrel, 6 capsules that are located at the midplane of the core and 2 capsules that are located in a low flux region above the core. The capsules are located in positions within the reactor vessel that are diametrically opposite each other. The licensce indicates that each pair of diametrically opposite capsules have similar, if not identical neutron fluences and temperatures.
The modified with-drawal schedule would permit the removal of either capsule. The two
- capsules that are located outside the core barrel are identified as
. Capsules A-60 and A-240.
Capsule A-240 has been withdrawn and its material tested. The test data is reported in Battelle Report 8403010373 840228 PDR ADOCK 05000255 P
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.. BCL-585-12. The saterials in CapIule A-240 were similar to the limiting materials in the Palisades reactor vessel beltline and were exposed to 1
2 a neutron fluence of. approximately 4.42x10 5 n/cm (E>1MeV), which is greater than the predicted peak E0L neutron fluence for the Palisades reactor vessel beltline. Hence, the material test results from Capsule A-240 may be utilized to predict the EOL naterial properties of the Palisade reactor vessel.
As of October 31, 1982, the licensee indicates that Capsule A-60 had 1
accumulated approximately 8.7x10 " n/cm? (E>1MeV) neutron fluence. Since the neutron fluence accumulated by the Capsule is significantly greater than the predicted E0L fluence for the Palisades reactor vessel and Capsule A-240 has provided material properties that can be utilized to predict the EOL material properties of the Palisades reactor vessel, Capsule A-60 will provide no useful fract:fre toughness data and may be deleted from the surveillance program.
The licensee indicates that the withdrawal schedule for the six capsules that are located at the midplane of the core will provide frgeture tough-n/cm to 3.3x10 n/cm2(E>1MeV).
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. ness data from neutron fluences of 3.7x1018 These capsules, along with Capsule A-240, will provide material test data that can be used to determine the effect of neutron radiation on the Palisades reactor vessel beltline materials throughout life of the vessel. Therefore, the staff. finds the proposed reactor vessel material surveillance withdrawal schedule acceptable.
Based on the above discussion, the staff concludes (1) the deletion cf Capsule A-60 from the Reactor Vessel Surveillance Program, and (2) the -
modification of the Reactor Vessel Surveillance Coupon Removal Schedule to provide the option of removing either a primary capsule or an equivalent capsule, are acceptable.
3.0 ENVIRONMENTAL CONSIDERATION
The staff has determined that the amendment does not authorize a change in effluent types or total amounts nor an increase in power level and will not result in any significant environmental impact. Having made this determination, the staff has furtter concluded that the amendment involves an action which is insignificant from the standpoin.t of environmental impact and, pursuant to 10 CFR 551.5(d)(4), that an environmental impact statement or negative declaration and environmental impact appraisal need not be prepared in connection with the issuance of this amendment.
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4.0 CONCLUSION
The staff has concluded, based on the considerations discussed above, that:
(1) there is reasonable assurance that the health and safety of the will not be endangered by operation in the proposed manner; and (2) public such
' activities will be conducted in compliance with the Comission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the health and safety of the public.
5.0 ACKNOWLEDGEMENT B. J. Elliot prepared this evaluation.
Dated: February 28, 1984 O
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