ML20205T199
| ML20205T199 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 11/07/1988 |
| From: | Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20205T172 | List: |
| References | |
| NUDOCS 8811140167 | |
| Download: ML20205T199 (3) | |
Text
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UNITED STATES 3
NUCLE AR REGULATORY COMMISSION WASHING ton, D. C, 20666 I
I SAFETY EVALUATION BY THE OFFICF 0F NUCLEAR REACTOR rec 0LATION RELATED TO AMENDMENT NO. 116 TO FACILITY OPFPATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 l
INTRODUCTION Ry letter dated August 24, 1988, the Power Authority of the State of New York, licensee for the James A. Fitzpatrick Nuclear Power Plant, proposed revisions to the Technical Specifications (TS). The changes address the use of boron, L
enriched in the isotope B-10, in the sodium pentaborate solution used in the Standby Liouid Control System (SLCS) in order to meet the requirements of the Anticipated Transient Pithout Scram (ATWS) Rule, 10 CFR Part 50.62 paragraph (c)(4). The proposed changes revise TS Sections 3.4.C, 4.4.A, 4.4.C Figures 3.4-1 and 2, and Bases 3.4 and 4.4 EVALUATION The proposed TS changes are intended to meet the requirements of the ATWS Pule, 10 CFR Part 50.62(c)(4).
The ATWS Rule reautres that the SLCS be equivalent in control capacity to a system with an 86 gpm injection rate, using 13 weight percent unenriched sodium pentaborate solution, in a system L
with a 251 inch diameter reactor vessel. Of the several proposed approaches l
presented in the General Electric report (Ref.1), and approved in the NRC i
evaluation (Ref. 2), the licensee has chosen to use enriched (in B-10)
L boron. Using the calculation methods of Reference 1 allows a minimum concentration of 11.5 weight percent sodium pentaborate when using an enrichirent of 34.7 atom percent R-10, an injection rate of 50 gpm and a water mass of 491.700 pcunds (218 inch vessel). The new limits are reflected in the revised TS Sectivn 3.4.C and Figure 3.4-1, i
l The licensee s submittal stated that surveillance and positive verification j
will be performed periodically (once per month) to assure that the correct i
boron concentration is maintained. When additional chemicals, e.g., boron or boric acid are added to the storage tank, or if the solution temperature drops i
4 below specified limits, the boron concentration will also be verified (TS Section 4.4.C).
The enrichment of B-10 will be checked at least once per t
operating cycle.
Periodic verification of the 50 opm flow rate is also i
perforred ITS Section 4.4.A).
The temperature-concentration requirements of l
existing Figure 3.4-2 are unchanged; however, the Figure is revised to reflect i
88111 0167 781107 L
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ADOCK 05000333 5
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2-an editorial change in the title. The aforementioned surveillance requirements provide reasonable assurance that an adequate neutron poison level will be maintained, are consistent with previously reviewed specifications, and are, therefore accept 3ble. The bases to Technical Specification 3.4 and 4.4, which were revised to reflect the proposed changes, are also acceptable.
ENVIRONMENTAL CONSIDERATION This amendment involves a change to a requirement with respect to the installation or use of a facility component located within the restricted area as defined in 10 CFR Part 20 and chances to the surveillance requirements.
The 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 this amendment involves no significant hazards consideration and there has been no public comment on such finding. Accordingly, this amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR Part 51.?2(c)(9). Pursuant to 10 CFR Part 51.22(b), ao environmental impact statement or environmental assessment need be prepared in connection with the issuance of this arendment.
CONCLUSIONS The licensee has requested TS changes for James A. FitzPatrick Nuclear Power Plant which would provide for the use of enriched boron in the SLCS to meet the reouirements of 10 CFR Part 50.62(c)(4). The approach selected by the licensee and the associated TS are acceptable. The staff has concluded, based on the considerations discussed above, that: (1) there is rear.cnable assurance that the health and safety of the public will not be endange:*d by operation in the proposed manner, and (2) such activities will be conducted in compliance with the Commission's regulations and the issuance of this amendment will not be inimical to the common defense and security or to the j
health and safety of the public.
1 Dated: November 7, 1988 8
l PRINCIPAL CONTRIBUTOR:
l H. McCoy I
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I REFERENCES 1.
"Anticipated Transients Without Scram: Response to NRC ATWS Rule, 10 CFR 50.62 " NEDE-31096-P, December 1985.
2.
"Safety Evaluation of Topical Report (NEDE-31096-P) ' Anticipated Transients Without Scram: Response to ATWS Rule, 10 CFR Part 50.62.'"
l letter from G. 1.ainas (NRC) October 21, 1986.
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