05000281/LER-1979-008-03, During Surveillance Check,Found Deterioration of Piping on Low Portion of Recirculation Spray Subsystems.Caused by Chloride Stress Corrosion.Piping Replaced W/Nonsensitized Piping

During Surveillance Check,Found Deterioration of Piping on Low Portion of Recirculation Spray Subsystems.Caused by Chloride Stress Corrosion.Piping Replaced W/Nonsensitized Piping

ML18139A692
Person / Time
Site:	Surry
Issue date:	08/25/1980
From:	Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139A691	List: 05000281/LER-1979-008, Forwards Updated LER 79-008/03X-1 05000281/LER-1979-008-03, During Surveillance Check,Found Deterioration of Piping on Low Portion of Recirculation Spray Subsystems.Caused by Chloride Stress Corrosion.Piping Replaced W/Nonsensitized Piping
References
LER-79-008-03X, LER-79-8-3X, NUDOCS 8009020090
Download: ML18139A692 (3)

LER-1979-008, During Surveillance Check,Found Deterioration of Piping on Low Portion of Recirculation Spray Subsystems.Caused by Chloride Stress Corrosion.Piping Replaced W/Nonsensitized Piping

Event date:
Report date:
2811979008R03 - NRC Website

text

SUPPLEMENTAL REPORT CONTRC,L BLOCK:

~

~--'---'--.....__..__!_ (0 (PLEASE PRINT OR TYPE AWEOUIRED INFORP.',ATIONi A I s j P Is I 2 1010 o/ -Jo I o I o j o I o I - I oj oJG)/ 4 I 1 I 1 / 1 J 1 101

/ JG LICENSEE CODE 1,

1!:>

LICENSE NUMBER 2:,

>G LICENSE "TYPE JO 57 CAT 58 N'1

~

~~~ LJ:J© I o I s I o I o I o I 21 s 11 101 o J 2 I o I 9 I 1 I 9 fG) I o J s 12 / s J s 10 J 0 60 61 DOCKET NUMBER 68 69 EVENT DATE 7~

75 REPORT DATE 60 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES@

!During refueling and steam generator replacement of Surry Unit No. 2 outage, routine inspection of recirculation spray piping indicated deterioration on the low portion of two of the four recirculation spray subsystems.

This is less conservative with respect 5

L to T.S. 3.4.A.2 and is reportable under T.S.6.6.2.b.(4).

Redundant systems were operable 16 and were capable of providing cooling and depressurizeration as required.

Therefore, 7

the health and safety of the public were not affected.

8 9

8 9 6

SYSTEM CODE Isl HI@

9 10 Q

LERIRO CVENT YEAR

~

REPORT I 8 j O j NUMBER

Zl

Z:>

ACTION FUTURE TAKEN ACTION EFFECT ON PLANT

CAUSE

CAUSE COMP.

VALVE CODE SUB CODE COMPONENT CODE SUBCODE SUBCODE

~@ t2J@

PIIIPIEIXIXI@ w@ u.J@

1, l.::::J

Z3 SHUTDOWN 1:>

13 SEQUENTIAL REPORT NO.

I o Io Is I

?4 26 METHOD HOURS 18 OCCURRENCE CODE I o I 3 I 27

ZS

zg 19

zo REPORT TYPE IX I L=1 30 31 r:;::;,.

ATT AC HM ENT NPRD-4 FORM SUB.

PRIME COMP.

SUPPLIER REVISION NO. w 3:>

COMPONENT MANUFACTURER 80 W@LEJ@ ~@ ~ Io 1010 33 34 3!>

36 J 7

~ SUBMITTED I OJ

~@

40 41

~§ ~@)

L----LI__._I ___.____.J@

CAUSE DESCRIPTION AND CORRECTIVE ACTIONS @

43

-'17 0 J A sample of the piping was analyzed by a consulting laboratory.

The cause of the degradation has been determined to be chloride stress corrosion*. The degraded sensitized 2

piping has been replaced with non-sensitized piping to resist chloride stress corrosion.

.._I----------------------------------------'

8 9

FACILITY Q

STATUS

% POWER OTHER STATUS ~

L!J@ IO IO 10 l@I NA I

8 9

10 12

'-13---------~

ACTIVITY CONTENT 4'I RELEASED OF RELEASE AMOUNT OF ACTIVITY@

J w@) W@~I __

N_A_* -------J 8

9 10 PERSONNEL EXPOSURES NUMBER r:;:;., TYPE DESCRIPTION@

I o Io I o/'221~@

B 9 11 17 1*'-::3:----------------------------------------~

PERSONNEL INJURIES 80 NUMBER DESCRIPTIONG I or o I o J@

\\:Y 8

9 '

11

-:1:>;----------------------....:_ _____________________

8~0 LOSS OF OR DAMAGE TO FACILITY c:;.,

TYPE

DESCRIPTION

6

~@

80 METHOD OF DISCOVERY DISCOVERY DESCRIPTION 32

~@.... I ___

R_o_u_t_1_*n_e_S_u_r_v_e_i_* 1_1_a_n_c_e _________ _

45 46 80 NA LOCATION OF RELEASE@

45 80 NA NA NA 8

9 10 so PUBLICITY

,;';\\

ISSUE Dr:;-::\\ DESCRIPTION~

NRC USE ONLY c

~6,:-;::l 0~8:ioTior.9;:;;-_no-;::;2;-;o;;:-o;:-9in=o:-::~--------NA _________

____J68 619 I I I I I I I I I I 1 'EJ ~

NAME OF PREPARER J.L. Wilson (804) 3 57-3184 0

C.

ATTACHMENT NO.l SUPPLEl-lHiTAL REPORT

'"SURRY POWER STATION, UNI'aO. 2 DOCKET NO.

50-281 111111' e

REPORT NO.

79-008/03X.-l EVENT DATE:

02-09-79 TITLE OF RE.PORT:

RECIRCULATION SPRAY SYSTEM PIPE DETERIORATIW

1.

Description of Event

During the refueling and steam generator replacement outage of SuFry Unit No. 2, routine surveillance indicated deterioration of piping on the low (horizontal) portion of two of the four recirculation spray subsystems.

A visual inspection of the Surry Unit No. 1 recirculation spray systems piping was performed with satisfactory findings.-

The event constitutes a condition less conservative with respect to T.S.3.4.A.2 and is reportable in accordance with T.S. 6.6.2.b(4).

2.

Probable Cons1eguences/Status of Redundant Systems:

The recirculation spray systems are redundant systems.

They provide the necessary cooling and depressurization of containment during a loss of coolant event.

A complete description of the systems are contained in section 6.3.1 of the Final Safety Analysis Report for the Surry Power Station, Unit No. 1 and 2.

Because of the redundancy of the systems, and the nature of the degradation experienced, the systems would have performed their intended function.

Therefore the health and safety of the general public were not affected.

3.

Cause of Event

The cause of degradation has been determined to be chloride stress corrosion '

by the, con~ml ting laboratory.

4.

Inrrnediate Carree tive Action:

A sample of the degraded piping was sent to a consulting laboratory for evaluation.

Action was initiated to replace the degraded piping.

5.

Scheduled Corrective Action:

Degraded piping has been replaced.

6.

Action Taken to Prevent Recurrence:

The degraded sensitized stainless steel piping has been replaced by nonsensitized stainless steel piping which resists chloride stress corrosion.

The installed instrumentation gives an indication in the control room if water enters the piping under discussion.

Routine surveillance program to inspect the low point piping by ultrasonic testing during refueling is in effect.

Any piping that does not pass the inspection will be subjected to further evaluation and

I"

• ATTACPJIENT 2 SURRY POWER STATION

• NO 2 DOCKET NO:

50-281 REPORT NO:

79-008/C3X-l SUPPLEMENTAL REPORT

• I EVENT DATE:

02-09-79

6. replacement if necessary.

7.

Generic Implications:

None