ML17278A383: Difference between revisions
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
StriderTol (talk | contribs) (Created page by program invented by StriderTol) |
||
Line 19: | Line 19: | ||
=Text= | =Text= | ||
{{#Wiki_filter:REGUL INFORMATION DISTRIBUTI YSTEM (RIDS)ACCESSION NBR:8509170235 DOC | {{#Wiki_filter:REGUL INFORMATION DISTRIBUTI YSTEM (RIDS) | ||
~R, Licensing Branch 2" | ACCESSION NBR:8509170235 DOC DATE: 85/09/11, | ||
~ NOTARIZED YES DOCKET FACIL:50 BYNAME37 NPPSS Nuclear Project~ Unit 2i Washington Public Powe'5000397 AUTH AUTHOR- AFFILIATION SORENSEN<G.C, Hashingtan Public Power Supply System RECIP ~ NAME RECIPIENT AFFILIATION BUTLERiltl~ R, Licensing Branch 2" | |||
==SUBJECT:== | ==SUBJECT:== | ||
Application for amend to License NPF-21ichanging 6>S | Application for amend to License NPF-21ichanging Tech Spec 6>S 2 2 re administrative controls for corporate nuclear | ||
General Distribution NOTES: OL:12/20/83: | ~ ~ | ||
safety review board,Fee paid, DISTRIBUTION CODE ~ A001D COPIES RECEIVED:LTR ENCL / SIZE; ,4 ~ck TITLE'. OR Submittal: General Distribution NOTES: 05000397 OL:12/20/83: | |||
LTTR 28 ENCL 25 | RECIP IENT COPIES RECIPIENT ,COPIES ID CODE/NAME" LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB2 BC 01 7 7 INTERNAL: ACRS 09 6 6 ADM/LFMB 0 ELD/HDS2 1 0 NRR/DE/MTEB 1 NRR/DL DIR 1 1 NRR/DL/ORAB 0, NRR/Dl /TSRG 1 1 TB NRR/DSI/RAB 1 1 04 1 RGN5 1 1 EXTERNAL: 24X 1 1 EGS,G- BRUSKEgS LPDR 1- 1 NRC PDR 02 NSIC 1 1 P p 'Jl +) P l CO. | ||
TOTAL NUMBER OF COPIES REQUIRED:: LTTR 28 ENCL 25 | |||
==Dear Mr.Butler:== | ~ ~ | ||
I N ~ 1 N | |||
1 I ~ ~ i FP | |||
~ ~ | |||
Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372-5000 Docket No. 50-397 G02-85-552 September 11, 1985 Director of Nuclear Reactor Regulation Attention: Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555 | |||
==Dear Mr. Butler:== | |||
==Subject:== | ==Subject:== | ||
NUCLEAR PLANT NO.2 OPERATING LICENSE NPF-21, REtlUEST FOR AMENDMENT TO ADMINISTRATIVE CONTROLS FOR CORPORATE NUCLEAR SAFETY REVIEW BOARD (CNSRB)6.5.2.2 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"Adminis-trative Controls" section of the subject Technical Specifications. | NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21, REtlUEST FOR AMENDMENT TO ADMINISTRATIVE CONTROLS FOR CORPORATE NUCLEAR SAFETY REVIEW BOARD (CNSRB) 6.5.2. 2 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 "Adminis-trative Controls" section of the subject Technical Specifications. The proposed amendment involves the Corporate Nuclear Safety Review Board (CNSRB 6.5.2.2). | ||
The proposed amendment involves the Corporate Nuclear Safety Review Board (CNSRB 6.5.2.2).Technical Specification (TS)6.5.2.2, as presently written (see attached), states in part, that"The plant organization and the Directorates of Engi-neering, Support Services, and Licensing and Assurance shall be represented on the CNSRB.The Supply System proposes this sentence be deleted from the subject specification to provide increased flexibility in choosing the best technical representative, independent of organizational constraints. | Technical Specification (TS) 6.5.2.2, as presently written (see attached), | ||
Thus, the highest level of technical expertise can be insured as required in Sec-tion 4.7 of ANSI/ANS 3.1-1981 and Specification 6.5.2.1.In addition, this change is consistent with current industry practice, as indicated in the same technical specification sections for Limerick No.1, Shoreham No.1, Susquehanna No.1, Fermi No.2 and the General Electric Standard.BSD9170235 8509f i~J | states in part, that "The plant organization and the Directorates of Engi-neering, Support Services, and Licensing and Assurance shall be represented on the CNSRB. The Supply System proposes this sentence be deleted from the subject specification to provide increased flexibility in choosing the best technical representative, independent of organizational constraints. Thus, the highest level of technical expertise can be insured as required in Sec-tion 4.7 of ANSI/ANS 3.1-1981 and Specification 6.5.2.1. In addition, this change is consistent with current industry practice, as indicated in the same technical specification sections for Limerick No. 1, Shoreham No. 1, Susquehanna No. 1, Fermi No. 2 and the General Electric Standard. | ||
~1 V>Hr.W.R.Butler Page Two September ll, 1985 The Supply System has reviewed this change per 10 CFR 50.59 and determined that no unreviewed safety questions will'result from this amendment. | BSD9170235 8509f PDR ADOCK i | ||
This TS change has been reviewed and approved by the WNP-2 Plant Operations Com-mittee and the Supply System Corporate Nuclear Safety Review Board.n, t On April 6, 1983, the NRC,published gui,dance in the Federal'Re ister (48 FR 14870)concerning examples'of ameridments that are not likely to in-volve significant hazards consideration. | 05000397 | ||
One such example, (i)involves a"...purely administrative change to technical specifications: | ~J | ||
for example, a change to achieve consistency throughout the technical specifica-tions, correction of an error, or a change in nomenclature." Accordingly, this proposed change to the technical specifications involves no significant hazards consideration. | . P PDR | ||
\The Supply System has evaluated this request in accordance with 10 CFR 170.21 and has included a warrant for One hundred fifty dollars ($150.00)as initial payment for this application for amendment under Facility Category A (Power Reactors). | |||
In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter.Should you have any questions, please contact Hr.P.L.Powell, Hanager, WNP-2 Licensing. | ~1 V> | ||
Very truly yours, G.C.Sorensen, Hanager Regulatory Programs SIS/kjt Attachments cc: JO Bradfute WS Chin C.Eschels JB Hartin E.Revell AD Toth-NRC | Hr. W. R. Butler Page Two September ll, 1985 The Supply System has reviewed this change per 10 CFR 50.59 and determined that no unreviewed safety questions will'result from this amendment. This TS change has been reviewed and approved by the WNP-2 Plant Operations Com-mittee and the Supply System Corporate Nuclear Safety Review Board. | ||
n, t On April 6, 1983, the NRC,published gui,dance in the Federal 'Re ister (48 FR 14870) concerning examples'of ameridments that are not likely to in-volve significant hazards consideration. One such example, (i) involves a "... purely administrative change to technical specifications: for example, a change to achieve consistency throughout the technical specifica-tions, correction of an error, or a change in nomenclature." Accordingly, this proposed change to the technical specifications involves no significant hazards consideration. | |||
\ | |||
The Supply System has evaluated this request in accordance with 10 CFR 170.21 and has included a warrant for One hundred fifty dollars ($ 150.00) as initial payment for this application for amendment under Facility Category A (Power Reactors). | |||
In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter. Should you have any questions, please contact Hr. P. L. Powell, Hanager, WNP-2 Licensing. | |||
Very truly yours, G. C. Sorensen, Hanager Regulatory Programs SIS/kjt Attachments cc: JO Bradfute - NRC WS Chin - BPA C. Eschels - EFSEC JB Hartin - NRC RV E. Revell - BPA AD Toth - NRC Site | |||
I Il}} |
Latest revision as of 15:27, 29 October 2019
ML17278A383 | |
Person / Time | |
---|---|
Site: | Columbia ![]() |
Issue date: | 09/11/1985 |
From: | Sorensen G WASHINGTON PUBLIC POWER SUPPLY SYSTEM |
To: | Butler W Office of Nuclear Reactor Regulation |
Shared Package | |
ML17278A384 | List: |
References | |
GO2-85-552, TAC-59673, NUDOCS 8509170235 | |
Download: ML17278A383 (6) | |
Text
REGUL INFORMATION DISTRIBUTI YSTEM (RIDS)
ACCESSION NBR:8509170235 DOC DATE: 85/09/11,
~ NOTARIZED YES DOCKET FACIL:50 BYNAME37 NPPSS Nuclear Project~ Unit 2i Washington Public Powe'5000397 AUTH AUTHOR- AFFILIATION SORENSEN<G.C, Hashingtan Public Power Supply System RECIP ~ NAME RECIPIENT AFFILIATION BUTLERiltl~ R, Licensing Branch 2"
SUBJECT:
Application for amend to License NPF-21ichanging Tech Spec 6>S 2 2 re administrative controls for corporate nuclear
~ ~
safety review board,Fee paid, DISTRIBUTION CODE ~ A001D COPIES RECEIVED:LTR ENCL / SIZE; ,4 ~ck TITLE'. OR Submittal: General Distribution NOTES: 05000397 OL:12/20/83:
RECIP IENT COPIES RECIPIENT ,COPIES ID CODE/NAME" LTTR ENCL ID CODE/NAME LTTR ENCL NRR LB2 BC 01 7 7 INTERNAL: ACRS 09 6 6 ADM/LFMB 0 ELD/HDS2 1 0 NRR/DE/MTEB 1 NRR/DL DIR 1 1 NRR/DL/ORAB 0, NRR/Dl /TSRG 1 1 TB NRR/DSI/RAB 1 1 04 1 RGN5 1 1 EXTERNAL: 24X 1 1 EGS,G- BRUSKEgS LPDR 1- 1 NRC PDR 02 NSIC 1 1 P p 'Jl +) P l CO.
TOTAL NUMBER OF COPIES REQUIRED:: LTTR 28 ENCL 25
~ ~
I N ~ 1 N
1 I ~ ~ i FP
~ ~
Washington Public Power Supply System 3000 George Washington Way P.O. Box 968 Richland, Washington 99352-0968 (509)372-5000 Docket No. 50-397 G02-85-552 September 11, 1985 Director of Nuclear Reactor Regulation Attention: Mr. W. R. Butler, Chief Licensing Branch No. 2 Division of Licensing U.S. Nuclear Regulatory Commission Washington, D.C. 20555
Dear Mr. Butler:
Subject:
NUCLEAR PLANT NO. 2 OPERATING LICENSE NPF-21, REtlUEST FOR AMENDMENT TO ADMINISTRATIVE CONTROLS FOR CORPORATE NUCLEAR SAFETY REVIEW BOARD (CNSRB) 6.5.2. 2 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 "Adminis-trative Controls" section of the subject Technical Specifications. The proposed amendment involves the Corporate Nuclear Safety Review Board (CNSRB 6.5.2.2).
Technical Specification (TS) 6.5.2.2, as presently written (see attached),
states in part, that "The plant organization and the Directorates of Engi-neering, Support Services, and Licensing and Assurance shall be represented on the CNSRB. The Supply System proposes this sentence be deleted from the subject specification to provide increased flexibility in choosing the best technical representative, independent of organizational constraints. Thus, the highest level of technical expertise can be insured as required in Sec-tion 4.7 of ANSI/ANS 3.1-1981 and Specification 6.5.2.1. In addition, this change is consistent with current industry practice, as indicated in the same technical specification sections for Limerick No. 1, Shoreham No. 1, Susquehanna No. 1, Fermi No. 2 and the General Electric Standard.
BSD9170235 8509f PDR ADOCK i
05000397
~J
. P PDR
~1 V>
Hr. W. R. Butler Page Two September ll, 1985 The Supply System has reviewed this change per 10 CFR 50.59 and determined that no unreviewed safety questions will'result from this amendment. This TS change has been reviewed and approved by the WNP-2 Plant Operations Com-mittee and the Supply System Corporate Nuclear Safety Review Board.
n, t On April 6, 1983, the NRC,published gui,dance in the Federal 'Re ister (48 FR 14870) concerning examples'of ameridments that are not likely to in-volve significant hazards consideration. One such example, (i) involves a "... purely administrative change to technical specifications: for example, a change to achieve consistency throughout the technical specifica-tions, correction of an error, or a change in nomenclature." Accordingly, this proposed change to the technical specifications involves no significant hazards consideration.
\
The Supply System has evaluated this request in accordance with 10 CFR 170.21 and has included a warrant for One hundred fifty dollars ($ 150.00) as initial payment for this application for amendment under Facility Category A (Power Reactors).
In accordance with 10 CFR 50.91, the State of Washington has been provided a copy of this letter. Should you have any questions, please contact Hr. P. L. Powell, Hanager, WNP-2 Licensing.
Very truly yours, G. C. Sorensen, Hanager Regulatory Programs SIS/kjt Attachments cc: JO Bradfute - NRC WS Chin - BPA C. Eschels - EFSEC JB Hartin - NRC RV E. Revell - BPA AD Toth - NRC Site
I Il