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{{#Wiki_filter:1 REGUL NFORMATION DISTRIBUTI TEM (RIDS)ACCESSION NBR: Sb j20j0204 DOC.DATE: 86/j j/j8 NOTARIZED: | {{#Wiki_filter:1 REGUL NFORMATION DISTRIBUTI TEM (RIDS) | ||
YES DOCKET¹FACIL: 50-397 WPPSS | ACCESSION NBR: Sb j20j0204 DOC. DATE: 86/ j j/ j8 NOTARIZED: YES Nuclear Progecti Unit 2i Washington Public DOCKET 05000397 | ||
¹ FACIL: 50-397 WPPSS Powe AUTH, NAME AUTHOR AFFILIATION SORENSEN> Q. C. Washing ton Pub l i c Power Supply System RECIP. NAME RECIPIENT AFFILIATION ADENSAM E. G. BWR Prospect Directorate 3 | |||
==SUBJECT:== | ==SUBJECT:== | ||
Application for amend to License NPF-2ii changing Tech Specs primary containment isolation valvei Table 3.h.3-i.Fee paid.DISTRIBUTION CODE: AOOID COPIES RECEIVED: LTR i ENCL i BIZE: TITLE: OR Submittal: | Application for amend to License NPF-2ii changing Tech Specs primary containment isolation valvei Table 3. h. 3-i. Fee paid. | ||
General Distribution NOTES: RECIPIENT ID CODE/NAME | DISTRIBUTION CODE: AOOID COPIES RECEIVED: LTR i ENCL i BIZE: | ||
TITLE: OR Submittal: General Distribution NOTES: | |||
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL BWR EB i i BWR EICSB 2 2 BWR FOB 1 1 BWR PD3 L* 1 0 BWR PD3 PD Oi 5 5 BRADFUTEs J j BWR PSB i i BWR RSB j i INTERNAL: ACRS 09 6 6 ADM/LFMB ELD/HDS2 i 0 NR /DHFT/TSCB | |||
.NRR/ORAS j 0 EQF 04 RGN5 i EXTERNAL: EQSQ BRUSKEi 8 i i LPDR 03 NRC PDR 02 j i NSIC 05 Ree id u3 C,~k 4 50.O TOTAL NUMBER OF COPIES REQUIRED: LTTR 29 ENCL 25 | |||
==Dear Ms.Adensam:== | 7 I | ||
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Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richiand, Washington 99352 (509) 372-5000 November 18, 1986. | |||
G02-86-1028 Docket No. 50-397 Director of Nuclear Reactor Regulation Attn: Ms. E. G. Adensam, Project Director BWR Project Directorate No. 3 Division of BWR Licensing UPS. Nuclear Regulatory Commission Washington, D. C. 20555 | |||
==Dear Ms. Adensam:== | |||
==Subject:== | ==Subject:== | ||
NUCLEAR PLANT NO.2 OPERATING LICENSE NPF-21, RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS-PRIMARY CONTAINMENT ISOLATION VALVE-TABLE 3.6.3-1 In accordance with the Code of Federal Regulations (CFR), Title 10, Parts 50.90 and 2.101, the Supply System hereby requests an amendment to the WNP-2 Operating License (Attachment 1).The amendment deals with a configuration change to the Traversing Incore Probe System (TIP)nitrogen purge line.This change is in response to the recent recognition of the misclassification of the'nitrogen purge line as an instrument line and, therefore, the requirement to meet GDC-54 and-56 configuration criteria.Upon completion of the change the TIP configuration for the nitrogen purge line penetration will meet GDC-54 and-56.This request is submitted in anticipation of the work being started and completed during the Spring 1987 refueling outage.The intent is to allow adequate time for staff review and approval, and arrange for release of the changed specification upon completion of the modification. | NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21, RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS-PRIMARY CONTAINMENT ISOLATION VALVE-TABLE 3.6.3-1 In accordance with the Code of Federal Regulations (CFR), Title 10, Parts 50.90 and 2.101, the Supply System hereby requests an amendment to the WNP-2 Operating License (Attachment 1). The amendment deals with a configuration change to the Traversing Incore Probe System (TIP) nitrogen purge line. This change is in response to the recent recognition of the misclassification of the'nitrogen purge line as an instrument line and, therefore, the requirement to meet GDC-54 and -56 configuration criteria. | ||
The addition of TIP-V-15, an ASME solenoid valve outside containment and an ASME check valve inside containment will allow purge gas to be supplied from outside containment. | Upon completion of the change the TIP configuration for the nitrogen purge line penetration will meet GDC-54 and -56. | ||
Attachment 2 is the proposed Final Safety Analysis Report which wi 11 be applicable upon completion of this work.Bhi2010204 86iii8 | This request is submitted in anticipation of the work being started and completed during the Spring 1987 refueling outage. The intent is to allow adequate time for staff review and approval, and arrange for release of the changed specification upon completion of the modification. | ||
~0 | The addition of TIP-V-15, an ASME solenoid valve outside containment and an ASME check valve inside containment will allow purge gas to be supplied from outside containment. Attachment 2 is the proposed Final Safety Analysis Report which wi 11 be applicable upon completion of this work. | ||
, ,.0~Page Two November 18, 1986 REQUEST FOR AMEND.TO TS-PRIMARY CONTAINMENT ISOLATION VALVE-TABLE 3.6.3-1 The Supply System has reviewed this Technical Specification change request per 10 CFR 50.59 and 50.92 and has determined that it does not represent an unreviewed safety question or involve a significant hazard consideration. | Bhi2010204 R | ||
The change does not: 1)Involve an increase in the probability or consequences of an accident previously evaluated because the modification conforms to containment isolation design criteria and, therefore, cannot increase the prob-ability or consequences of previously evaluated accidents. | 86iii8 I It ~tv,chic. g/>~ | ||
The design criteria are based on design basis accident evaluations; hence, with this modification conforming to the design criteria, no increase in the probability or consequences of an accident is credible.2)Create the possibility of a new or different kind of accident than previously evaluated because the'odification conforms to containment isolation design criteria and does not introduce a new design or plant operating mode beyond that originally intended in the TIP System design.3)Involve a significant reduction in a margin of safety, because no safety margins are jeopardized. | ~bye << | ||
The design change does not alter any limits required for containment isolation. | ADOCK 05000397 PDR | ||
The NRC has previously reviewed the nitrogen purge line configuration issue in the review of the Detroit Edison-Fermi, and Long Island Lighting Company-Shoreham facilities. | |||
In accordance with 10 CFR 170.21, an application fee of One hundred fifty dollars ($150.00)accompanies this request.In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter.This change has been reviewed and approved by the WNP-2 Plant Operations Comnittee and the Supply System Corporate Nuclear Safety Review Board.Should you require any further information or assistance to aid in evaluating this request, please contact Mr.P.L.Powell, Manager, WNP-2 Licensing. | ~0 | ||
Very trul yours, G.C.Sorensen, Manager Regulatory Programs MRW/tmh Attachment cc: JO Bradfute | , , .0 ~ | ||
Page Two November 18, 1986 REQUEST FOR AMEND. TO TS - PRIMARY CONTAINMENT ISOLATION VALVE - TABLE 3.6.3-1 The Supply System has reviewed this Technical Specification change request per 10 CFR 50.59 and 50.92 and has determined that it does not represent an unreviewed safety question or involve a significant hazard consideration. | |||
The change does not: | |||
: 1) Involve an increase in the probability or consequences of an accident previously evaluated because the modification conforms to containment isolation design criteria and, therefore, cannot increase the prob-ability or consequences of previously evaluated accidents. The design criteria are based on design basis accident evaluations; hence, with this modification conforming to the design criteria, no increase in the probability or consequences of an accident is credible. | |||
: 2) Create the possibility of a new or different kind of accident than previously evaluated because the'odification conforms to containment isolation design criteria and does not introduce a new design or plant operating mode beyond that originally intended in the TIP System design. | |||
: 3) Involve a significant reduction in a margin of safety, because no safety margins are jeopardized. The design change does not alter any limits required for containment isolation. | |||
The NRC has previously reviewed the nitrogen purge line configuration issue in the review of the Detroit Edison-Fermi, and Long Island Lighting Company-Shoreham facilities. | |||
In accordance with 10 CFR 170.21, an application fee of One hundred fifty dollars ($ 150.00) accompanies this request. In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter. | |||
This change has been reviewed and approved by the WNP-2 Plant Operations Comnittee and the Supply System Corporate Nuclear Safety Review Board. | |||
Should you require any further information or assistance to aid in evaluating this request, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing. | |||
Very trul yours, G. C. Sorensen, Manager Regulatory Programs MRW/tmh Attachment cc: JO Bradfute NRC C Eschels - EFSEC JB Martin - NRC RV E Revell - BPA NS Reynolds - BLCPSR NRC Site Inspector | |||
STATE OF WASHINGTON ) | |||
==Subject:== | ==Subject:== | ||
Primar Containment Isolation Valve 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.DATE/+, 1986 G.C.$.S , Manager Regula'tory Programs On this day personally appeared before me G.C.SORENSEN to me known to be the individual who executed the foregoing instrument and acknowledged that he signed the same as his free act and deed for the uses and purposes therein mentioned. | Primar Containment Isolation Valve | ||
GIVEN under my hand and seal this , 1986.otary Pu ic i n for the State of Washington Residing at~I gyral | ) | ||
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. | |||
DATE /+ , 1986 G. C. $ . S , Manager Regula'tory Programs On this day personally appeared before me G. C. SORENSEN to me known to be the individual who executed the foregoing instrument and acknowledged 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 , 1986. | |||
otary Pu ic i n for the State of Washington Residing at | |||
~ I gyral | |||
~0 L}} | ~0 L}} | ||
Revision as of 15:15, 29 October 2019
| ML17278B106 | |
| Person / Time | |
|---|---|
| Site: | Columbia  |
| Issue date: | 11/18/1986 |
| From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
| To: | Adensam E Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML17278B107 | List: |
| References | |
| GO2-86-1028, TAC-63935, NUDOCS 8612010204 | |
| Download: ML17278B106 (7) | |
Text
1 REGUL NFORMATION DISTRIBUTI TEM (RIDS)
ACCESSION NBR: Sb j20j0204 DOC. DATE: 86/ j j/ j8 NOTARIZED: YES Nuclear Progecti Unit 2i Washington Public DOCKET 05000397
¹ FACIL: 50-397 WPPSS Powe AUTH, NAME AUTHOR AFFILIATION SORENSEN> Q. C. Washing ton Pub l i c Power Supply System RECIP. NAME RECIPIENT AFFILIATION ADENSAM E. G. BWR Prospect Directorate 3
SUBJECT:
Application for amend to License NPF-2ii changing Tech Specs primary containment isolation valvei Table 3. h. 3-i. Fee paid.
DISTRIBUTION CODE: AOOID COPIES RECEIVED: LTR i ENCL i BIZE:
TITLE: OR Submittal: General Distribution NOTES:
RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LTTR ENCL ID CODE/NAME LTTR ENCL BWR EB i i BWR EICSB 2 2 BWR FOB 1 1 BWR PD3 L* 1 0 BWR PD3 PD Oi 5 5 BRADFUTEs J j BWR PSB i i BWR RSB j i INTERNAL: ACRS 09 6 6 ADM/LFMB ELD/HDS2 i 0 NR /DHFT/TSCB
.NRR/ORAS j 0 EQF 04 RGN5 i EXTERNAL: EQSQ BRUSKEi 8 i i LPDR 03 NRC PDR 02 j i NSIC 05 Ree id u3 C,~k 4 50.O TOTAL NUMBER OF COPIES REQUIRED: LTTR 29 ENCL 25
7 I
<<P <<4C I>>>>
, <<, <<<</$
f<>3 I "f}.II
}li44
>> I,<<
<<>>>>'l K
~ <<T>> g" T}>>4
<<T e }f>>',,<<>> f
$ <<>>
g<<5 k '1
<< ~ <<>>I I'
Washington Public Power Supply System P.O. Box 968 3000 George Washington Way Richiand, Washington 99352 (509) 372-5000 November 18, 1986.
G02-86-1028 Docket No. 50-397 Director of Nuclear Reactor Regulation Attn: Ms. E. G. Adensam, Project Director BWR Project Directorate No. 3 Division of BWR Licensing UPS. Nuclear Regulatory Commission Washington, D. C. 20555
Dear Ms. Adensam:
Subject:
NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21, RE/VEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS-PRIMARY CONTAINMENT ISOLATION VALVE-TABLE 3.6.3-1 In accordance with the Code of Federal Regulations (CFR), Title 10, Parts 50.90 and 2.101, the Supply System hereby requests an amendment to the WNP-2 Operating License (Attachment 1). The amendment deals with a configuration change to the Traversing Incore Probe System (TIP) nitrogen purge line. This change is in response to the recent recognition of the misclassification of the'nitrogen purge line as an instrument line and, therefore, the requirement to meet GDC-54 and -56 configuration criteria.
Upon completion of the change the TIP configuration for the nitrogen purge line penetration will meet GDC-54 and -56.
This request is submitted in anticipation of the work being started and completed during the Spring 1987 refueling outage. The intent is to allow adequate time for staff review and approval, and arrange for release of the changed specification upon completion of the modification.
The addition of TIP-V-15, an ASME solenoid valve outside containment and an ASME check valve inside containment will allow purge gas to be supplied from outside containment. Attachment 2 is the proposed Final Safety Analysis Report which wi 11 be applicable upon completion of this work.
Bhi2010204 R
86iii8 I It ~tv,chic. g/>~
~bye <<
ADOCK 05000397 PDR
~0
, , .0 ~
Page Two November 18, 1986 REQUEST FOR AMEND. TO TS - PRIMARY CONTAINMENT ISOLATION VALVE - TABLE 3.6.3-1 The Supply System has reviewed this Technical Specification change request per 10 CFR 50.59 and 50.92 and has determined that it does not represent an unreviewed safety question or involve a significant hazard consideration.
The change does not:
- 1) Involve an increase in the probability or consequences of an accident previously evaluated because the modification conforms to containment isolation design criteria and, therefore, cannot increase the prob-ability or consequences of previously evaluated accidents. The design criteria are based on design basis accident evaluations; hence, with this modification conforming to the design criteria, no increase in the probability or consequences of an accident is credible.
- 2) Create the possibility of a new or different kind of accident than previously evaluated because the'odification conforms to containment isolation design criteria and does not introduce a new design or plant operating mode beyond that originally intended in the TIP System design.
- 3) Involve a significant reduction in a margin of safety, because no safety margins are jeopardized. The design change does not alter any limits required for containment isolation.
The NRC has previously reviewed the nitrogen purge line configuration issue in the review of the Detroit Edison-Fermi, and Long Island Lighting Company-Shoreham facilities.
In accordance with 10 CFR 170.21, an application fee of One hundred fifty dollars ($ 150.00) accompanies this request. In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter.
This change has been reviewed and approved by the WNP-2 Plant Operations Comnittee and the Supply System Corporate Nuclear Safety Review Board.
Should you require any further information or assistance to aid in evaluating this request, please contact Mr. P. L. Powell, Manager, WNP-2 Licensing.
Very trul yours, G. C. Sorensen, Manager Regulatory Programs MRW/tmh Attachment cc: JO Bradfute NRC C Eschels - EFSEC JB Martin - NRC RV E Revell - BPA NS Reynolds - BLCPSR NRC Site Inspector
STATE OF WASHINGTON )
Subject:
Primar Containment Isolation Valve
)
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.
DATE /+ , 1986 G. C. $ . S , Manager Regula'tory Programs On this day personally appeared before me G. C. SORENSEN to me known to be the individual who executed the foregoing instrument and acknowledged 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 , 1986.
otary Pu ic i n for the State of Washington Residing at
~ I gyral
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