05000000/LER-1950-237, Updated LER 50-237/01L:on 760406,unacceptable Ultrasonic Indication Found on Isolation Condenser safe-end.Caused by Cracks in safe-ends.Cracked safe-end Removed & Sent to Bmcl for Metallographic Analysis: Difference between revisions

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| Mode =  
| Mode =  
| Docket = 05000000
| Docket = 05000000
| LER year = 2050
| LER year = 1950
| LER number = 237
| LER number = 237
| LER revision =  
| LER revision = 0
| Event date =  
| Event date =  
| Report date =  
| Report date =  
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=text=
=text=
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ACT!vrT Y      COdTENT                                                                              =
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NUV8tA              TYPE IBU9lol ol cl [2]                          l OtSCAPTON
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: 15) I            il A O9                                                                                =
Di LOSS OR OAMAGE TO FACILITY
* TYPE        DESCAtPTON                                                                                                            '
IE 12J UU l              eM 10                                                                                                                                                    El PUullCrTY iB0Dl                          NA G
ADDmONAL FACTORS 8403020366 760902 1511                                    N//                              gDRADOCK 05000 8 CD                                                                                                                                                                6'
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            , . ~                                                          .                                                      .
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    ,            FYEfiT DESCRIllIOv- Continued)              ,
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s of cracking in furnace-sensitized stainless steci forgingshave occurred on'
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      ,          both Unit-2 core spr.;y loops as well as on the !!PCI steam line.-
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* The safe-end (which was SA-182 F316 stainicss steel) was replaced with one forged from SA-182 F316L stainless ste'e1. -(50-237/1976-21)                                                       ,,       ,
r8 Io I ii si L'LI 7 09 10 11 12 17 43 44 47 48
r-                                                                                                                                        '
.I CAUSE DESCH:PTION l' 7[ff- ( fsfcytt),;'/jff -ftJr) phir$ pf ;>jtyyp y>,,y 9,9 gg,jj-yo j!/1TTrl 1.f- ("OL UlWiti!
l CAUSE DESCRIPTION (Continued)                                                                          ,
3 Li 7 fl 9 E
and four axially-oriented cracks at the 1:00, 4:00, 4:45, and 5:00 positions. The depth of the circumferential crack was found to be 0.261 inches, while the axial cracks ranged in depth from 0.255 to 0.500 inches. The circumferential crack was located approximately 3/8 inch from the safe-end-to-pipe weld and was 0.60 inches long at the I.D. surface.               The axial cracks ranged from 0.23 to 0.43 inches in length and extended to within 1/16 inch of the safe-end-to-pipe weld.
l /1/?Cl* A 70Ptf*3
The metallographic exanination revealed similar. features in both the axial and circumferential cracks: initiation at the I. D. surface, and                                                                                      .
;~C/' N f'TAf l.O f.f/r*/ /(. ////11 YS/!- l///~ f'f*S !)! TE Pf Vf*A/f*O TIIE f /
intergranular propagation in a heavily-sensitized microstructure. Microprobe analyses of fracture surfaces and cross sections of the cracks indicated no chlorides, fluorides, sulfides, or other possible corrosives. Moderate residual l               stresses from welding and possibly from inner surface grinding (up to 5 mils of cold working were observed) may also have been contributing factors. The mechanism I
iu9 t
of cracking is the'same as that experienced in'the HPCI safe-end, the 10-inch core spray piping, and the 4-inch recirculation bypass piping.
h ~ l 25 X o S rrNr /* or nsir ris'rrontre >?rM/ Al I Y-t')t*//~ 7/TTD C A Ac t' A T THf" 17'nn PM STA S
The cracked safe-end was manufactured from'SA-182 F316 stain 1 css steel and was unclad. It was approximately 5 inches long, with a 14-inch 0.D. at the piping end (0.56-inch wall thickness) end a 16-inch 0.D. at the nozzle end (1.08-inch wall thickness). The safe-end was furnace-sensitized during the post-weld stress relief treatment of the pressure vessel.                                                                          .
% POWIR DTHER STATUS O CO InY DIOCOVERY DESCR;PilON I
                                              .                                                                                                                            l Se g                                                                                                              9 g                                          .  .
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                                                        ..                      ..                          _-__-                          Q
ACT!vrT Y COdTENT
=
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PERSONNEL EXPOSURES NUV8tA TYPE OtSCAPTON IB lol ol cl [2]
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PERSONNEL INJUR:ES NUMutR DESCOTTION 15 1:010101 I H A 09 11 12 S
OTTSrTE CONSEOUENCES
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Di LOSS OR OAMAGE TO FACILITY TYPE DESCAtPTON IE 12J l
eM UU 10 El PUullCrTY iB l NA 0D G
ADDmONAL FACTORS 8403020366 760902 1511 N//
gDRADOCK 05000 8 CD 6'
'E I ao a
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Drctden fluclear l'o vor Stati                           ..
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g, 3 kg gd f
., o FYEfiT DESCRIllIOv-Continued) of cracking in furnace-sensitized stainless steci forgingshave occurred on' s
                .w
both Unit-2 core spr.;y loops as well as on the !!PCI steam line.-
                  .  ./      Morri     wls t0450 Telephono 815/g42,2920                             .
r The safe-end (which was SA-182 F316 stainicss steel) was replaced with one forged from SA-182 F316L stainless ste'e1. -(50-237/1976-21) l CAUSE DESCRIPTION (Continued) r-and four axially-oriented cracks at the 1:00, 4:00, 4:45, and 5:00 positions. The depth of the circumferential crack was found to be 0.261 inches, while the axial cracks ranged in depth from 0.255 to 0.500 inches.
g        hMM            LTr:: rn;.
The circumferential crack was located approximately 3/8 inch from the safe-end-to-pipe weld and was 0.60 inches long at the I.D. surface.
t g
The axial cracks ranged from 0.23 to 0.43 inches in length and extended to within 1/16 inch of the safe-end-to-pipe weld.
W             *h b
The metallographic exanination revealed similar. features in both the axial and circumferential cracks:
BBS Ltr. #76-531                                                       ' July 14, 1976                       h       (,               g
initiation at the I. D. surface, and intergranular propagation in a heavily-sensitized microstructure. Microprobe analyses of fracture surfaces and cross sections of the cracks indicated no chlorides, fluorides, sulfides, or other possible corrosives.
                                                                              ,                                                                                    ,g pZ 4 #:
Moderate residual l
l   ~
stresses from welding and possibly from inner surface grinding (up to 5 mils of I
(-                                 A 10 l     Mr. James.C. Keppler, Regional Director                                                                               9,l s '               -
cold working were observed) may also have been contributing factors.
j     Directorate of Regulatory Operations - Region III                                                               %
The mechanism of cracking is the'same as that experienced in'the HPCI safe-end, the 10-inch core spray piping, and the 4-inch recirculation bypass piping.
    ;      U. S. Nuc1 cur Kegulatory Commission                                                                                                                 g, ,
The cracked safe-end was manufactured from'SA-182 F316 stain 1 css steel and was unclad.
799 Roosevcit Road                                                                                                       s                 p        /
It was approximately 5 inches long, with a 14-inch 0.D. at the piping end (0.56-inch wall thickness) end a 16-inch 0.D. at the nozzle end (1.08-inch wall thickness). The safe-end was furnace-sensitized during the post-weld stress relief treatment of the pressure vessel.
    ,    Glen Ellyn, Illinois 60137
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Enclosed pleaset find an update report to Reportable Occurrence report
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    ,    number 50-237/1976-21.               This report is being submitted to your office in accordance with the Srcsden Nuc1 car Power Station Technical Specifications, Section 6.6.B.
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                                                                                              . 'S t ep)ienson Station Superintendent Dresden Nuclear Power Station BBS:jo Enclosure                                                                               .-
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cc: Director of Inspection & Enforcement                                           -
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Director of Management Information & Program Control i
 
File /NRC s
Drctden fluclear l'o vor Stati g,
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BBS Ltr. #76-531
' July 14, 1976 h
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l Mr. James.C. Keppler, Regional Director 9,l s '
j Directorate of Regulatory Operations - Region III U. S. Nuc1 cur Kegulatory Commission g,,
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799 Roosevcit Road s
Glen Ellyn, Illinois 60137
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Enclosed pleaset find an update report to Reportable Occurrence report number 50-237/1976-21.
This report is being submitted to your office in accordance with the Srcsden Nuc1 car Power Station Technical Specifications, Section 6.6.B.
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. 'S t ep)ienson Station Superintendent Dresden Nuclear Power Station BBS:jo Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File /NRC i
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LICENSEE EVENT REPOPN V
t Cf N51               tVlN1 L CE *.M t                                                                                               TYPE                 fvPE NtWI                                            tiCENGE NUV0t R
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[@] Iv la I s I el s1_d                             lo lo I-I ol ol ol ol 01-101025I I2641 i i t t i l o30l I31ol 31 32 7 09                                       14       1S Af ecur cart twtNT Dart CAfincur          [vY hIN 1013 Io00Cair                      Nuvotn 1-1 c 12.181 oj i ol 7121317 I 674: Lol                                   8! 0121716 00      J 0 i Coat in 11J LtJ LIJ                          60          61                                      68     69                                 7b 7       0         S7       68         09 FVENT DESCR!PilON
l l
                                                                                                                                                                            }
l l
O        IDuring the preparations to test the startinn of #1 cmernency diesel neverator (EDC). BO 7 oo                                                                                                                        diesel nenerator was fr=ediatej
l (PLEASE PflNT Att RECulRED INFCRMATl!N) 1 6
@ l water was detected in #7 cylinder. The backup ernernency                                                                                                             60 7 H9 h { ly tested satisf actorily_and the repfi rs cormence) on #1 EDG. The _ engine was re.pnited                                                                           80              l 7 o9                                                                                                                                                                        l
t Cf N51 tVlN1 L CE *.M t TYPE fvPE tiCENGE NUV0t R
@ [by replacing the cylinder head _ and 13 3 d gasket. This is a reportable cecurrenceJ n                                                                               CO 7 tl 9                                                                                                                                                                       l
[@] Iv la I s I el s1_d lo lo I-I ol ol ol ol 01-1010 I I 41 i i t t i l o l I ol 31 NtWI 30 31 32 25 26 7 09 14 1S Af ecur cart [vY hIN 00Cair Nuvotn twtNT Dart 0 i Coat in 11J LtJ LIJ 1013 Io 1-1 c 12.181 oj i ol 7121317 I 6 :
@ laccordance with Technical Specification                                                 _{t.6.2h (2).               (lfSRE S1-76-lo)                                80 p.,vr 7 u9                                                                             ccwn Nt                   councNtsr s,su v       C .ta                                                   s. min               Mar.ur Ac Tu.* n         votAYON CDOf         CCDF                 COVPON' NT CODE h l E l [E_j                   IE IM i Cl I! NI El17                      d43          44 iElIl4l7l 47
Lol 8! 0121716 J CAfincur 68 69 74 7b 00 7
[MJ 48 7 09 10                       11         12 CAUSL DECCRPTION crack in S7 cylinder head whic!}
0 S7 68 09 60 61 FVENT DESCR!PilON IDuring the preparations to test the startinn of #1 cmernency diesel neverator (EDC).
  @ [EMD-G51 Turbo Vee _20, 3810 Bhn diesci onnine surtained a                                                                                                             60 7 H9                                                                                                                                  inc ke t;. Thets w.3terfroml iextendedbetweentwoexhaustvalveseatsandthrounhthewater                                                                                                         60 l      HH                                                                                                                                                                    }
}
it.he Sylindet head unter Jacket u n porriittted to drip int _o the cylinder. (Continued) c-VI1HDD Of f AOut y                                                                        DiSCG.f4v                          O'SCOvE nY Ot ECD'PflON
BO O
                                        % I'OWin                     01stn STAfus EE) stArus
diesel nenerator was fr=ediatej 7 oo
[2J               Lo_LsIol               I       n/^                     l     LaJ         l n/i                                                       00 I
@ l water was detected in #7 cylinder. The backup ernernency 60 tested satisf actorily_and the repf rs cormence) on #1 EDG. The _ engine was re.pnited l 7 H9 i
12 13                               44       45       46 7 u            9                10 senu OF LOCATON OF Pf tf ASE AVOUNT OF AC Ylvit y ttti E.( D       Of rit f 5!
80 h { ly
l 1                                         1 N/A                                        I        I N/A                                                              80 10      11 44       45 7 0           9 PERSONNEL EXPOSURES Novi t n           tiiE       of SCn+1:oN                                                                                                                     I 1
@ [by replacing the cylinder head _ and 1 3 d gasket. This is a reportable cecurrenceJ n l
Lo I o I of           LzJ         Lt4LA-                                                                                                                     60 7 89                     11       1H     13 PIHSONNEL INJURES NuVel H             DESCn P h0N                                                                                                                                 I EE] Io l o l ol                 I         n/A                                                                                                                           80 7 39                       11 12 OfISl!E CONSLOUENCCS                                                                                                                                               I
7 o9 3
    @l 7 09 N/A                                                                                                                                                   60 LOSS On DAMAGE TO rACillTY ivrt         Di SChPf ION                                                                                                                                           l b (Zj               i       N/A                                           _
CO 7 tl 9 (lfSRE S1-76-lo) l
60 7 89               10 PUUUCliY                                                            ()     h#                                                                                       l 3i                   N/A
@ laccordance with Technical Specification _{t.6.2h (2).
80 p.,vr 7 u9 ccwn Nt councNtsr s,su v C.ta s. min Mar.ur Ac Tu.* n votAYON CDOf CCDF COVPON' NT CODE h l E l [E_j IE IM i Cl I! NI El d
iElIl4l7l [MJ 7 09 10 11 12 17 43 44 47 48 CAUSL DECCRPTION crack in S7 cylinder head whic!}
@ [EMD-G51 Turbo Vee _20, 3810 Bhn diesci onnine surtained a 60 inc ke t;. Thets w.3terfroml 7 H9 iextendedbetweentwoexhaustvalveseatsandthrounhthewater 60 it.he Sylindet head unter Jacket u n porriittted to drip int _o the cylinder. (Continued)
}
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I N/A l
ttti E.( D Of rit f 5!
AVOUNT OF AC Ylvit y 80 1
44 45 7 0 9
10 11 PERSONNEL EXPOSURES Novi t n tiiE of SCn+1:oN I
Lo I o I of LzJ Lt4LA-60 1
7 89 11 1H 13 PIHSONNEL INJURES I
NuVel H DESCn P h0N EE] Io l o l ol I
n/A 80 7 39 11 12 OfISl!E CONSLOUENCCS I
@l N/A 60 7 09 LOSS On DAMAGE TO rACillTY l
ivrt Di SChPf ION b (Zj i
N/A 60 7 89 10
() h#
l PUUUCliY 3i N/A
(
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W                                   '
SO W
SO 7 0 11 ADDITIONAL i ACIOHS 3 IThe hackup enernency diesel rencrator was demonstrated _to be operable.                                                                                               eO Therefor 7 89 l
7 0 11 ADDITIONAL i ACIOHS 3 IThe hackup enernency diesel rencrator was demonstrated _to be operable. Therefor eO 7 89 (Continued) l Isafety systems would have functioned if they had been requ_ ired.
1-    Isafety systems would have functioned if they had been requ_ ired. (Continued)                                                                                  eo 7 U9 T.     I,. Ilaticota                                                       PHONE: (804) 357-3184 NAME.                                                                                                                               G9 0 801 961
eo 1-7 U9 (804) 357-3184 T.
I,.
Ilaticota PHONE:
NAME.
G9 0 801 961


    *                    %)
%)
* J 5
J 5
CAUSE DESCRIPTION (CONTINUED)
CAUSE DESCRIPTION (CONTINUED)
Inspection of the engine prior to starting permitted detection of the water and prevented further damage to the engine.
Inspection of the engine prior to starting permitted detection of the water and prevented further damage to the engine.
This is the sixth cylinder head on this engine to be found with a crack, in a tima frame of juct over three months. USRE S1-76-07 listed the other incidents and Indicated the probabic cause as either a cylinder heat imbalance or a heat stresF as a result of an engine overheat condition at some previous time.
This is the sixth cylinder head on this engine to be found with a crack, in a tima frame of juct over three months.
The location of /S head on the engine does not conform to the previous pattern and tends to eliminate a cylinder heat imbalance as the probable cause. It appears that a previous engine overheat condition has heat stressed the cylinder heads to such a point that premature metal f atigue f rom vibration is causing the cracks to appear between the exhaust valve seats. This is an area of high heat and vibration stress.
USRE S1-76-07 listed the other incidents and Indicated the probabic cause as either a cylinder heat imbalance or a heat as a result of an engine overheat condition at some previous time.
To ensure the reliability of this engine, the weekly testing of thic engine as outlined in USRE S1-76-07 will continue. New cylinder heads have been ordered and total replacement should preclude any additional failure. This course of action has been thoroughly discussed with the manufacturer's representative who concurs with this procedure.
stresF The location of /S head on the engine does not conform to the previous pattern and tends to eliminate a cylinder heat imbalance as the probable cause. It appears that a previous engine overheat condition has heat stressed the cylinder heads to such a point that premature metal f atigue f rom vibration is causing the cracks to appear between the exhaust valve seats.
This is an area of high heat and vibration stress.
To ensure the reliability of this engine, the weekly testing of thic engine as outlined in USRE S1-76-07 will continue.
New cylinder heads have been ordered and total replacement should preclude any additional failure. This course of action has been thoroughly discussed with the manufacturer's representative who concurs with this procedure.
ADDITIONAL FACTORS (CO:TTINUED)
ADDITIONAL FACTORS (CO:TTINUED)
Accordingly, no hazard to the safety or health of the generai public existed.
Accordingly, no hazard to the safety or health of the generai public existed.
4
4


6 '
a 6
a              .
VIMOINI A ELI:CTHIC AND l'OWHH COMI*ANh p
VIMOINI A ELI:CTHIC AND l'OWHH COMI*ANh               p Hica:Moxn.V HO M A nUM61 1
Hica:Moxn.V HO M A nUM61 1
August 4, 1976                           11 . 5 ,               +     s
August 4, 1976 11. 5,
                                                                                              '. 1 < ;;
+
                                                                                                                'll s3 Mr. Normn C. !!oscley, Director                           Scrial No.173 Office of Inspection and Enforcement                     P0&M/ALil:jlf U. S. Nuclear Regulatory Comission Region II - Suite 818                                     Docket No. 50-280 230 Peacht.rce Street, Northwest                         License No. DPR-32 Atlanta, Georgia     30303
s
'. 1 < ;;
'll s3 Mr. Normn C. !!oscley, Director Scrial No.173 Office of Inspection and Enforcement P0&M/ALil:jlf U. S. Nuclear Regulatory Comission Region II - Suite 818 Docket No.
50-280 230 Peacht.rce Street, Northwest License No. DPR-32 Atlanta, Georgia 30303


==Dear Mr. Moscicy:==
==Dear Mr. Moscicy:==
 
i Pursuant to Surry Power Station Technical Specification '6.6.2, the Virginia Electric and Power Company hereby submits a copy of Licensco Event Report No. USRE-S1-76-10.
i                     Pursuant to Surry Power Station Technical Specification '6.6.2, the Virginia Electric and Power Company hereby submits a copy of Licensco Event Report No. USRE-S1-76-10.
1 The substance of this report has been reviewed by the Station Nuclear Safety and Operating Comittee and will be placed on the agenda' for the next meeting of the Syctem Nuclear Rafety and operating Comittee.
1 The substance of this report has been reviewed by the Station Nuclear Safety and Operating Comittee and will be placed on the agenda' for the next meeting of the Syctem Nuclear Rafety and operating Comittee.
Very truly yours, 26.D7.ssaa:;,y l                                                 C. M. Stallings Vice President-Power Supply and Production Operations Enclosure                                                               -
Very truly yours, 26.D7.ssaa:;,y l
I          cc:  tir. Robert W. Reid, Chief (40 copics)
C. M. Stallings Vice President-Power Supply and Production Operations Enclosure I
tir. Robert W. Reid, Chief (40 copics) cc:
Operating Reactors Branch 4 i
Operating Reactors Branch 4 i
k                                                                                                       g.m, L
k g.m, L
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}}
}}


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Latest revision as of 01:30, 14 December 2024

Updated LER 50-237/01L:on 760406,unacceptable Ultrasonic Indication Found on Isolation Condenser safe-end.Caused by Cracks in safe-ends.Cracked safe-end Removed & Sent to Bmcl for Metallographic Analysis
ML20086S457
Person / Time
Site: Dresden, Surry, 05000000
Issue date: 07/13/1976
From: Stephenson B
COMMONWEALTH EDISON CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML20086S443 List:
References
BBS-#76-531, LER-50-237-01L, LER-50-237-1L, NUDOCS 8403020366
Download: ML20086S457 (3)


LER-1950-237, Updated LER 50-237/01L:on 760406,unacceptable Ultrasonic Indication Found on Isolation Condenser safe-end.Caused by Cracks in safe-ends.Cracked safe-end Removed & Sent to Bmcl for Metallographic Analysis
Event date:
Report date:
0001950237R00 - NRC Website

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r The safe-end (which was SA-182 F316 stainicss steel) was replaced with one forged from SA-182 F316L stainless ste'e1. -(50-237/1976-21) l CAUSE DESCRIPTION (Continued) r-and four axially-oriented cracks at the 1:00, 4:00, 4:45, and 5:00 positions. The depth of the circumferential crack was found to be 0.261 inches, while the axial cracks ranged in depth from 0.255 to 0.500 inches.

The circumferential crack was located approximately 3/8 inch from the safe-end-to-pipe weld and was 0.60 inches long at the I.D. surface.

The axial cracks ranged from 0.23 to 0.43 inches in length and extended to within 1/16 inch of the safe-end-to-pipe weld.

The metallographic exanination revealed similar. features in both the axial and circumferential cracks:

initiation at the I. D. surface, and intergranular propagation in a heavily-sensitized microstructure. Microprobe analyses of fracture surfaces and cross sections of the cracks indicated no chlorides, fluorides, sulfides, or other possible corrosives.

Moderate residual l

stresses from welding and possibly from inner surface grinding (up to 5 mils of I

cold working were observed) may also have been contributing factors.

The mechanism of cracking is the'same as that experienced in'the HPCI safe-end, the 10-inch core spray piping, and the 4-inch recirculation bypass piping.

The cracked safe-end was manufactured from'SA-182 F316 stain 1 css steel and was unclad.

It was approximately 5 inches long, with a 14-inch 0.D. at the piping end (0.56-inch wall thickness) end a 16-inch 0.D. at the nozzle end (1.08-inch wall thickness). The safe-end was furnace-sensitized during the post-weld stress relief treatment of the pressure vessel.

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l Mr. James.C. Keppler, Regional Director 9,l s '

j Directorate of Regulatory Operations - Region III U. S. Nuc1 cur Kegulatory Commission g,,

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799 Roosevcit Road s

Glen Ellyn, Illinois 60137

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Enclosed pleaset find an update report to Reportable Occurrence report number 50-237/1976-21.

This report is being submitted to your office in accordance with the Srcsden Nuc1 car Power Station Technical Specifications, Section 6.6.B.

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. 'S t ep)ienson Station Superintendent Dresden Nuclear Power Station BBS:jo Enclosure cc: Director of Inspection & Enforcement Director of Management Information & Program Control File /NRC i

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LICENSEE EVENT REPOPN V

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l (PLEASE PflNT Att RECulRED INFCRMATl!N) 1 6

t Cf N51 tVlN1 L CE *.M t TYPE fvPE tiCENGE NUV0t R

[@] Iv la I s I el s1_d lo lo I-I ol ol ol ol 01-1010 I I 41 i i t t i l o l I ol 31 NtWI 30 31 32 25 26 7 09 14 1S Af ecur cart [vY hIN 00Cair Nuvotn twtNT Dart 0 i Coat in 11J LtJ LIJ 1013 Io 1-1 c 12.181 oj i ol 7121317 I 6 :

Lol 8! 0121716 J CAfincur 68 69 74 7b 00 7

0 S7 68 09 60 61 FVENT DESCR!PilON IDuring the preparations to test the startinn of #1 cmernency diesel neverator (EDC).

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diesel nenerator was fr=ediatej 7 oo

@ l water was detected in #7 cylinder. The backup ernernency 60 tested satisf actorily_and the repf rs cormence) on #1 EDG. The _ engine was re.pnited l 7 H9 i

80 h { ly

@ [by replacing the cylinder head _ and 1 3 d gasket. This is a reportable cecurrenceJ n l

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CO 7 tl 9 (lfSRE S1-76-lo) l

@ laccordance with Technical Specification _{t.6.2h (2).

80 p.,vr 7 u9 ccwn Nt councNtsr s,su v C.ta s. min Mar.ur Ac Tu.* n votAYON CDOf CCDF COVPON' NT CODE h l E l [E_j IE IM i Cl I! NI El d

iElIl4l7l [MJ 7 09 10 11 12 17 43 44 47 48 CAUSL DECCRPTION crack in S7 cylinder head whic!}

@ [EMD-G51 Turbo Vee _20, 3810 Bhn diesci onnine surtained a 60 inc ke t;. Thets w.3terfroml 7 H9 iextendedbetweentwoexhaustvalveseatsandthrounhthewater 60 it.he Sylindet head unter Jacket u n porriittted to drip int _o the cylinder. (Continued)

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10 12 13 44 45 46 senu OF LOCATON OF Pf tf ASE 1 N/A I

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AVOUNT OF AC Ylvit y 80 1

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10 11 PERSONNEL EXPOSURES Novi t n tiiE of SCn+1:oN I

Lo I o I of LzJ Lt4LA-60 1

7 89 11 1H 13 PIHSONNEL INJURES I

NuVel H DESCn P h0N EE] Io l o l ol I

n/A 80 7 39 11 12 OfISl!E CONSLOUENCCS I

@l N/A 60 7 09 LOSS On DAMAGE TO rACillTY l

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N/A 60 7 89 10

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7 0 11 ADDITIONAL i ACIOHS 3 IThe hackup enernency diesel rencrator was demonstrated _to be operable. Therefor eO 7 89 (Continued) l Isafety systems would have functioned if they had been requ_ ired.

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CAUSE DESCRIPTION (CONTINUED)

Inspection of the engine prior to starting permitted detection of the water and prevented further damage to the engine.

This is the sixth cylinder head on this engine to be found with a crack, in a tima frame of juct over three months.

USRE S1-76-07 listed the other incidents and Indicated the probabic cause as either a cylinder heat imbalance or a heat as a result of an engine overheat condition at some previous time.

stresF The location of /S head on the engine does not conform to the previous pattern and tends to eliminate a cylinder heat imbalance as the probable cause. It appears that a previous engine overheat condition has heat stressed the cylinder heads to such a point that premature metal f atigue f rom vibration is causing the cracks to appear between the exhaust valve seats.

This is an area of high heat and vibration stress.

To ensure the reliability of this engine, the weekly testing of thic engine as outlined in USRE S1-76-07 will continue.

New cylinder heads have been ordered and total replacement should preclude any additional failure. This course of action has been thoroughly discussed with the manufacturer's representative who concurs with this procedure.

ADDITIONAL FACTORS (CO:TTINUED)

Accordingly, no hazard to the safety or health of the generai public existed.

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VIMOINI A ELI:CTHIC AND l'OWHH COMI*ANh p

Hica:Moxn.V HO M A nUM61 1

August 4, 1976 11. 5,

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'll s3 Mr. Normn C. !!oscley, Director Scrial No.173 Office of Inspection and Enforcement P0&M/ALil:jlf U. S. Nuclear Regulatory Comission Region II - Suite 818 Docket No.

50-280 230 Peacht.rce Street, Northwest License No. DPR-32 Atlanta, Georgia 30303

Dear Mr. Moscicy:

i Pursuant to Surry Power Station Technical Specification '6.6.2, the Virginia Electric and Power Company hereby submits a copy of Licensco Event Report No. USRE-S1-76-10.

1 The substance of this report has been reviewed by the Station Nuclear Safety and Operating Comittee and will be placed on the agenda' for the next meeting of the Syctem Nuclear Rafety and operating Comittee.

Very truly yours, 26.D7.ssaa:;,y l

C. M. Stallings Vice President-Power Supply and Production Operations Enclosure I

tir. Robert W. Reid, Chief (40 copics) cc:

Operating Reactors Branch 4 i

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