ML20058E882
| ML20058E882 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 07/27/1982 |
| From: | Vandenburgh D YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML20058E885 | List: |
| References | |
| FYR-82-78, NUDOCS 8207300244 | |
| Download: ML20058E882 (3) | |
Text
f1.g Proposzd Change #177 Telephone (617) 872-8100 TWX 7103807619 YANKEE ATOMIC ELECTRIC COMPANY 2.C.15.1 FYR 82-78 2"~ M 1671 Worcester Road. Framingham, Massachusetts 01701
,YAN K EE -
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July 27, 1982 United States Nuclear Regulatory Commission Washington, D. C.
20555 Attention: Office of Nuclear Reactor Regulation
References:
a) License No. DPR-3 (Docket No. 50-29) b) Yankee Atomic Electric Company Letter to USNRC, FYR 81-52, dated March 26, 1981.
Subject:
Technical Specifications Relating to Cycle Dependent Variables
Dear Sir:
Pursuant to Section 50.59 of the Commission's Rules and Regulations, Yankee Atomic Electric Company hereby proposes the following amendment to Appendix A of the Operating License for the Yankee Nuclear Power Station (YNPS):
Proposed Change Reference is made to the Technical Specifications of the YNPS Operating License No. DPR-3.
We propose to modify the Technical Specifications as shown in Attachment A.
Reason for Change Pursuant to Section 50.59 of the Commission's Rules and Regulations, Licensees are permitted to make changes to their facility, without prior Commission approval, as long as the changes do not involve:
1) an unreviewed safety question; 2) plant technical specification changes.
Routine changes are made to the core configuration at each refueling outage to compensate for burnup by adding a batch of f resh fuel assemblies and removing exposed assemblies. This process allows continued full power operation during subsequent operating cycles.
In order to support plant operation and define appropriate Limiting Conditions for Operation (LCO), a series of core performance analyses are performed. These analyses typically address the mechanical design, thermal-hydraulic design, physics and safety analysis aspects of the reloaded core. The most recent analysis supporting the current Core 15 operation was submitted in Reference b.
Due to the nature of the YNPS, particularly in the area of LOCA related LCC's, core specific characteristics have been used to develop core operating limits. Use of the core specific characteristics has been necessary to assure 8207300244 820727 (pgl W[le,.g$ h gph PDR ADOCK 05000029 P
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20555 Page 2 full power operation and provide sufficient margin for routine plant maneuvers. In the past this has necessitated the need for minor changes to plant Technical Specifications to reflect the core specific characteristics.
Based on Section 50.59 of the Commission's Rules and Regulations, these minor and routine changes to plant Technical Specification changes have required formal review and approval - through a written Safety Evaluation Report (SER)
- by the Commission. Also, because it is often difficult to predict plant startup dates following refueling outages, the review places an undue burden on resources both at the Commission and the licensee. Therefore, the changes proposed herein are designed to reduce the scope of review and the need for issuance of a formal SER for routine changes associated with a core refueling. By including the flexibility in plant Technical Specifications to make routine changes associated with core refuelings, pursuant to 10CFR50.59, staff resources, normally diverted for such reviews, can be directed to important safety issues.
In addition, it allows the licensee increased flexibility to plan refueling shutdowns.
Basis for Change The proposed changes described herein were discussed at a meeting in Bethesda on October 28, 1981, with members of your staff. At this meeting we made a presentation of the concept proposed herein. The concept was generally well received, and we were given an invitation to submit a proposal for an amendment change to accomplish our mutual objectives.
In summary, Yankee Atomic Electric Company is seeking a procedural change to the YNPS Technical Specifications dealing with routine changes in core operating limits due to cycle specific core characteristics. Yankee will continue to perform a core performance analysis for each core reload. The analysis will be performed in accordance with methods used in previous core reload submittals and accepted by the NRC.
The results of the analysis will be documented in a Core Performance Analysis Report, as has been the practice for the past 15 reloads, but now to support the core changes under 10CFR50.59. This document will be available to NRC staff upon request. The core specific parameters as identified in the proposed Technical Specifications would be transmitted by letter to the NRC for inf ormation prior to plant startup.
Attachment B contains an example of the type of submittal envisioned for future cycles. We have used, as an example, the core specific parameters for the currently approved operating cycle (15) to clarify the nature of the procedural technical specification change to facilitate the review.
Safety Considerations Based on the considerations contained herein, it is concluded that there is reasonable assurance that operation of the Yankee Nuclear Power Station
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United States Nuclear Regulatory Commission Washington, D. C.
20555 Page 3 consistent with the proposed Technical Specification will not endanger the health and safety of the public.
This proposed change has been reviewed by the Nuclear Safety Audit and Review Committee.
Fee Determination This proposed change is administrative in nature and has no safety or environmental significance. For these reasons, Yankee Atomic Electric Company proposes this change as a Class II Amendment. A payeent of $1,200.00 is enclosed.
Schedule of Change These changes to the Yankee Nuclear Poser Station Technical Specifications will be implemented upon Commission approval. We are currently operating Core 15 which is scheduled through September 1962.
Startup of Core 16 is currently planned for early December 1982. Since we would like to apply this approach for Core 16, a timely review consistent with the alove schedules is essential to preclude a reload submittal as in the past 90 days prior to startup; therefore, we request approval of this procedural change by September 1,1982.
We trust that you will find this submittal satisfactory; however, should you desire additional information, feel free to contact us.
Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY D. E. Vandenburgh Senior Vice President COMMONWEALTH OF MASSACHUSETTS)
)ss MIDDLESEX COUNTY
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Then personally appeared before me, D. E. Vandenburgh, who, being duly sworn, did state that he is Senior Vice President of Yankee Atomic Electric Company, that he is duly authorized to execute and file the foregoing request in the name and on the behalf of Yankee Atomic Electric Company and that the statements therein are true to the test o-s knowledge and b lief.r
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W gArmandR.Soucy Notary Pub %
My Commission Expires September 7, 1984
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