ML20059G526
| ML20059G526 | |
| Person / Time | |
|---|---|
| Site: | Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png |
| Issue date: | 10/27/1993 |
| From: | NRC |
| To: | |
| Shared Package | |
| ML20059G500 | List: |
| References | |
| NUDOCS 9311080179 | |
| Download: ML20059G526 (6) | |
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UNITED STATES QIli!
NUCLEAR REGULATORY COMMISSION l
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WASHINGTON. O C. 20555-0001 SAFETY EVALUATION BY THE OFFICE OF NUCLEAR REACTOR REGULATION i
RELATED TO AMENDMENT NO. 168 TO FACILITY OPERATING LICENSE NO. DPR-61 CONNECTICUT YANKEE AT0f.C POWER COMPANY HADDAM NECK PLANT DOCKET NO. 50-213
1.0 INTRODUCTION
l By letter dated August 18, 1993, the Connecticut Yankee Atomic Power Company (the licensee) submitted a request for changes to the Haddam Neck Plant Technical Specifications (TS). The amendment modifies the TS by permanently removing the ability for the Haddam Neck Plant to operate with three loops while in Modes 1 or 2.
2.0 EVALUATION In the licensee's June 27, 1991, proposed license amendment, three-loop operation was prohibited for Modes 1 or 2 for Cycle 17 due to the lack of a large and small break Loss-of-Coolant accident (LOCA) analysis for zircaloy-clad fuel.
It was the licensee's intention in 1991 to restore three-loop operation at the Haddam Neck Plant in the future.
However, recent economic evaluations have determined that the costs necessary to support three-loop operation are not justified. Therefore, the licensee has requested an amendment to permanently remove the ability for the Haddam Neck Plant to operate with three loops while in Modes 1 or 2.
As part of the proposed amendment, all references to three-loop operation for Modes 1 or 2 will be i
deleted. Because only four-loop operation will continue to be permitted for Modes 1 or 2, reference to four loops operation in TS are no longer necessary.
The following changes were made to the TS to delete any references to three-loop operation:
Technical Specification Section 2.1.1 relating to Safety Limits-Reactor Core will be revised to delete reference to Figure 2.1.2, " Reactor Core Safety Limit - Three Loops in Operation #."
In addition, Figure 2.1.-l will be revised to remove the phrase "Four Loops in Operation" since this clarifier is now moot.
Figure 2.1-2 will be deleted in its entirety.
Table 2.2-1 will be revised to delete all mention, and the variables associated with, three-loop operation. Discussion of the phrase "four loop" will also be deleted since this is understood. All of Section 2.0, Safety Limits and Limiting Safety System Settings, will be reissued in 9311000179 931027 PDR ADOCK 05000213 P
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. their entirety. The bases corresponding to Section 2.1 will be revised to capture the above changes.
Technical Specification Section 3/4.1.1, Boration Control, Shutdown Margin, will be revised to delete the mention of four-loop operation since this clarifier is no longer necessary.
Technical Specifications related to Reactivity Control Systems, Shutdown Margin - Three-Loops Operating, including Limiting Condition for Operation 3.1.1.4, and Surveillance Requirements 4.1.1.4.1 and 4.1.1.4.2 will be deleted in their entirety since three-loop operation is no longer permitted in MODES 1 or 2.
This deletion will result in pages 3/41-5 and 3/4 1-6 remaining, but containing only the words, "This page intentionally blank."
Technical Specifications related to Reactivity Control Systems, Novable Control Assemblies, Bank Height, Limiting Condition for Operation 3.1.3.1 will be revised to delete the references to three-loop operation.
In addition, references to four-loop operation will also be removed since this clarifier is no longer necessary.
Technical Specifications related to Reactivity Control Systems, Position Indication Systems, Operating will have the Limiting Condition for l
Operation 3.1.3.2 revised to delete reference to four-loop operation.
The ACTION statement which allowed three-loop operation in MODES 1 or 2 will be removed.
Technical Specification Section 3.1.3.6.1 related to Reactivity Control Systems, Control Group Insertion Limits, will have the title revised to delete mention of four-loop operation, since this clarification is no longer necessary. Also, the reference to four-loop operation will be dropped from the mode applicability section.
Technical Specifications related to Reactivity Control Systems, Control Group Insertion Limits, Three Loops Operating including Limiting Condition for Operation 3.1.3.6.2 and Surveillance Requirement 4.1.3.6.2 will be deleted in their entirety since three-loop operation is no longer permitted in MODES 1 or 2.
This deletion will result in page 3/41-26 remaining but containing only the words "This page intentionally blank."
Technical Specifications related to Power Distribution Limits, Section 3/4.2.1, Axial Offset, Four Loops Operating, will have the title revised to delete the reference to four-loops operating. This clarification is no longer necessary, since three-loop operation is no longer allowed.
Technical Specifications related to Power Distribution Limits, Three Loops Operating including Limiting Condition for Operation 3.2.1.2, Surveillance Requirements 4.2.1.2.1, 4.2.1.2.3 and 4.2.1.2.4 will be deleted in their entirety since three-loop operation is no longer permitted in MODES 1 or 2.
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, Technical Specifications related to Power Distribution Limits, Section 3/4.2.2, Linear Heat Generation Rate, Four Loops Operating, will have the title revised to delete the reference to four loops operating. This clarification is no longer necessary, since three-loop operation is no longer allowed in MODES 1 or 2.
Technical Specifications related to Power Distribution Limits, Three Loops Operating including Limiting Condition for Operation 3.2.2.2,,
Surveillance Requirements 4.2.2.2.1 and 4.2.2.2.2 will be deleted in their entirety since three-loop operation is no longer permitted in MODES 1 or 2.
Technical Specifications related to Power Distribution Limits, Section 3/4.2.3, Nuclear Enthalpy Rise Hot Channel Factor - Four-Loops Operating will have the title revised to delete reference to four loops operating since three-loop operation is no longer permitted in MODES 1 or 2.
Technical Specifications related to Power Distribution Limits - Three Loops Operating including Limiting Condition for Operation 3.2.3.2, Surveillance Requirements 4.2.3.2.1 and 4.2.3.2.2 will be deleted in their entirety since three-loop operation is no longer permitted in MODES 1 or 2.
The corresponding bases will also be revised to delete reference to the surveillance which will be removed.
Technical Specification Table 3.2-1, DNB Parameters, will be revised to delete variables associated with three-loop operation as well as the clarifier "Four-Loops in Operation." These changes will be made to reflect the fact that three-loop operation is no longer permitted in MODES 1 or 2.
The bases which corresponds to this table will also be revised to delete discussion of three-loop operation.
All of Section 3/4.2, Power Distribution Limits, will be repaginated and reissued in their entirety due to the number of pages that have been deleted.
Technical Specification Table 3.3-1, Reactor Trip System Instrumentation, will be revised to reflect that three loop operation is not permitted in MODES 1 or 2.
Therefore, reference to "in each [any] operating loop" is superfluous as well as table notation "**". The remaining asterisks will be revised to eliminate those not used.
Technical Specification 3.3-2 Table 3.3.-2, Engineered Safety Features Actuation System Instrumentation, will be revised to reflect that three-loop operation is not permitted in MODES 1 or 2.
The table notation in Table 3.3-2 will be revised to conform to the changes made in the license amendment request. ACTION Statement 22 will be revised to reflect the fact that for the condition discussed, the plant is already in HOT STANDBY.
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. Technical Specifications related to Reactor Coolant System, Isolated Loop including Limiting Condition for Operation 3.4.1.5, Surveillance Requirements 4.4.1.5.1 and 4.4.1.5.2 will be deleted in their entirety since three-loop operation is no longer permitted in MODES 1 or 2.
This deletion will result in page 3/4 4-9 remaining but containing only the words "This page intentionally blank." The corresponding bases, Section 3/4.4.1, Reactor Coolant Loops and Coolant Circulation, will also be revised to reflect these changes.
Technical Specifications related to Reactor Coolant System, Idled Loop including Limiting Condition for Operation 3.4.1.8, Surveillance Requirements 4.4.1.8.1 and 4.4.1.8.2 will be deleted in their entirety since operation with an idled loop in MODES 1 or 2 is not permissible.
This deletion will result in page 3/4 4-12 remaining but containing only the words "This page intentionally blank." The corresponding bases Section 3/4.4.1, Reactor Coolant Loops and Coolant Circulation, will also be revised to reflect these changes.
Technical Specifications related to Reactor Coolant System, Idled Loop Startup including Limiting Condition for Operation 3.4.1.10, Surveillance Requirements 4.4.1.10.1, 4.4.1.10.2, and 4.4.1.10.3 will be deleted in their entirety since operation with an idled loop in MODES 1 or 2 is not permissible. This deletion will result in page 3/4 4-14 remaining but containing only the words "This page intentionally blank." The corresponding bases Section 3/4.4.4.1, Reactor Coolant Loops and Coolant Circulation, will also be revised to reflect these changes.
Technical Specifications related to Reactor Coolant System, Steam Generators Limiting Condition for Operation 3.4.5, will be revised to reflect the fact that all loops must be operable in MODES 1 and 2.
Technical Specifications related to Plant Systems, Turbine Cycle, limiting Condition for Operation 3.7.1.1 will be revised to clarify that all loops must be operable in MODES I and 2.
This proposed modification is affected by the proposed change on safety valves previously submitted via CYAPC0 letter dated May 4, 1993.
Technical Specifications related to Plant Systems, Main Steam Line Trip Valves, Limiting Condition for Operation 3.7.1.1 will be revised to reflect that three-loop operation is not permitted in MODES 1 or 2.
Technical Specifications related to Plant Systems, Feedwater Isolation Valves, Limiting Condition for Operation 3.7.9 will be revised to reflect the fact that if a feedwater isolation valve is inoperable, opr. ration may continue in MODES 3 or 4.
This change has been prompted by the removal of the ability for the plant to operate while in MODES 1 or 2 with only three loops available.
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Technical Specifications related to Special Test Exceptions, Shutdown Margin Limiting Condition for Operation 3.10.1, and Surveillance Requirement 4.10.1.2 will be revised to delete reference to Technical Specification 3.1.1.4 which will be deleted via this proposed license l
amendment.
Technical Specifications related to Special Test Exceptions, Physics Tests, Limiting Condition for Operation 3.10.2 will be revised to delete i
reference to Technical Specification 3.1.3.6.2 which will be deleted in this proposed license amendment. The respective bases Section 3/4.10.2, Physics Tests, will have a typographical error corrected to properly reference Specification 3.1.1.6.
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Technical Specifications related to Special Test Exceptions, Position Indication System - Operating, Limiting Condition for Operation 3.10.4 will be revised to delete a reference to a technical specification which~
will be deleted via this proposed license amendment, the respective bases Section 3/4.10.4, Individual Rod Position Indication System - Operating, j
will also be revised to reflect this change.
Technical Specification 6.9.1.9.a relating to items which made up the Technical Report Supporting Cycle Operation will be revised to delete reference to those technical specifications which wil' be removed via this proposed license amendment. The remaining items will be renumbered for consistency.
l The corresponding Technical Specification Table of Contents pages will be revised to reflect the deletions and reissuance of the technical specifications.
l Three-loop operation was not allowed in Modes 1 and 2 during Cycle 17 because of the lack of large and small break LOCA analyses for the recently installed zircaloy-clad fuel.
Current plant procedures prohibit three-loop operation and all three-loop analyses have been deleted from the Haddam Neck Plant's Updated Final Safety Analysis Report. Therefore, three-loop operation is already prohibited via plant procedures and the footnotes in each of the applicable TS pages. This amendment is administrative in nature because it will permanently delete all references to three-loop operation which is already prohibited.
In addition, it will allow the removal of the footnotes to prohibit three-loop operation.
The only reason the references to three-loop operation were maintained was because the licensee had hoped in the future to restore this capability. As the licensee has determined this is not economically feasible, the removal of the references to.three-loop operation I
will provide a clearer and more readable TS.
Based on the above, the staff concludes that the TS amendment is administrative in nature and is acceptable.
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3.0 STATE CONSULTATION
In accordance with the Commission's regulations, the Connecticut State official was notified of the 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 component located within the restricted area as defined in 10 CFR Part 20 and changes surveillance requirements. The amendment also relates to changes in recordkeeping, reporting, or administrative procedures or l
requirements. 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 j
significant increase in individual or cumulative occupational radiation i
exposure. The Commission has previously issued a proposed finding that the j
amendment involves no significant hazards consideration, and there has been no public comment on such finding (58 FR 48381). Accordingly, the amendment l
meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(9) and (10).
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.
5.0 CONCLUSION
j 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:
A. Wang Date:
October 27, 1993 l
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