ML19312D482: Difference between revisions

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{{#Wiki_filter:CRC FORM 366
{{#Wiki_filter:CRC FORM 366 U. S. NUCLEAR REIULATGY COMMISSION
* U. S. NUCLEAR REIULATGY COMMISSION
     * (777) *
     * (777) *
         ,r7                                                                      LICENSEE EVENT REPORT
         ,r7                                                                      LICENSEE EVENT REPORT
Line 38: Line 37:
23 l 0l 3l 4l 24            26 y
23 l 0l 3l 4l 24            26 y
27 l 0l 11 N      M W30
27 l 0l 11 N      M W30
[.-j 38 LOJ 32 K N AC                ON PL NT            ME                        HOURS          SB IT          FORI      S.      SUPPL 1            MAN F CTURER
[.-j 38 LOJ 32 K N AC                ON PL NT            ME                        HOURS          SB IT          FORI      S.      SUPPL 1            MAN F CTURER lXlggg g 33        34              35 g          [36Z j@
  .
lXlggg g 33        34              35 g          [36Z j@
_
l 0l q q 0l 3/                40 O@ B@ yg 44            42                  43 l Sl 2l 8l 0[@
l 0l q q 0l 3/                40 O@ B@ yg 44            42                  43 l Sl 2l 8l 0[@
44            47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS g l The event occurred as a result of a deficiency in the piping system stress analysis.                                                                                    I i i        l The af fected piping is being re-evaluated to determine what modifications, if any. to 1
44            47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS g l The event occurred as a result of a deficiency in the piping system stress analysis.                                                                                    I i i        l The af fected piping is being re-evaluated to determine what modifications, if any. to 1
           , 7        l existing pipe supports are required to ensure that the original system design criterial i 3        l a re me t.                                                                                                                                                l i 4        l                                                                                                                                                            l
           , 7        l existing pipe supports are required to ensure that the original system design criterial i 3        l a re me t.                                                                                                                                                l i 4        l                                                                                                                                                            l
     '7          8 9                                                                                                                                                            80 SYA    S          % POWER                        OTHER STATUS                DIS O      Y                      DISCOVERY DESCRIPTION i s        ]@l ]l 0 l 0 l@l                            NA                          l    l Bl@l            Notification from A/E                                      l A TlVITY      C$ TENT RELEASED OF RELEASE                      AMOUNT OF ACTIVITY                                                    LOCATIO'N CF RELEASE i s                                                          NA                    l          l              NA                                                      l
     '7          8 9                                                                                                                                                            80 SYA    S          % POWER                        OTHER STATUS                DIS O      Y                      DISCOVERY DESCRIPTION i s        ]@l ]l 0 l 0 l@l                            NA                          l    l Bl@l            Notification from A/E                                      l A TlVITY      C$ TENT RELEASED OF RELEASE                      AMOUNT OF ACTIVITY                                                    LOCATIO'N CF RELEASE i s                                                          NA                    l          l              NA                                                      l LZJ @ 'lz_l@l                                                          "            ''                                                                    *
        '      '
LZJ @ 'lz_l@l                                                          "            ''                                                                    *
                       * ,ERSON~a Ex,OSSES Nuu.ER          Tv,E          oESCR , TION @
                       * ,ERSON~a Ex,OSSES Nuu.ER          Tv,E          oESCR , TION @
                                                                                       "A i 7        l 010101@Lzl@l                                                                                                                                              I i
                                                                                       "A i 7        l 010101@Lzl@l                                                                                                                                              I i
Line 54: Line 48:
LOSS 08 OR OAMAGE TO FACIL?TY 43 TYPE      DESCRIPTION 8008240          '
LOSS 08 OR OAMAGE TO FACIL?TY 43 TYPE      DESCRIPTION 8008240          '
                                                                                                                                                                             .i          i i
                                                                                                                                                                             .i          i i
7 i 9 8 9 lzl@l    10 NA                                                                                                                                        l 80    l
7 i 9 8 9 lzl@l    10 NA                                                                                                                                        l 80    l 2 0 - ISSUFl @OE              NA      CRIPTION                                                                                          l      lllllllllllllj 7        8 9            to                                                                                                              68 63                          80 5 NAME OF PREPARER                  t.7    D      Neemfp+                                          PHONE:                          (703}o6 M 151
* 2 0 - ISSUFl @OE              NA      CRIPTION                                                                                          l      lllllllllllllj 7        8 9            to                                                                                                              68 63                          80 5 NAME OF PREPARER                  t.7    D      Neemfp+                                          PHONE:                          (703}o6 M 151
,


. . , ,
Virginia Electric and ' Power Company
Virginia Electric and ' Power Company
         . North Anna Power Station, Unit #1                  Attachment, Page 1 of 1 Docket No. 50-338 Report No. LER 80-034/01T-0 Description of Eve-t On March 7,1980, Stone & Webster discovered that several Class II (Q2) lines in the low and high head safety injection system have not been utress analyzed for fluid temperatures below 70*F. The subject lines transport water from the Refueling Water Storage Tank to the Reactor
         . North Anna Power Station, Unit #1                  Attachment, Page 1 of 1 Docket No. 50-338 Report No. LER 80-034/01T-0 Description of Eve-t On March 7,1980, Stone & Webster discovered that several Class II (Q2) lines in the low and high head safety injection system have not been utress analyzed for fluid temperatures below 70*F. The subject lines transport water from the Refueling Water Storage Tank to the Reactor
                                   ~
                                   ~
                                                                        .
Coolant System cold legs during the injection phase of the Emergency Core Cooling System, and, as such, can be exposed to fluid temperatures in the 40-50*F range. Th'c resulting pipe wall temperatures below 70*F could create limits on equipment and pipe supports which have not been previously analyzed.
Coolant System cold legs during the injection phase of the Emergency Core Cooling System, and, as such, can be exposed to fluid temperatures in the 40-50*F range. Th'c resulting pipe wall temperatures below 70*F could create
                                                                                          -
limits on equipment and pipe supports which have not been previously analyzed.
Probable Consequences of Occurrence With piping handling water temperatures less than 70*F, pipe stresses and -
Probable Consequences of Occurrence With piping handling water temperatures less than 70*F, pipe stresses and -
support loading could exceed design allowables and possibly prevent the Emergency Core Cooling System from performing its intended function during a postulated accident condition. The health and safety of the general public were not affected by this event. The low and high head safety injection lines for Unit 2 were also not analyzed for fluid temperatures below 70*F and are therefore similarly affected.
support loading could exceed design allowables and possibly prevent the Emergency Core Cooling System from performing its intended function during a postulated accident condition. The health and safety of the general public were not affected by this event. The low and high head safety injection lines for Unit 2 were also not analyzed for fluid temperatures below 70*F and are therefore similarly affected.
Line 72: Line 60:
Scheduled Corrective Action Pending the completion of the current safety injection piping temperature review, pipe support modifications, _ if required, will be made as determined necessary.
Scheduled Corrective Action Pending the completion of the current safety injection piping temperature review, pipe support modifications, _ if required, will be made as determined necessary.
Action Taken to Prevent Reccurrence No further actions are required.
Action Taken to Prevent Reccurrence No further actions are required.
                                                                                            !
I l
                                                                                            ,
l}}
I
                                                                                            !
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Latest revision as of 09:35, 1 February 2020

LER 80-034/01T-0:on 800307,S&W Discovered That Several Class 2 Lines in Low & High Head Safety Injection Sys Were Not Stress Analyzed for Fluid Temp.Caused by Deficiency in Piping Sys Stress Analysis
ML19312D482
Person / Time
Site: North Anna Dominion icon.png
Issue date: 03/21/1980
From: Cartwright W
VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19312D477 List:
References
LER-80-034-01T, LER-80-34-1T, NUDOCS 8003240473
Download: ML19312D482 (2)


Text

CRC FORM 366 U. S. NUCLEAR REIULATGY COMMISSION

  • (777) *

,r7 LICENSEE EVENT REPORT

/

CONTROL CLOCK: l 1

l l l l l lh 6

(PLEASE PRINT OR TYPE ALL REOUIRED INFORMATION) 57 CAT 68l@

l lO l 8i 9l l VlLICENSEE 7

Al NlCODE Al Sl 1l@l 0l 0l -l 0lLICENSE 14 15 0l 0l 0l 0l -l 0l 0l@l NUMtlER 25 4 l 1l 26 1 l 1l LICENSE TYPE 1l@l 30 CON'T 101il Sg a

y lL ]@l 0l 5l 0l 0l 0l 3l 3l 8l@l 68 0l 3lEVENT 69 Ol DATE 718l 01@l 14 013121118 75 REPORT DATE l O80l@

7 -8 60 61 DOCKET NUMB ER EVENT OESCRIPTION AND PROBABLE CONSEQUENCES h 10121 - l On March 7, 1980, Stone & Webster discovered that several Class II (02) lines in the 1 0 3 'l low and high head safety injection system have not been stress analyzed for fluid temp}-

O 4 l eratures which could be expected during the injectior; phase of the Emergency Core Cooll-O s l ing System. The health and safety of the general public were not affected by this l 0 s l occurrence. Reportable pursuant to T.S. 6.9.1.8.h. l 0 7 l I 101811 I E CODE S BC E COMPONENT CODE SUS O'E S E 7

O 9 8

l Sl Fl@ J@ W@ l Pl Il Pl El Xl Xl @ J h W @

9 to 11 12 13 18 19 20

_ SEOUE NTI AL OCCUR R ENCE' ~ REPORT REVISION LER/RO EVENT YEAR REPORT NO. CODE TYPE N O.

@ ,Rg l218l0l

_ 22 9

23 l 0l 3l 4l 24 26 y

27 l 0l 11 N M W30

[.-j 38 LOJ 32 K N AC ON PL NT ME HOURS SB IT FORI S. SUPPL 1 MAN F CTURER lXlggg g 33 34 35 g [36Z j@

l 0l q q 0l 3/ 40 O@ B@ yg 44 42 43 l Sl 2l 8l 0[@

44 47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS g l The event occurred as a result of a deficiency in the piping system stress analysis. I i i l The af fected piping is being re-evaluated to determine what modifications, if any. to 1

, 7 l existing pipe supports are required to ensure that the original system design criterial i 3 l a re me t. l i 4 l l

'7 8 9 80 SYA S  % POWER OTHER STATUS DIS O Y DISCOVERY DESCRIPTION i s ]@l ]l 0 l 0 l@l NA l l Bl@l Notification from A/E l A TlVITY C$ TENT RELEASED OF RELEASE AMOUNT OF ACTIVITY LOCATIO'N CF RELEASE i s NA l l NA l LZJ @ 'lz_l@l " *

  • ,ERSON~a Ex,OSSES Nuu.ER Tv,E oESCR , TION @

"A i 7 l 010101@Lzl@l I i

PERSONN E L INJU IES NuM ER 7-i s 8 9 1010101@lOESCRiPnON@

11 12 NA 80 l )

LOSS 08 OR OAMAGE TO FACIL?TY 43 TYPE DESCRIPTION 8008240 '

.i i i

7 i 9 8 9 lzl@l 10 NA l 80 l 2 0 - ISSUFl @OE NA CRIPTION l lllllllllllllj 7 8 9 to 68 63 80 5 NAME OF PREPARER t.7 D Neemfp+ PHONE: (703}o6 M 151

Virginia Electric and ' Power Company

. North Anna Power Station, Unit #1 Attachment, Page 1 of 1 Docket No. 50-338 Report No. LER 80-034/01T-0 Description of Eve-t On March 7,1980, Stone & Webster discovered that several Class II (Q2) lines in the low and high head safety injection system have not been utress analyzed for fluid temperatures below 70*F. The subject lines transport water from the Refueling Water Storage Tank to the Reactor

~

Coolant System cold legs during the injection phase of the Emergency Core Cooling System, and, as such, can be exposed to fluid temperatures in the 40-50*F range. Th'c resulting pipe wall temperatures below 70*F could create limits on equipment and pipe supports which have not been previously analyzed.

Probable Consequences of Occurrence With piping handling water temperatures less than 70*F, pipe stresses and -

support loading could exceed design allowables and possibly prevent the Emergency Core Cooling System from performing its intended function during a postulated accident condition. The health and safety of the general public were not affected by this event. The low and high head safety injection lines for Unit 2 were also not analyzed for fluid temperatures below 70*F and are therefore similarly affected.

Cause of Event The event occurred as a result of a deficiency on the part of the Architect Engineer in the stress analysis of the piping system.

Immediate Corrective Action The affected piping is presently being re-analyzed to determine if any modifications to the installed restraint arrangements are required as a result of the deficiency in the piping system stress analysis.

Scheduled Corrective Action Pending the completion of the current safety injection piping temperature review, pipe support modifications, _ if required, will be made as determined necessary.

Action Taken to Prevent Reccurrence No further actions are required.

I l

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