ML20134E971
| ML20134E971 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 10/30/1996 |
| From: | NRC (Affiliation Not Assigned) |
| To: | |
| Shared Package | |
| ML20134E970 | List: |
| References | |
| NUDOCS 9611040204 | |
| Download: ML20134E971 (4) | |
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UNITED STATES NUCLEAR REGULATORY COMMISSION l
If WASHINGTON, D.C. 20666-C001
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SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION RELATED TO AMENDMENT NO. 236 TO FACILITY OPERATING LICENSE N0. DPR-59 POWER AUTHORITY OF THE STATE OF NEW YORK JAMES A. FITZPATRICK NUCLEAR POWER PLANT t
DOCKET NO. 50-333 4
1.0 INTRODUCTION
By letter dated March 22, 1996, as supplemented October 11, 1996, 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 i
Specifications (TSs).
The requested changes would establish operability requirements for avoidance and protection from thermal hydraulic instabilities to be consistent with Boiling Water Reactor Owners Group (BWROG) long-term i
solution Option I-D.
The proposed changes include:
(1) provision of core power / flow operating map restrictions based on a plant and cycle specific thermal hydraulic stability exclusion region to prevent the occurrence of power oscillations, and (2) those associated with the removal of Simulated Thermal Power Monitor time delay from the Average Power Range Monitor (APRM) flow-biased scram to provide protection from postulated power oscillations.
Editorial changes are also made to support the revised specifications, improve readability of Bases sections, and enhance the presentation of requirements for single loop operation.
The October 11, 1996, submittal contained supplemental information and does not alter the proposed no significant hazards consideration determination.
l 2.0 EVALUATION The proposed changes include modifying the requirements for avoidance and protection from thermal hydraulic instabilities to be consistent with BWROG i
long term solution Option I-D, adding an exclusion region and its approved supporting methodologies to the Core Operating Limits Report (COLR), and modifying those associated with the removal of the Simulated Thermal Power i
Monitor time delay from the Average Power Range Monitor flow-biased scram.
NRC has evaluated and appraved the BWR0G Long-Term Stability Solutions Licensing Methodology which includes Option ID in topical reports NED0-31960 and NED0-31960, supplement 1.
The following TS, Surveillance Requirements (SR) and Bases are proposed changes.
(1) TS 3.5.J - Thermal Hydraulic Stability (a) The proposed TS 3.5.J.1 is to replace old TS 3.5.J.1, 3.5.J.2 and 3.5.J.3 and to read as follows:
9611040204 961030 PDR ADOCK 05000333 P
. When the reactor is in the run mode:
a.
Under normal operating conditions the reactor shall not be intentionally operated within the Power / Flow Exclusion Region defined in the COLR.
b.
If the reactor has entered the Power / Flow Exclusion Region, the operator shall immediately insert contrc1 rods and/or increase l
recirculation flow to establish operation outside the region.
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i The NRC staff has reviewed the proposed TS and has found them acceptable since NRC-approved methodologies are used to support cycle-specific parameters in the COLR and the operability requirements for avoidance and protection from thermal hydraulic instabilities are consistent with BWROG long-term solution Option I-D implementation criteria.
i (b) TS 3.5.J.4 through 3.5.J.6 are renumbered as TS 3.5.K under Single-Loop Operation.
It is administrative in nature with minor editorial l
changes; therefore, the proposed changes are acceptable.
l (2) SR 4.5.J.1 of Thermal Hydraulic Stability is deleted. The proposed change is acceptable since its function is taken over by the new limiting i
condition for operation 3.5.J.1.b.
4 (3) Bases 2.1.c - APRM Flux Scram Trip Setting (Run Mode)
The Bases is revised to reflect the application of the BWROG stability long-term solution Option I-D by adding the lower flow referenced scram setpoint of 54% power at 0% recirculation flow and 120% power at 100%
l recirculation flow to the APRM flow referenced scram trip setting and to l
rearrange the current contents, therefore, the proposed changes are acceptable.
(4) Figure 3.5-1 This figure is deleted since the figure of thermal power and core flow l
limits is no longer applicable and the power / flow exclusion region will be specified in the COLR.
(5) Bases 3.5.J - Thermal Hydraulic Stability The proposed changes are to revise the text to reflect the application of the BWROG stability solution Option I-D and the cycle-specific parameter in the COLR. Relocate the last paragraph of Bases Section 3.5.J to a i
revised Bases 3.5.K which is administrative in nature. Therefore, the l
proposed changes are acceptable.
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(6) Bases 3.5.L - References The proposed changes are to renumber Bases Section 3.5.K to be Bases 4
Section 3.5.L and add reference 3.5.L.2 which is a plant-specific application of the " Regional Exclusion with Flow-Biased APRM Neutron Flux Scram" Stability Solution (Option 1-D) to the James A. FitzPatrick l
Nuclear Power Plant to support the TS change request.
i (7) Table 3.1 Reactor Protection System (SCRAM) Instrumentation j
Requirements The Note 14 is deleted from trip function for APRM flow referenced neutron flux (not to exceed 117%) since it is no longer applicable to this trip function.
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The proposed changes are: (1) to include the Power / Flow Exclusion Region of Specification 3.5.J in TS 6.9(A)4.a; and (2) to add an approved topical report NED0-31960 and NED0-31960, Supplement 1, "BWR Owners' j
Group Long-Term Stability Solutions Licensing Methodology." These j
proposed changes are acceptable since they involve approved methodologies.
i On the basis of the staff review, the James A. FitzPatrick Nuclear Power Plant i
meets the BWROG Long-Term solution I-D implementation criteria which are that out-of-phase oscillations must be highly unlikely and the plant must have an unfiltered flow-biased scram (a commitment was made by licensee to remove the l
Simulated Thermal Power Monitor time delay from the APRM flow-biased scram).
1 Therefore, the staff concludes that the proposed changes including the i
application of Long Term Solution I-D to the FitzPatrick plant, relocation of the power / flow exclusion region to the COLR, some editorial corrections and addition of the approved topical report relating to the I-D methodologies are i
acceptable.
i The staff will perform an inspection on power distribution controls and design record files for the calculations reported in Table 4.1 of GENE-637-044-0295 3
since the calculated exclusion region is unusually small.
Full implementation of Long-Term Solution Option I-D in FitzPatrick will occur when: (1) the simulated thermal power time delay is removed from the flow-biased scram system, (2) the plant and cycle-specific exclusion region is included in the COLR, and (3) a power distribution control method (e.g., the SOLOMON system) j is available to operate inside the buffer region.
3.0 STATE CONSULTATION
i In accordance with the Commission's regulations, the New York State official was notified of the proposed issuance of the amendment.
The State official had no comments.
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4.0 ENVIRONMENTAL CONSIDERATION
The amendment 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 i
significant increase in the amounts, and no significant change in the types, l
of any effluents that may be released offsite, and that there is no j
significant increase in individual or cumulative occupational radiation 3
exposure. The Commission has previously issued a proposed finding that the amendment involves no significant hazards consideration, and there has been no l
public comment on such finding (61 FR 20854). 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 i
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the amendment.
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5.0 CONCLUSION
The staff has reviewed the request by Power Authority of the State of New York to revise the TS of the James A. FitzPatrick Nuclear Power Plant to implement t
BWROG long term solution Option I-D and to remove the power / flow exclusion j
region from the TS by replacing it with a reference to a COLR.
Based on the review, we conclude that these revisions are acceptable for the plant specific applications.
i 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 i
activities will be conducted in compliance with the Commission's regulations, i
and (3) the issuance of the amendment will not be inimical to the common j
defense and security or to the health and safety of the public.
Principal Contributor: Tia Huang Date: October 30, 1996 1
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