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{{#Wiki_filter:ACCELERATED DI RIBUTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)ACCESSION NBR:9101080281 DOC.DATE: 90/12/28 NOTARIZED: | {{#Wiki_filter:ACCELERATED DI RIBUTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS) | ||
YES DOCKET FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH.NAME, AUTHOR AFFILIATION WALLACE,E.G. | ACCESSION NBR:9101080281 DOC.DATE: 90/12/28 NOTARIZED: YES DOCKET FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME, AUTHOR AFFILIATION WALLACE,E.G. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | ||
Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) | |||
==SUBJECT:== | ==SUBJECT:== | ||
Application for amends to Licenses DPR-33,DPR-52 6 DPR-86, consisting of Tech Spec 277,revising Surveillance Requirement 4.9.A.1.e to specify fuel oil quality for diesel generators. | Application for amends to Licenses DPR-33,DPR-52 6 DPR-86, D consisting of Tech Spec 277,revising Surveillance Requirement 4.9.A.1.e to specify fuel oil quality for diesel generators. | ||
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: TITLE: OR Submittal: | DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE: | ||
General Distribution | TITLE: OR Submittal: General Distribution A | ||
BLACK 1 Copy each to: S.Black,B.WILSON 1 Copy each to: S.Black,B.WILSON | NOTES:1 Copy each to: B.Wilson,S. BLACK 05000259 1 Copy each to: S.Black,B.WILSON 05000260 1 Copy each to: S. Black,B.WILSON 05000296 D | ||
PLEASE HELP US TO REDUCE iVASTE!CONTACT THE DOCUMENT CONTROL DESK, ROOM P l-37 (EXT.20079)TO | RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL KREBS,M. 1 1 HEBDON,F 1 1 ROSS,T. 2 2 INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H NRR/DET/ESGB 1 1 NRR/DOEA/OTSB11 NRR/DST 8E2 1 1 NRR/DST/SELB 8D NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E NUDOCS-ABSTRACT 1 1 OC il OGC/HDS3 1 0 G FILE Ol RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC NOTES 5 5 D | ||
~~TENNESSEE VALLEY AUTHORITY DEC 38 1990 5B Lookout Place TVA-BFN-TS-277, SUPPLEMENT 2 10 CFR 50.90 U.S.Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C.20555 Gentlemen: | D D | ||
In the Matter of | NOTE TO ALL "RIDS" RECIPIENTS: | ||
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P l-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROiVI DISI'RIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED! | |||
TOTAL NUMBER OF COPIES REQUIRED: LTTR 29 ENCL 27 | |||
,,l i | |||
~ ~ | |||
TENNESSEE VALLEY AUTHORITY DEC 38 1990 5B Lookout Place TVA-BFN-TS-277, SUPPLEMENT 2 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen: | |||
In the Matter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) TVA BFN TECHNICAL SPECIFICATION (TS) | |||
NO. 277, DIESEL GENERATORS | |||
==References:== | ==References:== | ||
: 1. Letter from M. 0. Medford to NRC dated January 31, 1990, TVA BFN Technical Specification No. 277 Diesel Generators | |||
: 2. Letter from E. G. Wallace to NRC dated March 20, 1990, TVA BFN Technical Specification No. 277 Diesel Generators | |||
: 3. Letter from M. J. Ray to NRC dated May 14, 1990, TVA BFN Technical Specification No. 277 Diesel Generators | |||
: 4. Letter from R. L. Gridley to NRC dated January 20, 1989, BFN Diesel Generator Evaluation Report In accordance with the provisions of 10 CFR 50.4 and 50.90, TVA is submitting a revision to the request for an amendment to licenses DPR-33, DPR-52, and DPR-68 which was previously submitted by References 1, 2, and 3. | |||
This change is the result of NRC's review of TS 277 and is as follows: | |||
Surveillance Requirement 4.9.A.l.e is revised to specify the applicable year of the ASTM-D975 standard for fuel oil quality. The reference to ASTM-D975 is revised to state ASTM-D975-89. | |||
The proposed determination of No Significant Hazards previously submitted (Reference 2) remains valid. Adding the reference to the applicable year of the ASTM standard incorporates into the surveillance requirement information that was previously included in the submitted bases. This is considered to be an administrative change. | |||
9%010802S PDR i .,.901228...-,. | |||
ADOCK 05000259 (0 | |||
P PDR | |||
(')4r 5;. ~if An Equal Opportunity Employer | |||
U.S. Nuclear Regulatory Commission DE 28 $ % | |||
NRC also requested that TVA provide additional information to support the proposed minimum fuel quantity required in the seven day fuel tank assemblies. NRC requested that TVA address the unusable quantity of fuel in the tank assembly. The unusable quantity in the tank has been calculated to be less than 640 gallons per seven day tank assembly. TVA believes that the minimum quantity of 35,280 gallons per seven day tank assembly which has been proposed includes sufficient conservatism to bound the value required for operation of the diesel until the tanks can be replenished from off-site supplies without adding the unusable volume. | |||
Regulatory Guide 1.137, Fuel Oil Systems for Standby Diesel Generators, endorses two methods of establishing fuel oil storage requirements. These methods are (1) calculations based on the assumption that the diesel generator operates continuously for seven days at rated capacity, and (2) calculations based on the time-dependent loads of the diesel generator. | |||
The value of 35,280 gallons proposed in TS-277 is based on continuous operation of a diesel generator at 2900 kW for seven days. The 2900 kW load used in this calculation is less than the seven day rating of 2950 kW and includes considerable margin with respect to the load required during a design basis accident. The seven day rating is based on the diesel generator manufacturers specifications that the diesels can be operated for seven days a year at this rating without impacting the recommended maintenance and inspection schedule. The fuel consumption rate of the diesels at 2900 kW is 210 gallons/hour. (210 gallons/hour x 7 days x 24 hours/day = 35,280 gallons) | |||
The value does not include an allowance for the unusable quantity of fuel in the seven day fuel storage assemblies. | |||
The BFN Diesel Generator Evaluation Report (Reference 4) submitted to NRC provides the diesel generator maximum steady state loading for a design basis accident for the first two hours of an event. The maximum steady state load during this period is 2778 kW, which was determined for a simultaneous loss of off-site power (LOOP) and loss of coolant accident (LOCA). The actual load demand will decrease below this value relatively early in the event after the emergency core cooling systems recover the reactor pressure vessel water level. | |||
A more realistic but still conservative load for use in determining the fuel storage requirement is the 2000 hour diesel generator rating of 2850 kW. A diesel generator load of 2850 bounds the 2778 kW maximum steady state load for a design basis accident. The fuel consumption of the diesels at 2850 kW is 205 gallons/hour. Using this fuel consumption rate results in a required volume of 34,440 gallons (205 gallons/hour x 7 days x 24 hours/day = 34,440 gallons). Adding the unusable quantity of 640 gallons to this quantity results in a storage requirement of 35,080 gallons. The proposed value of 35,280 gallons is more conservative than this quantity. | |||
In summary, TVA considers that the proposed minimum value of 35,280 gallons provides sufficient conservatism to ensure that the diesel generators are capable of operating until replenished from off-site supplies without incorporating additional margin for the unusable quantity in the seven day tank assembly. | |||
II U.S. Nuclear Regulatory Commission DEC 28 1990 There are no commitments contained in this submittal. | |||
The enclosure provides revised TS pages which include these changes. We request, that these specifications be made effective 30 days after issuance. | |||
If there are any questions, please telephone Patrick P. Carier at. | |||
(205) 729-3570. | |||
Very truly yours, TENNESSEE VALLEY AUTHORITY E. G. Wallace, Manager Nuclear Licensing and Regulatory Affairs Enclosures cc: See page 4 Subscribed and sworn to before me this %%4 day of ~ 1990. | |||
Notary Public My Commission Expires 1D30-84 My Commission Expires | |||
/ r | |||
'E | |||
U.S. Nuclear Regulatory Commission cc (Enclosures): | |||
American Nuclear Insurers Attention: Librarian The Exchange, Suite 245 270 Farmington Avenue Farmington, Connecticut 06032 Ms.,S. C. Black, Deputy Director Project Directorate II-4 U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Gary Daly, Chairman Limestone County Commission 310 Washington Street Athens, Alabama 35611 Dr. C. E. Fox State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36194 Mr. J. E. Jones General Electric Company 735 Broad Street Suite 1108 James Building Chattanooga, Tennessee 37402 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. Thierry M. Ross, Project Manager U. S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville'Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region 1I 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323}} | |||
American Nuclear Insurers Attention: | |||
Librarian The Exchange, Suite 245 270 Farmington Avenue Farmington, Connecticut 06032 Ms.,S.C.Black, Deputy Director Project Directorate II-4 U.S.Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr.Gary Daly, Chairman Limestone County Commission 310 Washington Street Athens, Alabama 35611 Dr.C.E.Fox State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36194 Mr.J.E.Jones General Electric Company 735 Broad Street Suite 1108 James Building Chattanooga, Tennessee 37402 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr.Thierry M.Ross, Project Manager U.S.Nuclear Regulatory Commission One White Flint, North 11555 Rockville'Pike Rockville, Maryland 20852 Mr.B.A.Wilson, Project Chief U.S.Nuclear Regulatory Commission Region 1I 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323}} |
Revision as of 00:35, 22 October 2019
ML18033B594 | |
Person / Time | |
---|---|
Site: | Browns Ferry ![]() |
Issue date: | 12/28/1990 |
From: | Wallace E TENNESSEE VALLEY AUTHORITY |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML18033B595 | List: |
References | |
TVA-BFN-TS-277, NUDOCS 9101080281 | |
Download: ML18033B594 (8) | |
Text
ACCELERATED DI RIBUTION DEMONST TION SYSTEM REGULATORY INFORMATION DISTRIBUTION SYSTEM (RIDS)
ACCESSION NBR:9101080281 DOC.DATE: 90/12/28 NOTARIZED: YES DOCKET FACIL:50-259 Browns Ferry Nuclear Power Station, Unit 1, Tennessee 05000259 50-260 Browns Ferry Nuclear Power Station, Unit 2, Tennessee 05000260 50-296 Browns Ferry Nuclear Power Station, Unit 3, Tennessee 05000296 AUTH. NAME, AUTHOR AFFILIATION WALLACE,E.G. Tennessee Valley Authority RECIP.NAME RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)
SUBJECT:
Application for amends to Licenses DPR-33,DPR-52 6 DPR-86, D consisting of Tech Spec 277,revising Surveillance Requirement 4.9.A.1.e to specify fuel oil quality for diesel generators.
DISTRIBUTION CODE: A001D COPIES RECEIVED:LTR ENCL SIZE:
TITLE: OR Submittal: General Distribution A
NOTES:1 Copy each to: B.Wilson,S. BLACK 05000259 1 Copy each to: S.Black,B.WILSON 05000260 1 Copy each to: S. Black,B.WILSON 05000296 D
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL KREBS,M. 1 1 HEBDON,F 1 1 ROSS,T. 2 2 INTERNAL: ACRS 6 6 NRR/DET/ECMB 9H NRR/DET/ESGB 1 1 NRR/DOEA/OTSB11 NRR/DST 8E2 1 1 NRR/DST/SELB 8D NRR/DST/SICB 7E 1 1 NRR/DST/SRXB 8E NUDOCS-ABSTRACT 1 1 OC il OGC/HDS3 1 0 G FILE Ol RES/DSIR/EIB 1 1 EXTERNAL: NRC PDR 1 1 NSIC NOTES 5 5 D
D D
NOTE TO ALL "RIDS" RECIPIENTS:
PLEASE HELP US TO REDUCE iVASTE! CONTACT THE DOCUMENT CONTROL DESK, ROOM P l-37 (EXT. 20079) TO ELIMINATEYOUR NAME FROiVI DISI'RIBUTION LISTS FOR DOCUMENTS YOU DON'T NEED!
TOTAL NUMBER OF COPIES REQUIRED: LTTR 29 ENCL 27
,,l i
~ ~
TENNESSEE VALLEY AUTHORITY DEC 38 1990 5B Lookout Place TVA-BFN-TS-277, SUPPLEMENT 2 10 CFR 50.90 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555 Gentlemen:
In the Matter of Docket Nos. 50-259 Tennessee Valley Authority 50-260 50-296 BROWNS FERRY NUCLEAR PLANT (BFN) TVA BFN TECHNICAL SPECIFICATION (TS)
NO. 277, DIESEL GENERATORS
References:
- 1. Letter from M. 0. Medford to NRC dated January 31, 1990, TVA BFN Technical Specification No. 277 Diesel Generators
- 2. Letter from E. G. Wallace to NRC dated March 20, 1990, TVA BFN Technical Specification No. 277 Diesel Generators
- 3. Letter from M. J. Ray to NRC dated May 14, 1990, TVA BFN Technical Specification No. 277 Diesel Generators
- 4. Letter from R. L. Gridley to NRC dated January 20, 1989, BFN Diesel Generator Evaluation Report In accordance with the provisions of 10 CFR 50.4 and 50.90, TVA is submitting a revision to the request for an amendment to licenses DPR-33, DPR-52, and DPR-68 which was previously submitted by References 1, 2, and 3.
This change is the result of NRC's review of TS 277 and is as follows:
Surveillance Requirement 4.9.A.l.e is revised to specify the applicable year of the ASTM-D975 standard for fuel oil quality. The reference to ASTM-D975 is revised to state ASTM-D975-89.
The proposed determination of No Significant Hazards previously submitted (Reference 2) remains valid. Adding the reference to the applicable year of the ASTM standard incorporates into the surveillance requirement information that was previously included in the submitted bases. This is considered to be an administrative change.
9%010802S PDR i .,.901228...-,.
ADOCK 05000259 (0
P PDR
(')4r 5;. ~if An Equal Opportunity Employer
U.S. Nuclear Regulatory Commission DE 28 $ %
NRC also requested that TVA provide additional information to support the proposed minimum fuel quantity required in the seven day fuel tank assemblies. NRC requested that TVA address the unusable quantity of fuel in the tank assembly. The unusable quantity in the tank has been calculated to be less than 640 gallons per seven day tank assembly. TVA believes that the minimum quantity of 35,280 gallons per seven day tank assembly which has been proposed includes sufficient conservatism to bound the value required for operation of the diesel until the tanks can be replenished from off-site supplies without adding the unusable volume.
Regulatory Guide 1.137, Fuel Oil Systems for Standby Diesel Generators, endorses two methods of establishing fuel oil storage requirements. These methods are (1) calculations based on the assumption that the diesel generator operates continuously for seven days at rated capacity, and (2) calculations based on the time-dependent loads of the diesel generator.
The value of 35,280 gallons proposed in TS-277 is based on continuous operation of a diesel generator at 2900 kW for seven days. The 2900 kW load used in this calculation is less than the seven day rating of 2950 kW and includes considerable margin with respect to the load required during a design basis accident. The seven day rating is based on the diesel generator manufacturers specifications that the diesels can be operated for seven days a year at this rating without impacting the recommended maintenance and inspection schedule. The fuel consumption rate of the diesels at 2900 kW is 210 gallons/hour. (210 gallons/hour x 7 days x 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s/day = 35,280 gallons)
The value does not include an allowance for the unusable quantity of fuel in the seven day fuel storage assemblies.
The BFN Diesel Generator Evaluation Report (Reference 4) submitted to NRC provides the diesel generator maximum steady state loading for a design basis accident for the first two hours of an event. The maximum steady state load during this period is 2778 kW, which was determined for a simultaneous loss of off-site power (LOOP) and loss of coolant accident (LOCA). The actual load demand will decrease below this value relatively early in the event after the emergency core cooling systems recover the reactor pressure vessel water level.
A more realistic but still conservative load for use in determining the fuel storage requirement is the 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> diesel generator rating of 2850 kW. A diesel generator load of 2850 bounds the 2778 kW maximum steady state load for a design basis accident. The fuel consumption of the diesels at 2850 kW is 205 gallons/hour. Using this fuel consumption rate results in a required volume of 34,440 gallons (205 gallons/hour x 7 days x 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />s/day = 34,440 gallons). Adding the unusable quantity of 640 gallons to this quantity results in a storage requirement of 35,080 gallons. The proposed value of 35,280 gallons is more conservative than this quantity.
In summary, TVA considers that the proposed minimum value of 35,280 gallons provides sufficient conservatism to ensure that the diesel generators are capable of operating until replenished from off-site supplies without incorporating additional margin for the unusable quantity in the seven day tank assembly.
II U.S. Nuclear Regulatory Commission DEC 28 1990 There are no commitments contained in this submittal.
The enclosure provides revised TS pages which include these changes. We request, that these specifications be made effective 30 days after issuance.
If there are any questions, please telephone Patrick P. Carier at.
(205) 729-3570.
Very truly yours, TENNESSEE VALLEY AUTHORITY E. G. Wallace, Manager Nuclear Licensing and Regulatory Affairs Enclosures cc: See page 4 Subscribed and sworn to before me this %%4 day of ~ 1990.
Notary Public My Commission Expires 1D30-84 My Commission Expires
/ r
'E
U.S. Nuclear Regulatory Commission cc (Enclosures):
American Nuclear Insurers Attention: Librarian The Exchange, Suite 245 270 Farmington Avenue Farmington, Connecticut 06032 Ms.,S. C. Black, Deputy Director Project Directorate II-4 U.S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville Pike Rockville, Maryland 20852 Mr. Gary Daly, Chairman Limestone County Commission 310 Washington Street Athens, Alabama 35611 Dr. C. E. Fox State Health Officer State Department of Public Health State Office Building Montgomery, Alabama 36194 Mr. J. E. Jones General Electric Company 735 Broad Street Suite 1108 James Building Chattanooga, Tennessee 37402 NRC Resident Inspector Browns Ferry Nuclear Plant Route 12, Box 637 Athens, Alabama 35609-2000 Mr. Thierry M. Ross, Project Manager U. S. Nuclear Regulatory Commission One White Flint, North 11555 Rockville'Pike Rockville, Maryland 20852 Mr. B. A. Wilson, Project Chief U.S. Nuclear Regulatory Commission Region 1I 101 Marietta Street, NW, Suite 2900 Atlanta, Georgia 30323