ML19351D733
| ML19351D733 | |
| Person / Time | |
|---|---|
| Site: | Yankee Rowe |
| Issue date: | 04/13/1977 |
| From: | Vandenburgh D YANKEE ATOMIC ELECTRIC CO. |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| WYR-77-38, NUDOCS 8011170692 | |
| Download: ML19351D733 (4) | |
Text
$,, j repored Chang 3 No. 145 h-
=.2pplement No. 1 TcI: phone 617 366-90\\l rwx 700 390-0739 YANKEE ATOMIC ELECTRIC COMPANY wa n-e om, g
20 Turnpuke Road Westborough, Massachusetts 01581
.YAmus.ia RegulatoQ,
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United States Nuclear Regulatory Commission g
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@ dM Attention: Office of Nuclear Reactor Regulation c.
Subject:
Core XIII Refueling
Reference:
(1)
License No. DPR-3 (Docket Mo. 50-29)
(2)
Proposed Change No. 145, subm3'ted January 6, 1977 Dear Sir Pursuant to Section 50.59 of the Commission's Rules and Regulations, the Yankee Atomic Electric Company hereby requests the authorization to make the following changes.
,I PROPOSED CHANGE: Reference is made to the Technical Specifications and
" Yankee Nuclear Power Station Core XII Performance Analysis" of License No. DPR-3.
1.
We propose to refuel the reactor for Core XIII operation by replacing 36 fuel assemblies.
2.
We propose to use Rod Groups C and A for control instead of the currently controlling Rod Groups A and B.
3.
We propose to increase the maximum allowable core inlet temperature from the current limit of 511 F to 515 F.
REASON FOR CHANGE:
1.
The introduction of the new fuel is necessary to maintain sufficient reactivity for continued operation at full rated power.
2.
The use of Rod Group C for control during normal operation will reduce the Rod Group A drive motor wear and thus increase the lifetime of these systems.
)
3.
The increase in the maximum allowable core inlet temperature from 511 F to 515 F is necessary to assure full power electrical output capability during certain periods in the summer months when the cooling pond temperatures are high.
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- = United Stat 03 Nuclear Reguintory Comiscien April 13, 1977 Atta: ' Office of Wuclear Reactor Regulation-Page Two DESCRIPTION'OF CHANGE:
1.
Core XIII will be loaded with thirty-six (36) fresh fuel assemblies fabricated by. Exxon Nuclear and forty - (40) mechanically identical fuel assemblies from Core XII also fabricated by Exxon Nuclear.
2.
Rod Group C will be utilized instead of Rod, Group A for normal operation and control of the plant at or near the maximum. allowable power level as shown in the revised Figure 3.1-1 of the Technical.
Specifications. Rod Group A will continue to be used as a controlling
-group but for low power application.
Figure 3.1-1 of the revised Technical Specifications included in this submittal provides the proposed Power Dependent Rod Group Insertion Limits for Core XIII operation.
3.
As a result of the present core' inlet temperature limit of 511 F, the plant operated 'at less than full electrical output during certain periods last sumer due to the warmer pond temperature which exists at that time of year. The increase in the maximum core inlet temperature to 515 F should compensate for these warmer pond temperatures and thus assure full electrical output capability.
Attachment A provides revisions to the Technical Specifications to i
account for these changes in plant operation. Attachment B provides the report entitled " Yankee Nuclear Power Station Core XIII Performance Analysis", which af.:.resses the mechanical design, thermal-hydraulic
~
design, nuclear design and safe +.y analysis aspects of these changes.
' SAFETY CONSIDERATIONS: As stated above, Attachment B provides the report entitled " Yankee Nuclear Power Station Core XIII Performance Analysis" which addresses the mechanical, thermal-hydraulic, nuclear and safety aspects of this change. Reference (2) provided a proposed design change to the current ECCS at Yankee Rowe which would yield less severe consequences during large break-LOCA. The IOCA analysis being performed for Core XIII, which will be submitted for.your review as soon as available as Appendix A to the "Yar.kee Nuclear Power-Station Core XIII Performance Analysis", will '
be basci on this revised system.
Based on the' considerations herein,'it is concluded that there is
. reasonable assurance that Core XIII operation within the proposed specifications will not endanger the health and safety of the public.
This proposed change has been reviewed by the Nuclear Safety Audit
.and Review Coczmittee.
SCHEDULE OF CHANGE: The Core XII-XIII refueling is scheduled to commence.
on June 3, 1977.
We. respectfully request review of this Proposed Change by the Con::11ssion as soon as practical.
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United Stat 03 NuclOtr Regulatory CommiC0 ion April 13, 1977 Attn: Office of Nuclear Reactor Regulation Page Three f
Any questions regarding this Proposed Change should be directed to either Mr. W. J. Szymczak or Mr. J. R. Chapman at our Engineering Office, 20 Turnpike Road, Westboro, Massachusetts, 01581, (617) 366-9011, Extensions 2844 or 2843, respectively.
Respectfully submitted YANKEE ATOMIC ELECTRIC COMPANY AcS D. E. Vandenburgh Senior Vice President COMMONWEALTH OF MASSACHUSE'ITS)
)ss.
COUNTY OF WORCESTER
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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 and 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 best of his knowledge and belief.
JM Armand R. Soucy Notary Public My Commission Expires September 9, 1977
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.y u.0. NuCLEAn cE ULATcav C wssCN UM C N3C DISTRIBUTION FoR PART 50 DOCKET MATERIAL TO. -
FROM:
DATE OF DOCUMENT Yankee Atomic Electric Coqpany 4/13/77
~N. R.,C.
Westborough, Mass.
DATE REcElvto D. E. Vandenburgh 4/14/77
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<L-DE SC",lP TION ENCLOSURE Ltr. notorized 4/13/77...trans the following:
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