ML20212E976
| ML20212E976 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 09/21/1999 |
| From: | S NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20212E974 | List: |
| References | |
| NUDOCS 9909270219 | |
| Download: ML20212E976 (2) | |
Text
- K'o g-t UNITED STATES g
j NUCLEAR REGULATORY COMMISSION o
WASHINGTON, D.C. 20565-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 255 TO FACILITY OPERATING LICENSE NO. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333
1.0 INTRODUCTION
By letter dated October 8,1999, the Power Authority of the State of New York (the licensee) submitted a request for changes to the James A. FitzPatrick Nuclear Power Plant Technical Specifications (TSs). The requested changes would revise the actions to be taken in the event multiple control rods are inoperable.
2.0 EVALUATION The specific proposed changes are to TS 3.3.A.2 and the corresponding Bases (3.3.A.2).
These TS and Bases address actions to be taken when multiple control rods are inoperable.
The FitzPatrick TS currently require that during power operation inoperable control rods be positioned such that (1) the TS required shutdown margin can be met, and (2), during operation, no more than one control rod in any 5x5 array may be inoperable. (At least 4 inoperable rods must separate any 2 inoperable ones.) If this condition is not met, the reactor shall be shut down.
The proposed TS changes retain the shut down margin requirement but remove the existing 5x5 array requirement and instead require that with two or more inoperable rods in the Startup Hot Standby or Run mcdes, and with power less than 10 percent of rated thermal power, the rod pattern shall be equivalent to the Banked Position Withdrawal Sequence (BPWS) or else the inoperable rods shall be separated by two or more operable rods. If this is not met, the i
reactor must be shut down within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. For operation above 10 percent power, the j
restriction on inoperable rods is not required, since in that higher power operation region, the l
control rod drop analysis (CRDA) has no significant effect. This is because of the more rapid negative reactivity feedback during the higher power operation when the reactor coolant is less dense. The standard generic analysis results of the CRDA do not exceed the current NRC specified 280 calories /gm limit established for this event. The standard generic analysis i
performed by General Electric has been approved by the NRC staff.
The proposed specification 3.3.A.2.e.2 requires the reactor be in hct shutdown within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> l
if nine or more control rods are inoperable. Acceptable operation is with up to 8 inoperable control rods which is consistent with the bases of the CRDA analysis and is sufficiently low that the plant will be shutdown if there is a potential systematic problem with the Control Rod Drive j
system. Thus placing the shutdown action on 9 or more inoperable control rods ensures the l
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. consequences of the CRDA are acceptable. Therefore, this proposed specification is acceptable.
The requested change is intended to make the TS consistent with the conditions and rod patterns which are assumed to exist for the control rod drop accident analysis. This analysis for 3
FitzPatrick (and most other BWRs) assumes that during startup and low power operation l
control rod patterns conform to the BPWS which was developed to produce low reactivity worth i
rods in startup conditions analysis for the rod drop event. Use of these pattens has become a standard approach for this analysis and has been approved by the NRC. This is discussed in References 1 and 2 of the licensee's October 8,1999, submittal, which are the General Electric Proprietary Reports "NEDO-21231, Blanked Position Withdrawal Sequence, January 1977,"
and "NEDE-24011 P-A-13, General Electric Standard Application for Reactor Fuel, August 1998." These reports have been reviewed and approved by the NRC. The staff has reviewed the licensee's proposed changes and, since they are consistent with prior approved analyses, the NRC staff has determined the proposed changes to the TSs are acceptable.
3.0 STATE CONSULTATION
in accordance with the Commission's regulations, the New York State official was notified of the j
proposed issuance of the amendment. The State official had no comments.
4.0 ENVIRONMENTAL CONSIDERATION
The amendment changes a requirement with respect to installation or use of a facility 1
component located within the restricted area as defined in 10 CFR Part 20. The NRC staff has l
determined that the amendment involves no s,gnificant increase in the amounts, and no j
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 consideration, and there has been no public comment on such finding (63 FR 6991). 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 environmentalimpact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
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5.0 CONCLUSION
l 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 1
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.
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Principal Contributor: H. Richings Date:
September 21, 1999 l
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