ML17275B051: Difference between revisions

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{{#Wiki_filter:/,/REGULATORY~FORMATION DISTRIBUTION S M (RIDS)(ACCESSION'BR; 8106020353.
{{#Wiki_filter:/
DOC~DATE: 81/05/26.NOTARIZED:.
,/
NO DOCKET'FACILE:50 397 WPPSS Nucleary ProJecti Unit''~Nashington Public Powe'.05000397 AUTH',NAME".AUTHOR AFFILIATION
REGULATORY~FORMATION DISTRIBUTION                                                                 S           M (RIDS)
'ATLOCK>RE G, Nashington Public Power~Supply System~RECIP~NAMEI RECIPIENT AFFILIATION ENGELKENqR
(
~HE Region 5g San Francisco<
ACCESSION'BR; 8106020353.                         DOC ~ DATE:           81/05/26.           NOTARIZED:.                               NO               DOCKET' FACILE:50 397         WPPSS Nucleary ProJecti Unit''~ Nashington Public Powe'. 05000397 AUTH',NAME" .             AUTHOR AFFILIATION G,         Nashington Public Power~ Supply System~ 'ATLOCK>RE RECIP ~ NAMEI             RECIPIENT AFFILIATION ENGELKENqR ~ HE           Region 5g San Francisco< Office'- of, the Directot (81/03/01)                                                                 ~
Office'-of, the Directot~(81/03/01)
                                                                  '               '             '   '                         ~       " V SUBJECT'i'ntei im deficiehcy rept r e', annulus pressur izat$ on,<<on< piping
~''''~" V~SUBJECT'i'ntei im deficiehcy rept r e', annulus pressur izat$on,<<on<piping sys attached.to or suppor ted from reactor vessel.or sa'cri f f cial, shieldwal 1<ini tf al 1 y r eported 810122'.Deficiency f ound repor tab l e;Final rept" by June~1982,'ISTRIBUTION
                                                            ~                                                                                ~
'CODEt B019S COPIES RECE'I/ED!LTR., ENCL: SIZE';" TITLE': Construction Deficiency Report~(10CFR50~55E)NOTES!PM'.
sys attached.to or suppor ted from reactor vessel. or sa'cri f f cial, shieldwal < ini tf al y r eported 810122'.Deficiency 1                      1 f ound repor tab l e; Final rept" by June~ 1982,
2" copies of al l matei ial~1 cy'.BNR LRG PM(L',RIB) 05000397 RECIPIENTS ID'ODE/NAME)
                          'CODEt B019S             COPIES       RECE'I/ED!LTR.,                       ENCL:     'ISTRIBUTION SIZE';"
ACTION: A/D: L~ICENSNG 04'USHBROOK"gM, 06" INTERNAL-;
TITLE':   Construction Deficiency                       Report~ (10CFR50 ~ 55E)
ASLBP/J>, HARD EDO'STAFF 19.HYD/GEO>BR 22'E'/EES'PA'0.
NOTES!PM'. 2"       copies of al l matei                 ial   ~ 1       cy'.BNR LRG PM(L',RIB)                                                             05000397 RECIPIENTS                     COPIES                              RECIPIENT'D'ODE/NAME>                                  COPIES'TTR<
OELD 21~QA BR ,14 STANDRDS DEV 21 COPIES I.TTR ENCL" 1 1 1 1>>1 fg 1 1 RECIPIENT'D'ODE/NAME>
ID'ODE/NAME)                     I. TTR ENCL"                                                                        .                ENCL~
.L'IC'R 42'C 05 AULUCKpR-,'7 D/DIR HUM FAC15'QUIP QUAL" BR11 IKE 09 LAIC QUAL<BR 12'RC~PDR" 02'V 13 REG F ILE 01 COPIES'TTR<
ACTION:         A/D: L~ICENSNG                                                       L'IC'R 42'C 05 06" 04'USHBROOK"gM, AULUCKpR-,'7 INTERNAL-; ASLBP/J>, HARD                               1                            D/DIR      HUM    FAC15'QUIP 1
ENCL~1 1 1 1 1 1 EXTERNAL: ACRS'SIC 16'8 16 1 1 LPDR 03~,~gg$o.TOTAL NUMBER<OF COPIES" REQUIREDe." LTTR 5Z.ENCL<
EDO'       STAFF   19.               1                                      QUAL" BR11                                        1 HYD/GEO> BR                             1                            IKE                                          09              1 22'E'/EES'PA'0.
E II~I E I H I E''I I f EH/H I III (f E~'H I, H J I Washington Public Power Supply, System P.Q.Box 968 3000 George Washington Way Richland, Washington 99352 (509)372-5000 May 26, 1981 G02-81-119 Docket No.50-397 Mr.R.H.Engelken Office of Inspection of Enforcement Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plaza 2990 North Ca 1 i f orni a Bl vd.Walnut Creek;California 94596
1>>                           LAIC QUAL< BR                                                 1 1                                  PDR"                                  02' 12'RC~
1 OELD                21~                fg                                                        V             13 QA BR              ,14                1                            REG   F ILE                                 01             1 STANDRDS DEV 21                        1 EXTERNAL:                             16'8             16       1                   LPDR                                         03~
ACRS'SIC 1
                                      ,~ gg$
o
. TOTAL NUMBER< OF COPIES" REQUIREDe." LTTR                                           5Z. ENCL<


==Dear Mr.Engelken:==
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Washington Public Power Supply, System P.Q. Box 968  3000 George Washington Way Richland, Washington 99352 (509) 372-5000 May  26, 1981 G02-81-119 Docket No. 50-397 Mr. R. H. Engelken Office of Inspection of Enforcement Nuclear Regulatory Commission Region  V Suite 202, Walnut Creek Plaza 2990 North Ca 1 i forni a Bl vd .
Walnut Creek;    California  94596
 
==Dear Mr. Engelken:==


==Subject:==
==Subject:==
WPPSS NUCLEAR PROJECT NO.2 POTENTIALLY REPORTABLE DEFICIENCY
WPPSS NUCLEAR PROJECT   NO. 2 POTENTIALLY REPORTABLE DEFICIENCY - 10CFR50.55(e)
-10CFR50.55(e)
ANNULUS PRESSURIZATION EFFECT ON PIPING SYSTEMS
ANNULUS PRESSURIZATION EFFECT ON PIPING SYSTEMS  


==Reference:==
==Reference:==
Letter flo. G02-81-13, dated January 22, 1981, RG Matlock, The Supply System,      to RH Engelken, NRC  Region  V The Reference letter informed your staff of a potentially reportable deficiency regarding the effect of annulus pressurization on pi ping systems attached to or supported from the reactor vessel or sacrificial shield wall.
Although the analysis of resulting loads on pi pi ng systems and suppor ts is not completed at this time, the Supply System has concluded that this condition is a reportable deficiency under the terms of 10CFR50.55(e),
since  it  is a safety concern requiring extensive analysis which should have been, but was not, considered in the design of safety-related pi ping and supports prior to release for construction.
Final results of the ongoing analysis of piping systems and supports, by the architect-engineer, will be included in the "Plant Design Assessment Report for SRV and LOCA Loads", for the WNP-2 facility. It is anticipated that the final revision to the report will be submitted in June 1982. Since this matter was initially raised by the NRC staff in conjunction with their ongoing revieius on the WNP-2 docket (ref. WNP-2 FSAR, question 110.019) the
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Letter flo.G02-81-13, dated January 22, 1981, RG Matlock, The Supply System, to RH Engelken, NRC Region V The Reference letter informed your staff of a potentially reportable deficiency regarding the effect of annulus pressurization on pi ping systems attached to or supported from the reactor vessel or sacrificial shield wall.Although the analysis of resulting loads on pi pi ng systems and suppor ts is not completed at this time, the Supply System has concluded that this condition is a reportable deficiency under the terms of 10CFR50.55(e), since it is a safety concern requiring extensive analysis which should have been, but was not, considered in the design of safety-related pi ping and supports prior to release for construction.
Nr. R. H. Engelken                     Nay 26, 1981 Page Two                                G02-81-119 Supply System   will address this   concern in that forum, and does not anticipate providing   a duplicate or supplementary report to NRC Region V.
Final results of the ongoing analysis of piping systems and supports, by the architect-engineer, will be included in the"Plant Design Assessment Report for SRV and LOCA Loads", for the WNP-2 facility.It is anticipated that the final revision to the report will be submitted in June 1982.Since this matter was initially raised by the NRC staff in conjunction with their ongoing revieius on the WNP-2 docket (ref.WNP-2 FSAR, question 110.019)the P I Nr.R.H.Engelken Page Two Nay 26, 1981 G02-81-119 Supply System will address this concern in that forum, and does not anticipate providing a duplicate or supplementary report to NRC Region V.Very truly yours, k R..hRTLOCK Program Director HNP-2 EAF:dm cc: V.Stello AD Toth RC Root TA Nangelsdorf RE Snaith HS Chin WNP-2 Files-NRC-NRC Resident Inspector-BER Site-Bechtel Si te-BSR NY-BPA}}
Very   truly yours, k
R.   . hRTLOCK Program   Director HNP-2 EAF:dm cc:   V. Stello       -  NRC AD Toth         -   NRC Resident Inspector RC Root        - BER Site TA Nangelsdorf - Bechtel Si te RE Snaith      - BSR NY HS Chin        - BPA WNP-2 Files}}

Latest revision as of 16:36, 29 October 2019

Interim Deficiency Rept Re Annulus Pressurization on Piping Sys Attached to or Supported from Reactor Vessel or Sacrificial Shield Wall,Initially Reported 810122.Deficiency Found Reportable.Final Rept by June 1982
ML17275B051
Person / Time
Site: Columbia Energy Northwest icon.png
Issue date: 05/26/1981
From: Matlock R
WASHINGTON PUBLIC POWER SUPPLY SYSTEM
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
References
10CFR-050.55E, 10CFR-50.55E, GO2-81-119, NUDOCS 8106020353
Download: ML17275B051 (6)


Text

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REGULATORY~FORMATION DISTRIBUTION S M (RIDS)

(

ACCESSION'BR; 8106020353. DOC ~ DATE: 81/05/26. NOTARIZED:. NO DOCKET' FACILE:50 397 WPPSS Nucleary ProJecti Unit~ Nashington Public Powe'. 05000397 AUTH',NAME" . AUTHOR AFFILIATION G, Nashington Public Power~ Supply System~ 'ATLOCK>RE RECIP ~ NAMEI RECIPIENT AFFILIATION ENGELKENqR ~ HE Region 5g San Francisco< Office'- of, the Directot (81/03/01) ~

' ' ' ' ~ " V SUBJECT'i'ntei im deficiehcy rept r e', annulus pressur izat$ on,<<on< piping

~ ~

sys attached.to or suppor ted from reactor vessel. or sa'cri f f cial, shieldwal < ini tf al y r eported 810122'.Deficiency 1 1 f ound repor tab l e; Final rept" by June~ 1982,

'CODEt B019S COPIES RECE'I/ED!LTR., ENCL: 'ISTRIBUTION SIZE';"

TITLE': Construction Deficiency Report~ (10CFR50 ~ 55E)

NOTES!PM'. 2" copies of al l matei ial ~ 1 cy'.BNR LRG PM(L',RIB) 05000397 RECIPIENTS COPIES RECIPIENT'D'ODE/NAME> COPIES'TTR<

ID'ODE/NAME) I. TTR ENCL" . ENCL~

ACTION: A/D: L~ICENSNG L'IC'R 42'C 05 06" 04'USHBROOK"gM, AULUCKpR-,'7 INTERNAL-; ASLBP/J>, HARD 1 D/DIR HUM FAC15'QUIP 1

EDO' STAFF 19. 1 QUAL" BR11 1 HYD/GEO> BR 1 IKE 09 1 22'E'/EES'PA'0.

1>> LAIC QUAL< BR 1 1 PDR" 02' 12'RC~

1 OELD 21~ fg V 13 QA BR ,14 1 REG F ILE 01 1 STANDRDS DEV 21 1 EXTERNAL: 16'8 16 1 LPDR 03~

ACRS'SIC 1

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. TOTAL NUMBER< OF COPIES" REQUIREDe." LTTR 5Z. ENCL<

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Washington Public Power Supply, System P.Q. Box 968 3000 George Washington Way Richland, Washington 99352 (509) 372-5000 May 26, 1981 G02-81-119 Docket No. 50-397 Mr. R. H. Engelken Office of Inspection of Enforcement Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plaza 2990 North Ca 1 i forni a Bl vd .

Walnut Creek; California 94596

Dear Mr. Engelken:

Subject:

WPPSS NUCLEAR PROJECT NO. 2 POTENTIALLY REPORTABLE DEFICIENCY - 10CFR50.55(e)

ANNULUS PRESSURIZATION EFFECT ON PIPING SYSTEMS

Reference:

Letter flo. G02-81-13, dated January 22, 1981, RG Matlock, The Supply System, to RH Engelken, NRC Region V The Reference letter informed your staff of a potentially reportable deficiency regarding the effect of annulus pressurization on pi ping systems attached to or supported from the reactor vessel or sacrificial shield wall.

Although the analysis of resulting loads on pi pi ng systems and suppor ts is not completed at this time, the Supply System has concluded that this condition is a reportable deficiency under the terms of 10CFR50.55(e),

since it is a safety concern requiring extensive analysis which should have been, but was not, considered in the design of safety-related pi ping and supports prior to release for construction.

Final results of the ongoing analysis of piping systems and supports, by the architect-engineer, will be included in the "Plant Design Assessment Report for SRV and LOCA Loads", for the WNP-2 facility. It is anticipated that the final revision to the report will be submitted in June 1982. Since this matter was initially raised by the NRC staff in conjunction with their ongoing revieius on the WNP-2 docket (ref. WNP-2 FSAR, question 110.019) the

P I

Nr. R. H. Engelken Nay 26, 1981 Page Two G02-81-119 Supply System will address this concern in that forum, and does not anticipate providing a duplicate or supplementary report to NRC Region V.

Very truly yours, k

R. . hRTLOCK Program Director HNP-2 EAF:dm cc: V. Stello - NRC AD Toth - NRC Resident Inspector RC Root - BER Site TA Nangelsdorf - Bechtel Si te RE Snaith - BSR NY HS Chin - BPA WNP-2 Files