ML17279A160: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
(2 intermediate revisions by the same user not shown) | |||
Line 3: | Line 3: | ||
| issue date = 03/27/1987 | | issue date = 03/27/1987 | ||
| title = Application for Amend to License NPF-21,changing Tech Specs to Allow Use of Advanced Nuclear Fuels Corp,Inc Reload Fuel in Cycle 3.Fee Paid | | title = Application for Amend to License NPF-21,changing Tech Specs to Allow Use of Advanced Nuclear Fuels Corp,Inc Reload Fuel in Cycle 3.Fee Paid | ||
| author name = | | author name = Sorensen G | ||
| author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | | author affiliation = WASHINGTON PUBLIC POWER SUPPLY SYSTEM | ||
| addressee name = | | addressee name = | ||
Line 19: | Line 19: | ||
=Text= | =Text= | ||
{{#Wiki_filter:REQULAT INFORMATION DISTRIBUTIO | {{#Wiki_filter:REQULAT INFORMATION DISTRIBUTIO 'STEN (RIDS) | ||
'STEN (RIDS)ACCESSION NBR: 8704030044 DOC.DATE: 87/03/27 NOTARIZED: | ACCESSION NBR: 8704030044 DOC. DATE: 87/03/27 NOTARIZED: YES DOCKET 0 FACIL: 50-397 MPPSS Nuclear Progecti Unit 2i Mashington Public Poue 05000397 AUTH. NANE AUTHOR AFFILIATION SORENSEN> Q. C. Mashing ton Public Power Supply System RECIP. NANE RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) pc< ~<P | ||
YES DOCKET 0 FACIL: 50-397 MPPSS Nuclear Progecti Unit 2i Mashington Public Poue 05000397 AUTH.NANE AUTHOR AFFILIATION SORENSEN>Q.C.Mashing ton Public Power Supply System RECIP.NANE RECIPIENT AFFILIATION Document Control Branch (Document Control Desk)pc<~<P | |||
==SUBJECT:== | ==SUBJECT:== | ||
Application for amend to License NPF-2ii changing Tech Specs to allot'se o0 Advanced Nuclear Fuels Corp'nc rel.oad fuel in Cycle 3.DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR ENCL SIZE: TITLE: OR Submittal: | Application for amend to License NPF-2ii changing Tech Specs to allot'se o0 Advanced Nuclear Fuels Corp'nc rel.oad fuel in Cycle 3. | ||
General.Distribution NOTES: RECIPIENT ID CODE'/NANE | DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR ENCL SIZE: | ||
Document Control Desk Washington, D.C.20555 Gentlemen: | TITLE: OR Submittal: General. Distribution NOTES: | ||
RECIPIENT COPIES RECIPIENT C OP'IES ID CODE'/NANE LTTR ENCL ID CODE/NANE LTTR ENCL BMR EB 1 1 BMR EICSB 2 2 BMR FOB 1 1 BMR PD3 LA 0 | |||
.BMR PD3 PD 5 5 BRADFUTE> J 1 .1 BMR PSB 1 1 BMR RSB 1 1 INTERNAL: ACRS ADZ/LFXB NRR/DHFT/TSCB 1 hlRR/GRAS OQC/HDS2 0 01 EXTERNAL: EQ8(Q BRUSKEi S 1 1 LPDR NRC PDR 1 1 NSIC TOTAL NUNBER OF COPIES REQUIRED'TTR 28 ENCL 24 | |||
WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 March 27, 1987 G02-87-105 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen: | |||
==Subject:== | ==Subject:== | ||
NUCLEAR PLANT NO.2 OPERATING LICENSE NPF-21, REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS | NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21, REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS - RELOAD LICENSE AMENDMENT (CYCLE 3) | ||
-RELOAD LICENSE AMENDMENT (CYCLE 3)In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2.101, the Supply System hereby requests an amendment to the WNP-2 Technical Specifications (Tech.Specs.).This amendment is being submitted to allow the use of Advanced Nuclear Fuels Corporation, Inc.(ANF)reload fuel in Cycle 3 of WNP-2.ANF was formerly known as Exxon Nuclear Company who was the designer and fabricator of the reload fuel utilized during Cycle 2 of WNP-2.Changes to the following Tech.Specs.are being requested. | In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2. 101, the Supply System hereby requests an amendment to the WNP-2 Technical Specifications (Tech. Specs.). This amendment is being submitted to allow the use of Advanced Nuclear Fuels Corporation, Inc. (ANF) reload fuel in Cycle 3 of WNP-2. ANF was formerly known as Exxon Nuclear Company who was the designer and fabricator of the reload fuel utilized during Cycle 2 of WNP-2. Changes to the following Tech. | ||
2.0 Safety Limits and Limiting Safety System Settings (Introduction) 2.1.2 3/4.1.3.4 3/4.2.1 3/4.2.3 3/4.2.4 3/4.3.10 B 3/4.1.3 B 3/4.2.1 B 3/4.2.3 B 3/4.7.9 | Specs. are being requested. | ||
I.Technical Specification Changes II.WNP-2 Cycle 3 Reload Summary Report (WPPSS-EANF-109).(Includes the Startup Physics Program).III.WNP-2 Cycle 3 Reload Analysis (XN-NF-87-25). | 2.0 Safety Limits and Limiting Safety System Settings | ||
IV.WNP-2 Cycle 3 Plant Transient Analysis (XN-NF-87-24). | ( Introduction) 2.1.2 Thermal Power, High Pressure and High Flow 3/4.1.3.4 Four Control Rod Group Scram Insertion Times 3/4.2.1 Average Planar Linear Heat Generation Rate 3/4.2.3 Minimum Critical Power Ratio 3/4.2.4 Linear Heat Generation Rate 3/4.3.10 Neutron Flux Monitoring Instrumentation B 3/4.1.3 Control Rods B 3/4.2.1 Average Planar Linear Heat Generation Rate B 3/4.2.3 Minimum Critical Power Ratio B 3/4.7.9 Main Turbine Bypass Systems qadi 87aik7 I | ||
The Supply System has reviewed this change per 10 CFR 50.92 and determined that it does not: 1)Involve a significant increase in the probability or consequences of an accident previously evaluated because the transient analyses have been re-analyzed for the reload core.The proposed changes to the Tech.Specs.reflect new operating limits associated with the reload core, are based on the reload core physics and are within the previous acceptance criteria.2)Create the possiblity of a new or different kind of accident from any accident previously evaluated because the operational limitations applied to Cycle 3 are identical to Cycle 2.The values were derived from NRC qualified codes and by applying the most limiting transients throughout the cycle.These limita-tions are sufficient to ensure the plant is operated within previously accepted conditions. | S7O4OSOO44 | ||
3)Create a significant reduction in the margin of safety because the margin to safety for all accidents or operational occur-rences analyz'ed for Cycle 3 operation is either identical to or more conservative than that'used for,, Cycle 2.This change has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board.In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter.The Supply Sytem has evaluated this request in accordance with the criteria contained in 10 CFR 170.21 and has included a warrant of one hundred fifty dollars ($150.00)as initial payment for this applica-tion for Amendment under Facility Category A (Power Reactors). | 'P,'. | ||
U.S.Nuclear Regulatory Commission Page Three March 27, 1987 RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS-RELOAD LICENSE AMENDMENT (CYCLE 3)WNP-2 is scheduled to begin the spring outage on April 13, 1987.The plant is currently scheduled to resume commercial operation on June 15, 1987.Should you have any questions in this matter, please get in touch with Mr.P.L.-Powell, Manager, WNP-2 Licensing. | ., PDR, ADOCK 05000397 PDR | ||
Very truly yours, G.C.Sorensen, Manager Regulatory Programs WCW:dm Attachments (As stated)cc: JO Bradfute-NRC C Eschels | |||
U. S. Nuclear Regulatory Commission Page Two March 27, 1987 RE(VEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS-RELOAD LICENSE AMENDMENT (CYCLE 3) | |||
The following attachments to this letter are a Reload Summary Report, marked up Tech. Specs-. and the plant specific documents generated by ANF, all of which provide the basis for the proposed no significant hazards determination. | |||
I. Technical Specification Changes II. WNP-2 Cycle 3 Reload Summary Report (WPPSS-EANF-109). (Includes the Startup Physics Program). | |||
III. WNP-2 Cycle 3 Reload Analysis (XN-NF-87-25). | |||
IV. WNP-2 Cycle 3 Plant Transient Analysis (XN-NF-87-24). | |||
The Supply System has reviewed this change per 10 CFR 50.92 and determined that it does not: | |||
: 1) Involve a significant increase in the probability or consequences of an accident previously evaluated because the transient analyses have been re-analyzed for the reload core. The proposed changes to the Tech. Specs. reflect new operating limits associated with the reload core, are based on the reload core physics and are within the previous acceptance criteria. | |||
: 2) Create the possiblity of a new or different kind of accident from any accident previously evaluated because the operational limitations applied to Cycle 3 are identical to Cycle 2. The values were derived from NRC qualified codes and by applying the most limiting transients throughout the cycle. These limita-tions are sufficient to ensure the plant is operated within previously accepted conditions. | |||
: 3) Create a significant reduction in the margin of safety because the margin to safety for all accidents or operational occur-rences analyz'ed for Cycle 3 operation is either identical to or more conservative than that'used for,, Cycle 2. | |||
This change has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board. | |||
In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter. | |||
The Supply Sytem has evaluated this request in accordance with the criteria contained in 10 CFR 170.21 and has included a warrant of one hundred fifty dollars ($ 150.00) as initial payment for this applica-tion for Amendment under Facility Category A (Power Reactors). | |||
U. S. Nuclear Regulatory Commission Page Three March 27, 1987 RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS-RELOAD LICENSE AMENDMENT (CYCLE 3) | |||
WNP-2 is scheduled to begin the spring outage on April 13, 1987. The plant is currently scheduled to resume commercial operation on June 15, 1987. | |||
Should you have any questions in this matter, please get in touch with Mr. P. L. -Powell, Manager, WNP-2 Licensing. | |||
Very truly yours, G. C. Sorensen, Manager Regulatory Programs WCW:dm Attachments (As stated) cc: JO Bradfute - NRC C Eschels EFSEC JB Martin - NRC RV E Revell - BPA NS Reynolds - BLCP&R NRC Site Inspector | |||
STATE OF WASHINGTON ) | |||
==Subject:== | ==Subject:== | ||
Tech.Spec.Amendment e oa>cense yc e)I, G.C.Sorensen, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein;that I have full authority to execute this oath;that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true..$rensen, Manager Regulatory Programs | Tech. Spec. Amendment | ||
GIVEN under my hand and seal this+ | ) e oa >cense yc e ) | ||
County of Benton ) | |||
I, G. C. Sorensen, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true. | |||
. $ rensen, Manager Regulatory Programs On this day personally appeared before me G. C. Sorensen to me known to be the individual who executed the foregoing instrument and acknowledge that he signed the same as his free act and deed for the uses and purposes therein mentioned. | |||
GIVEN under my hand and seal this +Qfhday of , 1987. | |||
otary Public sn nd for the State of Washington Residing at}} |
Latest revision as of 08:22, 4 February 2020
ML17279A160 | |
Person / Time | |
---|---|
Site: | Columbia |
Issue date: | 03/27/1987 |
From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
Shared Package | |
ML17279A161 | List: |
References | |
GO2-87-105, TAC-64987, NUDOCS 8704030044 | |
Download: ML17279A160 (5) | |
Text
REQULAT INFORMATION DISTRIBUTIO 'STEN (RIDS)
ACCESSION NBR: 8704030044 DOC. DATE: 87/03/27 NOTARIZED: YES DOCKET 0 FACIL: 50-397 MPPSS Nuclear Progecti Unit 2i Mashington Public Poue 05000397 AUTH. NANE AUTHOR AFFILIATION SORENSEN> Q. C. Mashing ton Public Power Supply System RECIP. NANE RECIPIENT AFFILIATION Document Control Branch (Document Control Desk) pc< ~
J 1 .1 BMR PSB 1 1 BMR RSB 1 1 INTERNAL: ACRS ADZ/LFXB NRR/DHFT/TSCB 1 hlRR/GRAS OQC/HDS2 0 01 EXTERNAL: EQ8(Q BRUSKEi S 1 1 LPDR NRC PDR 1 1 NSIC TOTAL NUNBER OF COPIES REQUIRED'TTR 28 ENCL 24 WASHINGTON PUBLIC POWER SUPPLY SYSTEM P.O. Box 968 ~ 3000 George Washington Way ~ Richland, Washington 99352 March 27, 1987 G02-87-105 Docket No. 50-397 U. S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D. C. 20555 Gentlemen:
Subject:
NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21, REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS - RELOAD LICENSE AMENDMENT (CYCLE 3)
In accordance with the Code of Federal Regulations, Title 10, Parts 50.90 and 2. 101, the Supply System hereby requests an amendment to the WNP-2 Technical Specifications (Tech. Specs.). This amendment is being submitted to allow the use of Advanced Nuclear Fuels Corporation, Inc. (ANF) reload fuel in Cycle 3 of WNP-2. ANF was formerly known as Exxon Nuclear Company who was the designer and fabricator of the reload fuel utilized during Cycle 2 of WNP-2. Changes to the following Tech.
Specs. are being requested.
2.0 Safety Limits and Limiting Safety System Settings
( Introduction) 2.1.2 Thermal Power, High Pressure and High Flow 3/4.1.3.4 Four Control Rod Group Scram Insertion Times 3/4.2.1 Average Planar Linear Heat Generation Rate 3/4.2.3 Minimum Critical Power Ratio 3/4.2.4 Linear Heat Generation Rate 3/4.3.10 Neutron Flux Monitoring Instrumentation B 3/4.1.3 Control Rods B 3/4.2.1 Average Planar Linear Heat Generation Rate B 3/4.2.3 Minimum Critical Power Ratio B 3/4.7.9 Main Turbine Bypass Systems qadi 87aik7 I
S7O4OSOO44
'P,'.
U. S. Nuclear Regulatory Commission Page Two March 27, 1987 RE(VEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS-RELOAD LICENSE AMENDMENT (CYCLE 3)
The following attachments to this letter are a Reload Summary Report, marked up Tech. Specs-. and the plant specific documents generated by ANF, all of which provide the basis for the proposed no significant hazards determination.
I. Technical Specification Changes II. WNP-2 Cycle 3 Reload Summary Report (WPPSS-EANF-109). (Includes the Startup Physics Program).
III. WNP-2 Cycle 3 Reload Analysis (XN-NF-87-25).
IV. WNP-2 Cycle 3 Plant Transient Analysis (XN-NF-87-24).
The Supply System has reviewed this change per 10 CFR 50.92 and determined that it does not:
- 1) Involve a significant increase in the probability or consequences of an accident previously evaluated because the transient analyses have been re-analyzed for the reload core. The proposed changes to the Tech. Specs. reflect new operating limits associated with the reload core, are based on the reload core physics and are within the previous acceptance criteria.
- 2) Create the possiblity of a new or different kind of accident from any accident previously evaluated because the operational limitations applied to Cycle 3 are identical to Cycle 2. The values were derived from NRC qualified codes and by applying the most limiting transients throughout the cycle. These limita-tions are sufficient to ensure the plant is operated within previously accepted conditions.
- 3) Create a significant reduction in the margin of safety because the margin to safety for all accidents or operational occur-rences analyz'ed for Cycle 3 operation is either identical to or more conservative than that'used for,, Cycle 2.
This change has been reviewed and approved by the WNP-2 Plant Operations Committee and the Supply System Corporate Nuclear Safety Review Board.
In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter.
The Supply Sytem has evaluated this request in accordance with the criteria contained in 10 CFR 170.21 and has included a warrant of one hundred fifty dollars ($ 150.00) as initial payment for this applica-tion for Amendment under Facility Category A (Power Reactors).
U. S. Nuclear Regulatory Commission Page Three March 27, 1987 RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS-RELOAD LICENSE AMENDMENT (CYCLE 3)
WNP-2 is scheduled to begin the spring outage on April 13, 1987. The plant is currently scheduled to resume commercial operation on June 15, 1987.
Should you have any questions in this matter, please get in touch with Mr. P. L. -Powell, Manager, WNP-2 Licensing.
Very truly yours, G. C. Sorensen, Manager Regulatory Programs WCW:dm Attachments (As stated) cc: JO Bradfute - NRC C Eschels EFSEC JB Martin - NRC RV E Revell - BPA NS Reynolds - BLCP&R NRC Site Inspector
STATE OF WASHINGTON )
Subject:
Tech. Spec. Amendment
) e oa >cense yc e )
County of Benton )
I, G. C. Sorensen, being duly sworn, subscribe to and say that I am the Manager, Regulatory Programs for the WASHINGTON PUBLIC POWER SUPPLY SYSTEM, the applicant herein; that I have full authority to execute this oath; that I have reviewed the foregoing; and that to the best of my knowledge, information and belief the statements made in it are true.
. $ rensen, Manager Regulatory Programs On this day personally appeared before me G. C. Sorensen to me known to be the individual who executed the foregoing instrument and acknowledge that he signed the same as his free act and deed for the uses and purposes therein mentioned.
GIVEN under my hand and seal this +Qfhday of , 1987.
otary Public sn nd for the State of Washington Residing at