CY-97-006, Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant

Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant

ML20140D530
Person / Time
Site:	Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date:	05/30/1997
From:	Feigenbaum T CONNECTICUT YANKEE ATOMIC POWER CO.
To:
Shared Package
ML20140D536	List: CY-97-006, Application for Amend to License DPR-61,reflecting Limitations & Requirements Appropriate to Present Configuration of Plant ML20140D547 ML20140D557 ML20140D573 ML20140D576
References
CY-97-006, CY-97-6, NUDOCS 9706100412
Download: ML20140D530 (6)

Text

CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD e EAST HAMPTON, CT 06424-3099 May 30,1997 Docket No. 50-213 CY-97-006 Re: 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Haddam Neck Plant Proposed Revision To Operating License And Technical Specifications Defueled Operatina License And Technical Specifications introduction Pursuant to 10CFR50.90, Connecticut Yankee Atomic Power Company (CYAPCO) hereby proposes to amend its Operating License, DPR-61, by incorporating the attached proposed changes into the Haddam Neck Plant (HNP) Operating License and Technical Specifications.

Backaround in a letter dated December 5,1996,W CYAPCO informed the NPC that the Board of Directors of CYAPCO had decided to permanently cease operadons at the Haddam Neck Plant (HNP) and that the fuel had been permanently removed from the reactor.

Table 1 provides the HNP spent fuel assembly inventory.

The changes proposed herein reflect the limitations ud requirements appropriate to the present configuration of the plant. The primary reason for this change is to simplify and to improve clarity by eliminating the large volume of non-applicable material in the current Operating License and Technical Specifications. The objective is a clear and concise document for maintaining the plant in a permanently defueled condition. \

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9706100412 970530 lll lllfflllllflllllll PDR ADOCK 05000213 , ...

P pm e (1) T. C. Feigenbaum letter to the U. S. Nuclear Regulatory Commission,

" Certifications Of Permanent Cessation Of Power Operation And That Fuel Has Been Permanently Removed From The Reactor," dated December 5,1996.

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l U. S. Nucl=r R:gul: tory Commission l CY-97-006/Page 2 i

This submittal deletes, from Section 5, the description of the new fuel vault. Presently, new fuel is stored on-site. However, this new fuel is scheduled to be removed by early July 1997. If any of the new fuel is still on-site when this amendment is approved, l CYAPCO will implement appropriate administrative controls. CYAPCO will inform the NRC Project Manager and the NRC Senior Resident inspector when the last of the new fuel is shipped off-site.

The radiologics! consequences of a gaseous or liquid radioactive release are bounded by the fuel handling accident. With the plant permanently defueled condition, the l demands on the radwaste systems are lessened since no new radioisotopes are being generated by irradiation or fission. However, during 1998, CYAPCO plans to perform a decontamination of plant systems. During this time, the radiological consequences of a resin radiological release will be the bounding accident. Although this accident does not affect the proposed changes discussed herein, CYAPCO is providing the resin radiological dose calculation to the NRC Staff for their review.

Discussion in support of this license amendment request, the following information is provided; e Attachment 1 forwards the marked-up Operating License and Technical Specification pages and reflects the currently issued versions of the Operating License and Technical Specifications. Please be aware, for the sake of brevity, that the marked-up version does not include sections that I were deleted in their entirety.

. Attachment 2 forwards the retyped Operating License and Technical Specification pages. This attachment includes approximately 35 pages that have not been affected by this proposed change, for the following reasons:

• Completeness of the submittal, and

• That this proposed amendment, when issued, will replace the entire Operating License and Technical Specifications to assure that pages that were supposed to be retained will not be inadvertently discarded.

. Attachment 3 describes the proposed Operating License and Technical Specification changes.

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i U. S. Nucl:ar Regulatory Comm5 ion CY-97-006/Page 3 Attachment 4 provides a safety assessment for the proposed changes.

CYAPCO has roviewed the proposed Operating License and Technical Specification changes in accordance with 10CFR50.92. In addition, CYAPCO has determined that the changes do not involve a significant hazards consideration (SHC). The basis for this determination is also discussed in Attachment 4. 1

. Attachment 5 provides copies of the following calculations: l

• SFP-97-1575-DY, Revision 1, " Decay Heat and Heatup Rate Analysis for the Connecticut Yankee SFP."

> XX-XXX-60RA, Revision 1, " Radiological Assessment of a Spent Fuel Shipping Cask Drop in the CY Spent Fuel Pool,"

Note: This calculation also provides the radiological assessment for a fuel handling accident.

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• CYRESIN-01578-RY, Revision 0. " Radiological Consequences From a Resin Accident."

Since the HNP is not presently licensed to permit the lifting of a spent fuel shipping cask over the spent fuel pool, CYAPCO does not have to l consider the radiological consequences at this time. However, it has been evaluated to provide a comparison to the consequences of a fuel handi:ng accident.

Moreover, the Commission has provided guidance concerning the application of standards in 10CFR50.92 by providing certain examples (March 6,1986l 51FR7751) of amendrnents that are not likely to involve an SHC. The proposed changes described in Attachment 3 are not enveloped by a specific example. However, it has been demonstrated (i.e., Attachment 4) that the proposed changes do not involve an SHC.

Please be aware that CYAPCO intends to submit additional proposed Technical Specifications covering the Certified Fuel Handler as well as other aspects of defueled operation, administration and configuration.

Environmental Consideration CYAPCO has reviewed the proposed license amendment against the criteria of 10CFR51.22 for environmental considerations. The proposed changes do not involve an SHC, do not significantly increase the types and amounts of effluents that may be released off-site, and do not significantly increase individual or cumulative occupational radiation exposures. Based on the foregoing, CYAPCO concludes that the proposed changes meet the criteria delineated in 10CFR51.22(c)(9) for a categorical exclusion from the requirement of an environmentalimpact statement.

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U. S. Nuclear Regulatory Commission  ;

CY-97-006/Page 4 '

Plant Ooerations Review Committaa i The Plant Operations Review Committee has reviewed this proposed amendment request and concurs with the above determination.

Nuclear Safety Assessment Board Review The Nuclear Safety Assessment Board has reviewed this proposed amendment request and concurs with the above determination.  !

State Notification in accordance with 10CFR50.91(b), CYAPCO is providing the State of Connecticut with a copy of this proposed amendment request to ensure their awareness of this request.

Commitments The following three commitments are contained within this letter:

Commitment No. Commiiment CY-97-006-01 If any of the new fuel is still on-site when this amendment is approved, CYAPCO will implement j appropriate administrative controls. 1 CY-97-006-02 CYAPCO will inform the NRC Project Manager and the NRC Senior Resident inspector when the last of the new fuel is shipped off-site.

CY-97-006-03 An engineering review has been completed which will result in some of the specifications that are proposed to be deleted, being appropriately addressed in the Technical Requirements Manual (TRM).

The remaining statements made within this letter are for information only.

U. S. Nucl:ar Regulatory Commission CY-97-006/Page 5 Schedule Reautred for NRC Anoroval lt is CYAPCO's objective to discontinue unnecessary Operating Licensing and Technical Specification requirements as soon es possible. Therefore, CYAPCO requests that these proposed changes be reviewed and approved at the NRC Staffs earliest convenience. Finally, CYAPCO requests that the license amendment be effective upon issuance with implementation within 90 days.

Conclusion The proposed changes have been reviewed in accordance with 10CFR50.92 and have been determined to not constitute an SHC. In addition, the proposed changes have been reviewed against 10CFR51.22 and it has been determined that the proposed changes meet the criteria for a categorical exemption from requiring an environmental impact statement.

If the NRC staff should have any questions or comments regarding this submittal, please contact Mr. G. P. van Noordennen at (860) 267-3938.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY l

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, #ff T. C. Feigenba l

Executive V e President and Chief Nuciear Officer cc: H. J. Miller, NRC Region 1 Administrator M. B. Fairtile, NRC Project Manager, Haddam Neck Plant W. J. Raymond, NRC Senior Resident inspector, Haddam Neck Plant K. T. A. McCarthy, Director, CT DEP Monitoring and Radiation Division j

l Subscribed and sworn to before me this 30 day of May,1997 d_A G-runuh 7

.M Date Commission Expires: %N\tA 1

h 1

. .-_ ---- _ _ _ = . _ . . . . . .. . - _ . .

U. S. Nucl::ar R::gulatory Commission l CY-97-006/Page 6 l

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TABLE 1  !

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Haddam Neck Plant Spent Fuel Assembly Inventorv l

HNP Soent Fuel At Other Facilities l l Number Of Stainless Steel-Clad Fuel Assemblies At The GE Morris Facility 80 1

Number Of Stainless Steel-Clad Fuel Assemblies At The Battelle Hanford Facility 3 TOTAL HNP Spent Fuel Assemblies Off-Site 83 i HNP Soent Fuel in The HNP Spent Fuel Pool Number Of Stainless Steel-Clad Fuel Assemblies 858 Number Of Babcock And Wilcox-Type Zircaloy-Clad Fuel Assemblies 108 l

Number Of Westinghouse-Type Zircaloy-Clad Fuel Assemblies 53 l

TOTAL HNP Spent Fuel Assemblies On-Site 1019 i '

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