CY-98-071, Provides Supplemental Info in Support of 970530 Proposed License Amend,Reflecting Permanently Defueled Condition of HNP

From kanterella
(Redirected from CY-98-071)
Jump to navigation Jump to search
Provides Supplemental Info in Support of 970530 Proposed License Amend,Reflecting Permanently Defueled Condition of HNP
ML20247E992
Person / Time
Site: Haddam Neck File:Connecticut Yankee Atomic Power Co icon.png
Issue date: 05/07/1998
From: Mellor R
CONNECTICUT YANKEE ATOMIC POWER CO.
To:
NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20247E995 List:
References
CY-98-071, CY-98-71, NUDOCS 9805190081
Download: ML20247E992 (4)


Text

- - _ _ - _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _

4 l

CONNECTICUT YANKEE ATOMIC POWER COMPANY HADDAM NECK PLANT 362 INJUN HOLLOW ROAD EAST HAMPTON, CT 06424-3099 May 7,1998 l

Docket No. 50-213 J CY-98-071 Re: 10CFR50.90 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555 Haddam Neck Plant Supplement To Proposed Defueled License Amendment Spent Fuel Pool Coolina - Defueled introduction On May 30,1997,0) the Connecticut Yankee Atomic Power Company (CYAPCO) submitted a proposed license amendment to reflect the permanently defueied condition of the Haddam Neck Plant (HNP). The purpose of this letter is to provide supplemental information in support of the amendment request.

Backaround in a letter dated December 5,1996,(2) CYAPCO informed the NRC that the Board of l Directors of CYAPCO had decided to permanently cease operations at the HNP and that the fuel had been permanently removed from the reactor.

(1) CYAPCO Letter CY-97-006 from T. C. Feigenbaum to the U. S. Nuclear Regulatory Commission. " Proposed Revision To The Operating License And Technical Specifications Defueled Operating License And Technical Specifications," dated May 30,1997. ,

l (2) CYAPCO Letter B16066 from T. C. Feigenbaum to the U. S. Nuclear Regulatory \

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

9805190081 980507 P' PDR ADOCK 05000213 W PDR

U. S. Nucle:r Regulatory Commission CY-98-071/Page 2 The additions proposed herein reflect the limitations and requirements appropriate to the present configuration of the plant. The primary reason for this supplement is to provide Technical Specification 3/4.9.16 (" Spent Fuel Pool Cooling - Defueled") to assure appropriate spent fuel pool temperature limits are maintained while spent fuel is stored in the spent fuel pool.

Discussion In support of this supplemental proposed license amendment request, the following information is provided:

. Attachment 1 forwards the typed Technical Specification pages.

. Attachment 2 describes the proposed Technical Specification changes.

The current Technical Specification 3/4.9.15 is no longer applicable because the refueling outage ended on December 5,1996 when CYAPCO submitted its certification for permanent cessation of power operation and permanent removal of fuel from the reactor.(2) Nevertheless, CYAPCO chose to apply the LCO, Action Statement and Surveillance Requirements 4.9.15.2 and 4.9.15.3. Subsequently, the spent fuel pool decay heat load requirements were reanalyzed to reflect current actual conditions. This analysis was completed and submitted to the NRC Staff with a proposed license amendment on May 30,1997.")

The present decay heat load of less than 2.3E+06 BTU /hr is approximately 10 percent

of the heat load originally calculated for end-of-plant life with a full spent fuel pool. This heat load is well within the capacity of either heat exchanger. Therefore, the self-imposed restriction on heat exchanger operation is not applicable. CYAPCO will continue to restrict spent fuel pool temperature to .5150 'F and continue to verify the I spent fuel pool temperature every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until this proposed license amendment is approved and implemented, ihe proposed additions to the Technical Specifications supplement the May 30,1997 I submittal.0) This supplement does not alter the safety assessment and does not alter the determination that there are no significant hazards considerations (SHCs).

Environmental Consideration l

l The proposed additions to the Technical Specifications supplement the May 30,1997 i submittal.") This supplement does not alter the determination that the proposed additions meet the criteria delineated in 10CFR51.22(c)(9) for a categorical exclusion from the requirement of an environmental impact statement.

U. S. Nucl ar Regulatory Commission CY-98-071/Page 3 Plant Operations Review Committee l The Piant Operations Review Committee has reviewed this supplemental proposed amendment request and concurs with the above determination.

Nuclear Safety Assessment Board Review The Nuclear Safety Assessment Board has reviewed this supplemental 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 supplemental proposed amendment request.

Commitments This letter contains the following commitment:

CY-98-071-01 CYAPCO will continue to restrict spent fuel pool temperature to 5150 *F and continae to verify the spent fuel pool temperature every 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> until this proposed license amendment is approved and implemented.

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

Schedule Reauired for NRC Approval CYAPCO requests that these proposed additions be reviewed and approved at the NRC Staff's earliest convenience. In addition, CYAPCO requests that the license amendment be effective upon issuance with implementation within 60 days.

Conclusion The proposed additions 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.

t.h. S. Nuclear Regulatory Commission CY-98-071/Page 4 If the NRC Staff should have any questions regarding this submittal, please contact Mr. G. P. van Noordennen at (860) 267-3938.

Very truly yours, CONNECTICUT YANKEE ATOMIC POWER COMPANY ,

b.

R. A. Mellor T

, W Vice President - Operations and Decommissioning Attachments cc: H. J. Miller, NRC Region i Administrator T. L. Fredrichs, NRC Project Manager, Haddam Neck Plant W. J. Raymond, NRC Senior Resident inspector, Haddam Neck Plant D. Galloway, Acting Director, CT DEP Monitoring and Radiation Division  !

l Subscribed and sworn to before me l

l this 7* day of May,1998 1 Gan)P e- W Date Commission Expires: /2 h /[WoA

,