ML18139A243
| ML18139A243 | |
| Person / Time | |
|---|---|
| Site: | Surry  |
| Issue date: | 05/15/1980 |
| From: | Ferguson J VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML18139A244 | List: |
| References | |
| NUDOCS 8005200653 | |
| Download: ML18139A243 (3) | |
Text
VIRGINIA ELECTRIC A.ND POWER COMPANY R:CCRMOND,VIRGI:NIA. 23261 May 15, 1980 Mr. Harold R. Denton, Director Office of Nuclear Reactor Regulation Attn:
Mr. Steven A. Varga, Chief Serial No. 400 LQA/WRM:rab Operating Reactors Branch No. 1 Division of Licensing U.S. Nuclear Regulatory CoIInUission Washington, D.C.
20555 Docket Nos. 50-280 50-281 License Nos. DPR-32 DPR-37
Dear Mr. Denton:
Ai.~ENDMENT TO OPERATING LICENSES SURRY POWER STATION UNIT NOS. 1 AND 2 PROPOSED TECHNICAL SPECIFICATION CHANGE NO. 85 Pursuant to 10 CFR 50.90, the Virginia Electric and Power Company hereby requests an amendment, in the form of changes to the Technical Specifications, to Operating Licenses DPR-32 and DPR-37 for the Surry Power Station, Unit Nos. 1 and 2.
The proposed changes are enclosed and have been designated Change No. 85.
Vepco is p~esently participating in a Department of Energy demonstration and evaluation program concerned with high burnup technology.
Implementation of this technology will involve the use of higher enrich-ment fuel than what is presently used at Surry in order to achieve higher batch average discharge burnups.
Currently, Technical Specification 5.3.A.3 limits the enrich-ment of new fuel to 3.6 weight percent of U-235.
Specification 5.4.B limits fuel stored in the new and spent fuel racks to 44 grams of Uranium-235 per axial centimeter of fuel assembly.
Both of these Specifications are equivalent e~ichments.
The utilization of higher enrichment fuel could eventually allow increased discharge fuel burnup of up to 45,000 MWD/MTU, subject to demon-stration of adequate fuel performance.
In anticipation that adequate fuel performance will be demonstrated, the proposed changes will increase the present enrichment limits to 4.1 weight percent of U-235 or 51.7 grams of U-235 per axial centimeter of fuel assembly.
Additional criticality analyses have been performed for both the high density,spent fuel racks and. the new fuel storage areas for the proposed enrichments.
These studies show that the keff in all cases will
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be less than 0.98* (actual keff worst case 0.902) for the new fuel storage ~'9 area and less than 0.95 (actual keff worst case 0.938) for the spent fuel ~i~~ ~
racks.
These analyses were done utilizing at least the same degree of 1
conservatism as was used in the original analysis.
The Nuclear Design
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Analysis Reports for the new fuel storage racks and the spent fuel racks
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are provided as attachments.
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VrnorNtA ELECTRIC AND PoW1rn. CoMPANY To Mr. Harold R. Denton In addition to the proposed change in enrichment, this request also proposes a change to the description of the analysis of the new fuel storage area.
The present wording states that keff will be less than or equal to O. 90 even if unborated water is used to fill the new fuel area.
In performing the analysis for this request, it was assumed that an aqueous foam envelopment as the result of fire fighting occurs, which is more conservative than the p.res_ent analysis.
This is the same assumption used for the North Anna Technical Specifications.
In addition, the acceptance criterion was increased to 0.98 to conform with the NRC Standardized Technical Specifications.
This proposed change has been reviewed and approved by the Station Nuclear Safety and Operating Committee and the System Nuclear Safety and Operating Committee. It has been determined that this request does not involve an unreviewed safety question.
Web.ave evaluated this request in accordance with the criteria in 10 CFR 170.22. It has been determined that this request involves a single safety issue; therefore, a Class III license amendment fee is re-quired for Unit 1 and a duplicate Class I license amendment fee is required for Unit 2.
Accordingly, a voucher check in the amount of $4,400.00 is enclosed in payment of the required fees.
In order to achieve a discharge fuel burnup of 36,000 MWD/MTU, fuel of approximately 3. 7 weight percent enrichment must be procured.
We request that the enclosed proposed changes be reviewed and approved prior to August 1, 1980 in order to. allow sufficient time for-procurement of this higher enrichment fuel.
Very truly yours,
~ty--.
J. H. Ferguson Executive Vice President-Power Attachments:
- 1. Proposed Technical Specification Change No. 85- *
- 2.
Nuclear Design Analysis Report for the new fuel storage racks
- 3. Nuclear Design Analysis Report for the high density fuel storage racks
- 4.
Voucher Check No. 20202 for $4,400.00 cc:
Mr. James P. O'Reilly, Director Office of Inspection and Enforcement Region II 2
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e COMMONWEALTH OF VIRGINIA.. )
. ) s. s.
CITY OF RICHMOND
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- Before me, a Notary Public, in and for the City and Common-wealth aforesaid, today personally appeared J. H. Ferguson, who being duly sworn, made oath and said (1) that he is Executive Vice President-Power of the Virginia Electric and Power Company, (2) that he is dul.y authorized to execute and file the foregoing Amendment in behalf of that Company, and (3) that the statements in the Amendment are true to the best of his knowledge and belief.
Given under Trr'f hand and notarial seal this \\5~ day of
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. My Cotmnissic,rt expires --~-,,,......_.().... t/
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N"otary Public (SEAL)