ML20086D795: Difference between revisions

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n U                                        O rOq (id'ld V ERMONT YANKMn NUcr#AR POWER CORPORATION L~VJ3    b                                                  3EVcNTY GEVc4 OHOVc LTHCcT RUTI . AND, VI'.1&IO NT OG701 R I F* L Y T O:
VYV-7504                      p, o. nox 357 VcRNON, VERMONI 05354 liarch 9, 1973 r            cv%/    N s                        @V Director                                                                    (o            4 L
i' Directorate of Licensing                                                      LLJ U.S. Atomic i:ncrgy Conni: sion                                  E                  4 $735-Uashington, D.C.              20545                              -
Idb                          -11 O grKiG C4luy y          y,9 E@
ItEFl:REHCC: Operating Licence DPR-28                                                W1 Docket No. 50-271                                          Mtep#              f f
g Abnormal Occurience No. An-73-07                                        -
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(;- 
 
==Dear Sir:==
f>
An defined by Technical Specifications for the Verrnont Yankee Nuclear
      ~
Pou,r nrar tem prtinn f, . 7 . n ,1          un nrn vnnnreina enn (n11n..<no Aher,v.                    ,1
      \.;'                  G.. < u i r u i. e un Au- 7 ',-0 7 .
          )I                      At approxinately 2300 on March 2, 1973 during conduct of an
  \. '
                  ,,      operability check of the High Pressure Coolant Injection (HPCI) Systen, j        a stean Icak was noted around the bonnet of the steam exhaust line
        ,; _                check valve (llPCI-65) . Although the HPCI systen was observed to be
            ' g , /, ,      operable, repair of the check valve was elected as an innediate course of actlon. Replacenent of the gasket precluded HPCI operability as
                  ;/        required by Section 3.5.1:.1.a of Technical Specifications.                            The react.or U        was operating at approxinately 60Z power at the time of this incident.
The :lPCI exhaust line stop check valve uns ganged shut and the check valve bonnet ganket pas replaced and the bonnet retightened.
Con c u r re n t. l y , the operability verification required by Section 4.5.E.2 l                          of Technical Specifications was initiated. At 0230 on March 3, 1973 the llPCI operability tnst van repeated satisfactorily, and no leakage was detected fron the bonnet of !!PCI-65.
The Plant Operations Review Committen concluded that although the valve bonnet leaked, the UFCI systen was still operable and would have perf orned i t:. designed function prior to gan);ing shut the exhaust line utop check valve. Additionally, to determine whether or not this failure was a ttributable to conditiens during system operation, the valve bonnet o
8312050123 730309 PDR ADOCK 05000271 fd
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    ''
* I'                G                                          VCnMoNT          GNKCC NUCLEAR T'OWCR Cor l
l Directorate of I.icennini;                                                                                                    l
            !!:irch 9, 1973 Page 2 l
stu<l tightneun will be checked follouing each IIPCI Tamp operability tent                                                  f during the next three months.                                                                                                !
Very truly yours, i
l                                                                    VI:1:MONT YANKEE NUCLEAR POWER CORPORATION B.U. Riley O-          1 f        '
[
i Plant Superintendent l
If.lE / rph                                                                                                                  .
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                                            . - _ _ _ _ _ _ _ _ _ _ , . . _ .                ..- _..,_ _ _,--                .._,.-s}}

Latest revision as of 07:40, 16 April 2020

Updated AO 73-07:on 730302,steam Leak Noted Around Bonnet of Steam Exhaust Line Check Valve.Hpci Exhaust Stop Check Valve Gagged Shut,Check Valve Bonnet Gasket Replaced & Bonnet Retightened
ML20086D795
Person / Time
Site: Vermont Yankee Entergy icon.png
Issue date: 03/09/1973
From: Riley B
VERMONT YANKEE NUCLEAR POWER CORP.
To:
US ATOMIC ENERGY COMMISSION (AEC)
Shared Package
ML20086D797 List:
References
AO-73-07, AO-73-7, VYV-2504, NUDOCS 8312050123
Download: ML20086D795 (2)


Text

,

n U O rOq (id'ld V ERMONT YANKMn NUcr#AR POWER CORPORATION L~VJ3 b 3EVcNTY GEVc4 OHOVc LTHCcT RUTI . AND, VI'.1&IO NT OG701 R I F* L Y T O:

VYV-7504 p, o. nox 357 VcRNON, VERMONI 05354 liarch 9, 1973 r cv%/ N s @V Director (o 4 L

i' Directorate of Licensing LLJ U.S. Atomic i:ncrgy Conni: sion E 4 $735-Uashington, D.C. 20545 -

Idb -11 O grKiG C4luy y y,9 E@

ItEFl:REHCC: Operating Licence DPR-28 W1 Docket No. 50-271 Mtep# f f

g Abnormal Occurience No. An-73-07 -

? -

(;-

Dear Sir:

f>

An defined by Technical Specifications for the Verrnont Yankee Nuclear

~

Pou,r nrar tem prtinn f, . 7 . n ,1 un nrn vnnnreina enn (n11n..<no Aher,v. ,1

\.;' G.. < u i r u i. e un Au- 7 ',-0 7 .

)I At approxinately 2300 on March 2, 1973 during conduct of an

\. '

,, operability check of the High Pressure Coolant Injection (HPCI) Systen, j a stean Icak was noted around the bonnet of the steam exhaust line

,; _ check valve (llPCI-65) . Although the HPCI systen was observed to be

' g , /, , operable, repair of the check valve was elected as an innediate course of actlon. Replacenent of the gasket precluded HPCI operability as

/ required by Section 3.5.1
.1.a of Technical Specifications. The react.or U was operating at approxinately 60Z power at the time of this incident.

The :lPCI exhaust line stop check valve uns ganged shut and the check valve bonnet ganket pas replaced and the bonnet retightened.

Con c u r re n t. l y , the operability verification required by Section 4.5.E.2 l of Technical Specifications was initiated. At 0230 on March 3, 1973 the llPCI operability tnst van repeated satisfactorily, and no leakage was detected fron the bonnet of !!PCI-65.

The Plant Operations Review Committen concluded that although the valve bonnet leaked, the UFCI systen was still operable and would have perf orned i t:. designed function prior to gan);ing shut the exhaust line utop check valve. Additionally, to determine whether or not this failure was a ttributable to conditiens during system operation, the valve bonnet o

8312050123 730309 PDR ADOCK 05000271 fd

  • 1 f

S PDR fg 1714 a

  • I' G VCnMoNT GNKCC NUCLEAR T'OWCR Cor l

l Directorate of I.icennini; l

!!:irch 9, 1973 Page 2 l

stu<l tightneun will be checked follouing each IIPCI Tamp operability tent f during the next three months.  !

Very truly yours, i

l VI:1:MONT YANKEE NUCLEAR POWER CORPORATION B.U. Riley O- 1 f '

[

i Plant Superintendent l

If.lE / rph .

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