ML18012A817
| ML18012A817 | |
| Person / Time | |
|---|---|
| Site: | Harris  |
| Issue date: | 06/26/1997 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML18012A816 | List: |
| References | |
| NUDOCS 9707010245 | |
| Download: ML18012A817 (6) | |
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t UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON> D.C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION CAROLINA POWER 5 LIGHT COMPANY SHEARON HARRIS NUCLEAR POWER PLANT UNIT I DOCKET NO. 50-400
1.0 INTRODUCTION
By letter dated March 14,
- 1997, as supplemented by letters dated May 16, and June 17, 1997, Carolina Power and Light Company (the licensee) requested NRC approval for a revision to the Shearon Harris Nuclear Power Plant (HNP) Final Safety Analysis Report (FSAR) that changes the design basis for fuel cask handling operations.
The proposed revision would add a discussion in the FSAR for the handling of an IF-300 fuel cask with less than the full designed cask integrity.
Spent fuel in an IF-300 shipping cask is routinely received at HNP from other nuclear plants in the licensee's system for storage in the HNP spent fuel pool.
When used within the limitations listed in its Certificate of Compliance (CoC,) the IF-300 shipping cask is designed to withstand being dropped from 30 feet onto an unyielding surface.
In=concert with Review Criteria in section 15.7.5 of the NRC's NUREG-0800, Standard Review Plan (SRP), the consequences of a cask drop accident was not analyzed for HNP since the potential drop of a spent fuel cask is limited to less than an equivalent 30-foot drop onto a flat, essentially unyielding, horizontal surface.
However, recently the licensee has identified that some cask lifts involved in moving the spent fuel into the pool are performed with only 4 of the 32 head closure bolts in place and/or the exterior valve protective boxes removed.
Although these movements do not represent a potential drop of more than 30 feet, the licensee realized that such drops with less than the full cask integrity are outside the analyzed cask design and constitute an unr eviewed safety question.
The licensee has analyzed the consequences of a cask drop accident with the cask configured as used at HNP.
This analysis indicates that, even without full cask integrity, dropping an IF-300 cask loaded with the most limiting fuel from one of the other plants in the system results in off-site doses that are well within the acceptance criteria in the SRP.
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- 2. 0 EVALUATION The staff's evaluation of the proposed change to the HNP licensing basis consisted of reviewing the assumptions and methods in the licensee's radiological consequence analysis to ensure they are conservative,
- bounding, and consistent with the other HNP design basis analysis.
In addition, the staff performed independent calculations with those assumptions to provide reasonable assurance that the licensee's calculational methodology was technically sound.
The licensee's consequence analysis assumed the bounding condition that the IF-300 cask was loaded with PWR fuel'undles with maximum burn-up (45,000 MWd/MTU).
In concert with item 10 of the IF-300 cask CoC (Certificate number 9001 Rev. 31),
a minimum decay time of 5 years was assumed.
The fuel pin gap activity and chemical composition assumptions Here consistent with the guidance in Regulatory Guide (RG) 1.25.
In addition, the maximum reactor power level (with a radial peaking factor of 1.65) consistent with the RG 1.25 guidance was assumed for each bundle.
The licensee's analysis used the bounding assumption that 100X of the fuel pin gap activity in the fully loaded cask was released to the environment with no filtration.
The worse ca'se, short-term, ground-level atmospheric dispersion values for the Exclusion Area Boundary and the Low Population Zone, listed in table 2.3.4-5 of the HNP FSAR were also applied.
Based on the above evaluation, the staff concludes that the licensee has demonstrated with reasonable assurance that the maximum radiological consequences of dropping an IF-300 cask at the HNP are radiation doses to members of the public that are a small fraction of the numerical criteria in 10 CFR Part 100 and are well within the acceptance criteria in the
- SRP, and, therefore, they are acceptable.
3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the State of North Carolina official was notified of the proposed issuance of the amendment.
The State official had no comments.
- 4. 0 ENVIRONMENTAL CONSIDERATION The amendment (which adds a discussion in the FSAR for the handling of an IF-300 fuel cask with less than the full designed cask integrity) changes a
requirement with respect to installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20.
The NRC staff has determined that the amendment involves 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 the amendment involves no significant hazards consider ation, and there has been no public comment on such finding (62 FR 17226).
Accordingly, the amendment meets 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 the amendment.
5.
~CN LN The Commission has 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, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
Principal Contributor:
Roger L. Pedersen Date:
. June 26, 1 997
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AMENOiMENT NO.
73 TO FACILITY OPERATING LICENSE NO.
NPF-63 HARRIS, UNIT 1
~Docket Ri.le-PUBLIC PDII-1 Reading S.
Varga OGC G. Hill (2)
H. Reinhart (13H15)
R.
Pedersen ACRS J.
Johnson RII cc:
Harris Service List
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