05000289/LER-1978-005-01, /01T-0:on 780119,Plant Operation Review Committee Found Containment Integrity Violated by Opening Valves BS-V47A & B During Pump Operability Test.Caused by Error in Operating Procedure OP 1104-5.Procedure to Be Revised

From kanterella
(Redirected from ML19261F273)
Jump to navigation Jump to search
/01T-0:on 780119,Plant Operation Review Committee Found Containment Integrity Violated by Opening Valves BS-V47A & B During Pump Operability Test.Caused by Error in Operating Procedure OP 1104-5.Procedure to Be Revised
ML19261F273
Person / Time
Site: Crane Constellation icon.png
Issue date: 02/02/1978
From: Stevens R
METROPOLITAN EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19261F271 List:
References
LER-78-005-01T, LER-78-5-1T, NUDOCS 7910250714
Download: ML19261F273 (2)


LER-1978-005, /01T-0:on 780119,Plant Operation Review Committee Found Containment Integrity Violated by Opening Valves BS-V47A & B During Pump Operability Test.Caused by Error in Operating Procedure OP 1104-5.Procedure to Be Revised
Event date:
Report date:
2891978005R01 - NRC Website

text

..

TARRATIVE CF L 0E:ISZE E7E:T! REPORT 73-05/lT At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> en. January 19., 1976, during a Plant Operatiens Reviev Cec =ittee Meeting, it was recogniced that en certain previcus cecasiens, centai=ent in-tegrity was viclated. During the 3S ?mp Operability Test CP110h-3 and the newly initiated =enthly ISI test,1300-3A, the Building Spray Pa=ps are placed en recirculation to the 3WST. Een the Building Spray ?2=p is recirculating, 3S-Vh7A cr 3 is Opened as a precaution in case any leakage is present through BS-V1A/3. Se leakage vill be drained instead of spraying devn the Reactor Building. Since SS-VkTA/3 are listed as closed in CP1101-3, tne periodic Operation of these valves during the abcve testing violates centai=ent in-tegrity as defined by T.S.1.7, and is reportable per T.S. 6.9.2. A(2).

The Reactor Building Integrity Check List requires that 3S-Vh7A/3 he closed to establish contai=ent integrity. Se operating precedure and ISI test allev cpening of 3S-Vh7A/3 to prevent leakage thrcush 35-71A/3 fren spraying devn the R.3. When the 3uilding Spray ?=p is operating. S e Operating Frecedure and ISI Precedure, therefore, conflict with the contai=ent integrity check list.

Since 3S-V30A/3 prevented any actual " lev path between the Centai=ent 3uilding and the Auxiliary 3uilding when SS-Vh7A/3 vere opened, this incident did not present a threat to the health and safety of the public.

It has been deterrdned that Opening 3S-Vh7A/3 is acceptable, since there is a check valve (3S-V30A/3) inside centainment, provided the precedure contains adequate adrinistrative centrols. Therefore, the TC:T (ncted in the initial telegras) to terrdnate the operation of ES-VhTA/3 is not needed.

The Reactor Building Integrity Checklist per OP1101-3 sh be revised to per=it opening 3S-Vh7A/3 under centrolled test perieds.

1481 294 7/7 791 osse

n

NRC FORM 46 (C ^ NUCLEAR REGULATORY COMMISSION (7 77)

.CENSEE EVENT REPORT CCNTRCL BLOCK: l l

l l

l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 1

6

' l ? 'l A I T lM lI l 1 l@l 0 j 0 l -l 0 l 0 l 0 l 0 l 0 l - l 0 l 0 l@l i l 1 l 1 l 1l 1l@l l

lg o

1 7

4 3 LICENSEE COOE 14 15 UCENSE %M8ER 25 26 uCENSE TYPE J3 57 CAT 58 CcvT

$c[RC[ ll @l0 l: lo lo lo b IA lo @ln I-l' Ic I-I Q @loi2InIel~l: @

0 1

7 3

60 61 OCCK ET NUMBER 68 69 EV ENT O ATE 74 75 REPORT DATE 30 EVENT OESCRIPTICN AND PROB ABLE CONSECUENCES h lDuring the Plant Operation Review C==ittee Meeting of 1-19-78, it was deter =ined that [

a

centain=ent integ-ity, as defined by T.S.

1.7, had been violated. 3S-7h7A/3 vere j

g 3

gepened during the 3S Pu=p Cperability Test, Cpersting Fr0cedure OF110h-5, and ISI Test g

,1300-3A.

This event is reportable per T.S.

6.9 2.A(2).

Because 3S-V30A/3 prevented l g,3,

actual flew frc= the R.3. to the Au c. Building, there vas nc threat to the health and ;

3,,

oi7 I"M7 #

  • WMU
  • I o

a i l

7 8 9 80 SYSTEM

CAUSE

CAUSE COMP.

VALVE

'OCE COCE SLBCCCE COMPCNENT CODE SLBCCCE SUSCOCE 13 I T

7 IIEl?fI i?

k__E)

O 9

i 3 7

7 8

9 10 11 12 13 16 19 20 SEQU ENTI AL CCCUAAENCE A EPCRT REVISION L

EVENT. EA R A EPCRT NO.

CCCE TYPE No.

@.a=E A AO 1718

- l 10101s!

Lfj a li l IT l-l bI 21 22 23 24 26 27 23 29 JQ 31 32 ACTION FUTURE EFFECT SHUTOCWN ATTACHMENT NP R O.4 PRIVE COMP.

COMPCNENT TAREN ACTICN ON PLANT METHCO HOURS u SUS MITTE D FCRM dL8.

SUPPLIE R VANUFACTURER 12 l@lxl@

l x i@

21@

101010101 lYl@

IN @

12 l@

Izi91919l@

33 34 35 26 31 40 el 42 43 44 47 CAUSE CESCRIPTION AND CCRRECTIVE ACTIONS i

o Kperatinz Procedure OP110h-5 and Is! Test loco 1A allev erenine of gg-yh73 /3 vger *ge i

i i

[ES Punp is Operatine to erevent sersvin the 9.3, should leatare t%~f- =c v' s /n l

7 lCecur. The TC:! r.cted in the 2L-hcur telezrs= to te-inate crerstien of 3S-yh' A /3 is I

3 lnct needed. Cperating Frecedure CP1101-3 shall be revised to re--it creni-e 3S-vh7A /3 l lunder centrolled test periods.

l 1

A 7

a 3 go METHOO CF F ACILITY ST A TUS

%PCWEA OTHER STATUS

  • OISCOV E R Y DISCOV E R Y ESCRIPTION 32 E l h l 1 l 0 l 0 l @
!A l

l2l@l 2TA l

5 7

8 9 10 12 13 44 45 46 80 ACTIVITY CCNTENT RELI4 SED OF RELE ASE AMOUNT CF ACTIVITY LOCATICN OF AELEASE -

il6 lClh NA l

l NA l

7 8 9 to 11 44 45 ga PERSCNNEL EXPCSURES TYPE @lCESCRIPTICN =

NLMBER l0 l0 l0l@l l

NA l

1 7

7 d 9 11 12 13 30 PERSONNEL INARIES Q

NLYBER C E SCRIPTICN

/

10 10 10 l@l NA l

i s

7 3 3 11

  • 2 go LOSS OF CR OAMAGE TO FActLITv -

TYPE OESCRIPTICP i

a 1: l@l NA l

7 d 3 to go NRC USE CNLY rSSUE[@DE CPIPTfCN lY Weekly news release Iilll liiiiiil{

3 7

3 9 to 68 69 30 -

U.

,, "-e-g".

UC 0

N NAME OF PAEDA AER "* d

  • DwCNE:

j