ML20196G927

Forwards Addl Info Re TS Change Request NPF-38-193 to Increase Spent Fuel Pool Storage Capacity & Maximum Fuel Enrichment

ML20196G927
Person / Time
Site:	Waterford
Issue date:	07/21/1997
From:	Dugger C ENTERGY OPERATIONS, INC.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
W3F1-97-0181, W3F1-97-181, NUDOCS 9707230207
Download: ML20196G927 (7)

Text

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Ent rgy Oporttiona,Inc.

Killona, LA 70066-0751 Tel 504 739 6600 Charles M. Dugger Vice President. Operabons Waterford 3 1

W3F1-97-0181 A4.05

- PR July 21,1997 U.S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555

Subject:

Waterford 3 SES Docket No. 50-382 License No. NPF-38 Request For Additional Information Regarding Technical Specification Change Request NPF-38-193 Gentlemen:

3 By letter dated March 27,1997, Waterford 3 proposed to amend Operating License NPF-38 to increase the Spent Fuel Pool storage capacity and increase the maximum

, fuel enrichment. The NRC review staff requested additional information, in their letter 2

dated June 24,1997, regarding the proposed changes. This information is included in

the attachment entitled " Additional Information Regarding Technical Specification Change Request NPF-38-193." This additional information has no affect on the previously provided no significant hazards determination.

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/W) t 9707230207 970721 PDR ADOCK 05000382.

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Technical Specification Change Request NPF-38-193

,W3F1-97-0181 1 Page 2 July 21,1997 l

l Should you have any questions or comments concerning the additional information, please contact Roy Prados at (504) 739-6632.

'1 Very truly yours, '

l C.M. Dugger ,

Vice President, Operations l Waterford 3 CMD/RWP/tmm

Enclosures:

Affidavit Attachments cc: E.W. Merschoff, NRC Region IV C.P. Patel, NRC-NRR J. Smith i N.S. Reynolds l NRC Resident inspectcrs Office -

Administrator Radiation Protection Division (State of Louisiana)

American Nuclear Insurers -

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UNITED STATES OF AMERICA -

NUCLEAR REGULATORY COMMISSION in the matter of )

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Entergy Operations, incorporated ) Docket No. 50-382 Waterford 3 Steam Electric Station )

AFFIDAVIT '

Charles Marshall Dugger, being duly sworn, hereby deposes and says that he is Vice President Operations - Waterford 3 of Entergy Operations, Incorporated; that he is duly authorized to sign and file with the Nuclear Regulatory Commission the attached Additional Information Regarding Technical Specification Change Request NPF-38-193; that he is familiar with the content thereof; and that the matters set forth therein are true and correct to the best of his knowledge, information and belief.

lM u  %'m Charles Marshall Dugger . 6/

Vice President Operations - Waterford 3  ;

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STATE OF LOUISlANA ) l

) ss l PARISH OF ST. CHARLES )  !

Subscribed and sworn to before me, a Not Publ'c in and for the Parish and State above named this za e day of 4 .1997.

V O .

Y~ r L Notary Public My Commission expires a iM

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i i , ADDITIONAL INFORMATION REGARDING TECHNICAL SPECIFICATION CHANGE REQUEST NPF-38-193 Item 1 The amendment request discusses an increase in the maximum fuel enrichment to 5.0 wt% U-235 for allowed storage in the spent fuel pool. Have the fresh fuel storage racks been analyzed for the enrichment increase? If not, a restriction should be placed on fresh fuel storage in the new fuel vault. Discuss where the higher enriched fresh fuel will be initially stored.

Response

The fresh fuel storage racks have not been analyzed for the enrichment increase. Waterford 3 procedure RF-002-001, " Refueling Procedure Fuel Receipt" currently states that "New Fuel Assemblies shall not be placed in the New Fuel Storage Area." The higher enriched fresh fuel will initially be stored in the Region I spent fuel storage racks.

Item 2 TS 5.6.2, which discusses dry storage of new fuel for the first core loading in the spent fuel storage racks, is obsolete and should be revised to reference the fresh fuel storage pit and both the K, no greater than 0.95 if fully flooded and the K, no greater than 0.98 for aqueous foam optimum moderation conditions.

Response

This is an appropriate revision and the revised proposed TS 5.6.2 is attached.

Item 3 Since the criticality analysis accounted for fuel enriched to 5.0 +0.05 wt% U-235, would it be more appropriate to refer to 5.0 wt% as the maximum nominal enrichment in TS 5.3.17

Response

This is an appropriate change and the revised proposed TS 5.3.1 is attached.

PAGE 1 OF 2

t Item 4 What does " normal" % refer to in TS 5.6.17 1

Response

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" Normal" was used to differentiate between normal operations when % is less than 0.95 with unborated water and accident conditions when credit for soluble boron in the water is allowed.

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. i bFRIGN FEATURFR l

5.3 REACTOR CORE l l

FUEL ASSEMBLIES l 1

5.3.1 The reactor core shall contain 217 fuel assemblies with each fuel assembly containing a maximum of 236 fuel rods clad with Zircaloy-4. Eacn fuel rod shall have a nominal active fuel l length of 150 inches and contain a nominal total weight of 1830 grams uranium. The initial core l loading shall have a maximum enrichment of 2.91 weight percent U-235. Reload fuel shall be similar in physical design to the initial core loading. Assemblies shall have a maximum nominal enrichment of.).1,4re. weight percent U-235 p cWed they cent & cuff:&n' and p!:e= te ,

301 meet the final storage requirements described in Section 5.6. J CONTROL ELEMENT ASSEMBLIES 1

5.3.2 The reactor core shall contain 83 full-length and 8 part-length control element assemblies.

5.4 REACTOR COOLANT SYSTEM DESIGN PRESSURE AND TEMPERATURE 5.4.1 The Reactor Coolant System is designed and shall be maintained;

a. In accordance with the code requirements specified in Section 5.2 of the FSAR with allowance for normal degradation pursuant of the applicable Surveillance -I Requirements, '

b. For a pressure of 2500 psla, and

c. For a temperature of 650*F, except for the pressurizer and surge line which is 700*F. ,

1 VOLUME )

i 5.4.2 The total water and steem volume of the reactor coolant system is 11,800 +600,-0 cubic feet at a nominal T vg of 582.1*F. l 5.5 METEOROLOGICAL TOWERS LOCATION 5.5.1 The primary and backup meteorological towers shall be located as shown on Figure 5.1-1.

WATERFORD - UNIT 3 5-5 AMENDMENT NO.404

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DFSIGN FEATURES 5.6 FUEL STORAGE CRITICALITY 5.6.1 The spent fuel storage racks are designed and shall be maintained with:

a. A normal k egy c;9nt4e_g.f less than or equal to 0.95 when flooded with unborated l water, which includes a conservative allowance for uncertainties.

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b. A nominal 10.J.11_.38 inch center-to-center distance between fuel assemblies placed in Realon 1 (cask storaae oit) the spent fuel storage racks. I i

! c. A nominal 8.692 Inch canter to center distance between fuel assemblies in the Realon

. . 2 (soent fuel cool and refuelina canal) racks. except for the four southem-most racks l' in the spent fuel Dool which have an incmased N-S center-to-center nominal distance i of8.892 inches.

! d. New or oartially soent fuel assemblies may be allowed unrestrk?ed storaae in Realon j 4

1 racks. l

e. New fuel assemblies may be stored in the Realon 2 racks provided that thev are j stored in a " checkerboard oattem' as illustrated in Floure 5.6-1. i

f. Partially spent fuel assemblies with a discharae bumuo in the " acceptable rance" of l' Floure 5.6-2 may be_ allowed unrestricted storaae in the Realon 2 racks.

g. Partially spent fuel assemblies with a discharae bumuo in the " unacceptable ranae* of Fiaure 5.6-2 may be stored in the Realon 2 racks orovided that they are sto ed in a -

" checkerboard cattem*. as illustrated in Flaure 5.6-1. with spent fuel in the

" acceptable ranae" of Flaure 5.6-3.

5.6.2 The Iw for new fuel fer Se *-' c^re !^-8; stored dry-in the spent- new fuel storage racks shall be less than or eaual to 0.95 when flooded with unborated water and shall not exceed 0.98 when aqueous foam moderation is assumed.

DRAINAGE 5.6.3 The spent fuel pool is designed and shall be maintained to prevent inadvertent draining of the pool below elevation +40.0 MSL. When fuel is beina stored in the cask storaae cit and/or the

.refuelino canal. these areas will also be maintained at +40.0 MSL.

CAPACITY 5.6.4 The spent fuel pool is designed and shall be maintained with a storage capacity limited to no more than 40881849 fuel assemblies in the main oool. 255 fuel assemblies in the cask storaae oil and after permanent olant shutdown 294 fuel assemblies in the refuelina canal.

5.7 COMPONENT CYCLIC OR TRANSIENT LIMITS 5.7.1 The components identified in Table 5.7-1 are designed and shall be maintained within the cyclic or transient limits of Table 5.71.

WATERFORD - UNIT 3 5-6 AMENDMENT NOA04

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