ML17279A214: Difference between revisions

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{{#Wiki_filter:REQUL INFORMATION DISTRIBUTI iTEN (R IDS>V ACCESSION NBR: 8704220028 DOC.DATE.: 87/04/15 NOTARIZED:
{{#Wiki_filter:V REQUL       INFORMATION DISTRIBUTI             iTEN (R IDS>
NO FACIL: 50-397 WPPSS NucleaY Progecti Unit 2i Washington Public Powe AUTH.NANE AUTHOR AFFILIATION SORENSEN>Q.C.Washington Public Power Supply System:.REC IP.NANE RECIPlENT AFFILIATION Document Control Branch (Document Control Desk)DOCKET¹05000397
ACCESSION NBR: 8704220028         DOC. DATE.: 87/04/15     NOTARIZED: NO           DOCKET ¹ FACIL: 50-397   WPPSS NucleaY Progecti Unit 2i Washington Public Powe 05000397 AUTH. NANE           AUTHOR AFFILIATION SORENSEN> Q. C.     Washington Public Power Supply System:.
REC IP. NANE         RECIPlENT AFFILIATION Document Control Branch (Document Control Desk)


==SUBJECT:==
==SUBJECT:==
Advises that util satisfied requirement of 10CFR50.56 bg designing TIP-V-15 to be installed approx three feet outside containment penetration>
Advises that util satisfied requirement of 10CFR50. 56 bg designing TIP-V-15 to be installed approx three feet outside containment penetration> per 870401 tele on. Installat ion expected to allow sufficient access for testing 5 maint.
per 870401 tele on.Installat ion expected to allow sufficient access for testing 5 maint.DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR ENCL SIZE: TITLE: OR Submittal:
DISTRIBUTION CODE: A001D       COPIES RECEIVED: LTR         ENCL     SIZE:
General Distribution NOTES: RECIPIENT ID CODE/NANE PD5 LA SANWORTHz R COPIES LTTR ENCL 0 REC lP I ENT ID CODE/MANE PD5 PD COPIES LTTR ENCL 5 5 INTERNAL: ACRS NRR/DEST/ADE NRR/DOEA/TSB OGC/HDS2 6 6 1 1 1 0 ARl1/A8(F/LFNB 1 NRR/DEST/ADS
TITLE:   OR Submittal: General Distribution NOTES:
/ILRB 1 R 01;1 EXTERNAL: EQ8<Q BRUSQUE>8 NRC PDR 1 1 LPDR 1'SIC TOTAL NUJ')BER OF COPIES REQUIRED: LTTR 24 ENCL 21 yO Oo l I 4 l''sl'1 II*I Washington Public Power Supply System 30006eorgeWashingtonWay P.O.Box968 Richiand, Washington99352-0968 (509)372-5000 April 15, 1987 G02-87-135 P8 870415 8704>2002 OO397 pDR pD{3CK pD P Docket No.50-397 U.S.Nuclear Regulatory Commission Attn: Document Control Desk>lashington, D.C.20555 Gentlemen:
RECIPIENT         COPIES            REC lP I ENT        COPIES ID CODE/NANE       LTTR ENCL       ID CODE/MANE         LTTR ENCL PD5 LA                      0      PD5 PD                   5     5 SANWORTHz R INTERNAL: ACRS                     6     6     ARl1/A8(F/LFNB           1 NRR/DEST/ADE          1            NRR/DEST/ADS NRR/DOEA/TSB          1    1                  /ILRB         1 OGC/HDS2                    0      R                 01;     1 EXTERNAL:   EQ8<Q BRUSQUE> 8             1      LPDR NRC PDR 1
1   'SIC TOTAL NUJ')BER OF COPIES REQUIRED: LTTR         24   ENCL     21
 
yO             Oo l I 4 l'
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Washington Public Power Supply System 30006eorgeWashingtonWay     P.O. Box968 Richiand, Washington99352-0968   (509)372-5000 8704>2002P8 870415  OO397 pDR    pD{3CK pD April 15,   1987                                             P G02-87-135 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn:   Document Control Desk
>lashington, D.C. 20555 Gentlemen:


==Subject:==
==Subject:==
NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21, CL'ARIFICATION OF REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS - PRIMARY CONTAINMENT ISOLATION VALVE TABLE  3.6.3-1


==References:==
==References:==
1}    Letter, G02-87-064,    G. C. Sorensen    (SS)  to  NRC, Same  Subject, dated February 25,      1987
: 2)    Letter, G02-87-003,    G. C. Sorensen    (SS)  to E. G.
Adensam  (NRC}, Same  Subject, dated January 7, 1987
: 3)    Letter, G02-86-1028, G. C. Sorensen (SS) to E. G.
Adensam (NRC), Same Subject, dated November 18, 1986 Reference  3 requested  a change    to the HNP-2  Technical Specifications to reflect modifications to the Traversing Incore Probe (TIP) purge line currently scheduled for completion during the forthcoming Spring 1987 refueling outage. References 1 and 2 provided additional clarification and supplemental    information, respectively.
In a recent telephone conversation (April 1, 1987) with the Staff, the Supply System was requested to provide still further clarification.
Specifically, we were asked to clarify how we satisfied the following requirement of 10 CFR Part 50, Appendix A, Criterion 56:
      "Isolation valves outside containment shall          be  located  as close to the containment as practical
Page Two April 15, 1987 CLARIFICATION OF REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS PRIMARY CONTAINMENT ISOLATION VALVE - TABLE 3.6.3-1 The Supply System has satisfied this requirement by designing TIP-V-15 to be installed approximately three feet outside the containment penetration.      This is expected to allow sufficient access for testing and maintenance,      while  still being located as close as practical to the containment. TIP-V-6, located inside containment, will also be installed approximately three feet from the containment penetration.
Should you have any        further questions regarding this matter, please contact Mr. P. L. Powell, Manager, llNP-2 Licensing.
Very  truly yours, G. C. orensen, Manager Regulatory Programs HLA/tmh cc:    JO  Bradfute -    NRC C  Eschels -    EFSEC JB  Martin -    NRC'RV CE  Revell -    BPA NS Reynolds    -  BLCPSR NRC  Site Inspector


1}2)3)NUCLEAR PLANT NO.2, OPERATING LICENSE NPF-21, CL'ARIFICATION OF REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS
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-PRIMARY CONTAINMENT ISOLATION VALVE-TABLE 3.6.3-1 Letter, G02-87-064, G.C.Sorensen (SS)to NRC, Same Subject, dated February 25, 1987 Letter, G02-87-003, G.C.Sorensen (SS)to E.G.Adensam (NRC}, Same Subject, dated January 7, 1987 Letter, G02-86-1028, G.C.Sorensen (SS)to E.G.Adensam (NRC), Same Subject, dated November 18, 1986 Reference 3 requested a change to the HNP-2 Technical Specifications to reflect modifications to the Traversing Incore Probe (TIP)purge line currently scheduled for completion during the forthcoming Spring 1987 refueling outage.References 1 and 2 provided additional clarification and supplemental information, respectively.
                ,il li II i( h}}
In a recent telephone conversation (April 1, 1987)with the Staff, the Supply System was requested to provide still further clarification.
Specifically, we were asked to clarify how we satisfied the following requirement of 10 CFR Part 50, Appendix A, Criterion 56: "Isolation valves outside containment shall be located as close to the containment as practical Page Two April 15, 1987 CLARIFICATION OF REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS-PRIMARY CONTAINMENT ISOLATION VALVE-TABLE 3.6.3-1 The Supply System has satisfied this requirement by designing TIP-V-15 to be installed approximately three feet outside the containment penetration.
This is expected to allow sufficient access for testing and maintenance, while still being located as close as practical to the containment.
TIP-V-6, located inside containment, will also be installed approximately three feet from the containment penetration.
Should you have any further questions regarding this matter, please contact Mr.P.L.Powell, Manager, llNP-2 Licensing.
Very truly yours, G.C.orensen, Manager Regulatory Programs HLA/tmh cc: JO Bradfute-NRC C Eschels-EFSEC JB Martin-NRC'RV CE Revell-BPA NS Reynolds-BLCPSR NRC Site Inspector
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Latest revision as of 15:12, 29 October 2019

Advises That Util Satisfied Requirement of 10CFR50.56 by Designing TIP-V-15 to Be Installed Approx 3 Ft Outside Containment Penetration,Per 870401 Telcon.Installation Expected to Allow Sufficient Access for Testing & Maint
ML17279A214
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 04/15/1987
From: Sorensen G
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To:
NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
GO2-87-135, TAC-63935, NUDOCS 8704220028
Download: ML17279A214 (5)


Text

V REQUL INFORMATION DISTRIBUTI iTEN (R IDS>

ACCESSION NBR: 8704220028 DOC. DATE.: 87/04/15 NOTARIZED: NO DOCKET ¹ FACIL: 50-397 WPPSS NucleaY Progecti Unit 2i Washington Public Powe 05000397 AUTH. NANE AUTHOR AFFILIATION SORENSEN> Q. C. Washington Public Power Supply System:.

REC IP. NANE RECIPlENT AFFILIATION Document Control Branch (Document Control Desk)

SUBJECT:

Advises that util satisfied requirement of 10CFR50. 56 bg designing TIP-V-15 to be installed approx three feet outside containment penetration> per 870401 tele on. Installat ion expected to allow sufficient access for testing 5 maint.

DISTRIBUTION CODE: A001D COPIES RECEIVED: LTR ENCL SIZE:

TITLE: OR Submittal: General Distribution NOTES:

RECIPIENT COPIES REC lP I ENT COPIES ID CODE/NANE LTTR ENCL ID CODE/MANE LTTR ENCL PD5 LA 0 PD5 PD 5 5 SANWORTHz R INTERNAL: ACRS 6 6 ARl1/A8(F/LFNB 1 NRR/DEST/ADE 1 NRR/DEST/ADS NRR/DOEA/TSB 1 1 /ILRB 1 OGC/HDS2 0 R 01; 1 EXTERNAL: EQ8 8 1 LPDR NRC PDR 1

1 'SIC TOTAL NUJ')BER OF COPIES REQUIRED: LTTR 24 ENCL 21

yO Oo l I 4 l'

'sl

'1 II

  • I

Washington Public Power Supply System 30006eorgeWashingtonWay P.O. Box968 Richiand, Washington99352-0968 (509)372-5000 8704>2002P8 870415 OO397 pDR pD{3CK pD April 15, 1987 P G02-87-135 Docket No. 50-397 U.S. Nuclear Regulatory Commission Attn: Document Control Desk

>lashington, D.C. 20555 Gentlemen:

Subject:

NUCLEAR PLANT NO. 2, OPERATING LICENSE NPF-21, CL'ARIFICATION OF REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS - PRIMARY CONTAINMENT ISOLATION VALVE TABLE 3.6.3-1

References:

1} Letter, G02-87-064, G. C. Sorensen (SS) to NRC, Same Subject, dated February 25, 1987

2) Letter, G02-87-003, G. C. Sorensen (SS) to E. G.

Adensam (NRC}, Same Subject, dated January 7, 1987

3) Letter, G02-86-1028, G. C. Sorensen (SS) to E. G.

Adensam (NRC), Same Subject, dated November 18, 1986 Reference 3 requested a change to the HNP-2 Technical Specifications to reflect modifications to the Traversing Incore Probe (TIP) purge line currently scheduled for completion during the forthcoming Spring 1987 refueling outage. References 1 and 2 provided additional clarification and supplemental information, respectively.

In a recent telephone conversation (April 1, 1987) with the Staff, the Supply System was requested to provide still further clarification.

Specifically, we were asked to clarify how we satisfied the following requirement of 10 CFR Part 50, Appendix A, Criterion 56:

"Isolation valves outside containment shall be located as close to the containment as practical

Page Two April 15, 1987 CLARIFICATION OF REQUEST FOR AMENDMENT TO TECHNICAL SPECIFICATIONS PRIMARY CONTAINMENT ISOLATION VALVE - TABLE 3.6.3-1 The Supply System has satisfied this requirement by designing TIP-V-15 to be installed approximately three feet outside the containment penetration. This is expected to allow sufficient access for testing and maintenance, while still being located as close as practical to the containment. TIP-V-6, located inside containment, will also be installed approximately three feet from the containment penetration.

Should you have any further questions regarding this matter, please contact Mr. P. L. Powell, Manager, llNP-2 Licensing.

Very truly yours, G. C. orensen, Manager Regulatory Programs HLA/tmh cc: JO Bradfute - NRC C Eschels - EFSEC JB Martin - NRC'RV CE Revell - BPA NS Reynolds - BLCPSR NRC Site Inspector

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