05000244/LER-1976-024, Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking

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Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking
ML20084B843
Person / Time
Site: Ginna Constellation icon.png
Issue date: 06/08/1977
From: White L
ROCHESTER GAS & ELECTRIC CORP.
To: James O'Reilly
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML20084B847 List:
References
LER-76-024-01O, LER-76-24-1O, NUDOCS 8304070133
Download: ML20084B843 (3)


LER-2076-024, Updated LER 76-024/01O-1:on 761008,accumulation of Borated Water Found Near Valve in Safety Injection Sys Piping Between Boric Acid Tanks & Safety Injection Pumps.Caused by Chloride Stress Corrosion Cracking
Event date:
Report date:
2442076024R00 - NRC Website

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iUi'NSEIS" $NT"iiNP CONTROL BLOCK:I l l I I I I. [ PLEA .E P. TINT ALL CEZullE']INFCRM AT1o?

1 6 UCENSE NuveE A PE YFE

, N ME oi l Nl Y l Rl E lGl 1l l Ol 0 l-l 0 l0 l 0 l 0 l 0 l-l 0 l 0 l l 4 l 1 l 1l 1l1l l0l1l 32 7 89 . 14 15 25 26 30 31

" REPORT CATE CATEGORY T7PY ONHCE

  • OoCrET NuvetA ' EvtNT DATE E] con t i57 I I lo_l Lt_.1 101 s 101-1012 I 4 I 4 I 1110 f 0181716 I I Ol 6101817 ! e 7 8 58 59 60 61 = 68 69 74 75 E EVENT OEsCA:PTON -

f5[ij l During normal operations an auxiliar/ operator found an accumulation of borated water e

7 89 03 I near a valve in the Safety Injection System piping between the Boric Acid Tanks and E

7 09 Q l Safety Injection Pumps. Further investigation revealed a leak in a section of 8" E 7 53 9

@ l Schedule 10 stainless steel pipe between valves 826A and 826B. ~ The unit was taken E 7 89 oo l to cold shutdown as recommended by PORC. Leaks were (cont'd. on attached sheet) 6 7 89 pqug t CCct COMPONENT CODE

' C SER vcLATON E ISIFI [FJ 7 89 10 11 l el t le i Eix I xl 12 17 LN_j 43 44 lKI0l5l5l 47

[N_j 48 CAUSE OEsCAiPTION

] l As a result of metallurgical analysis and metallographic examinations, chloride stress b-7U9

{] l corrosion cracking is believed to be the cause of the leaks. As the investigation con-7 89 E

] l tinued, further information was submitted in a supplemental (cont'd. on attached sheet i

'stANs'  % POWE A OTHER STATUS OSCOVERY OrSCOVEAY DESCA.PT:CN d [ E_j l1l0 l 0] l NA l [b_j l By operator 7 8 9 10 12 13 44 45 46 E.

A LE OF E AMOUNT OF ACTMTV LOCAT:ON CF AELEISE 1? l2l [e jASE l NA l 44 l

45 NA E.

7 8 9 10 11 PERSONNEL EXPOSURES NUWEA TYPE DESCALPTON M l0l0l0l [c] l NA 12 13 6, 7 89 11 PEAsONNEL lNJUA:Es

  • NuvetA CESCA.PTON t .1 l0 l 0 l 0] l NA 7 89 11 12 c<

OFFsfTE CONsEOUENCEs is l NA 7 89 c.

Loss OR OAMAGE TO FAC!UTY Yvrf O(SCAIPTCN i yl See Event Description S;

7 89 10 PuBLCITY 37 l Press release on October 8,1976 7 89 El ADOITICNAL FACTOAs 8304070133 770608 PDR ADOCK 05000244 1e l NA g PDR 7 89 BC 19 l .

' Licensee Event Repo.s o '

o

. . Reportqble Occurrence 50-244/76-24 Event Description (cont'd.)

found in two sections of pipe, and 11guld penetrant and ultrasonic examina-tion of 75 welds and the piping associat4d with those welds 16 the boric acid tank outlet piping rev,ealed five other sections of pipe of fittings with indications. All seven of these components of the piping system containing leaks or indications were replaced. (Reportable Occurrence 76-24).

Cause Description (cont'd.) ,

report, dated February 10, 1977, which supported this conclusion, and pro-vided the corrective action performed and being considered. The supplemental report also described our December 21, 1976 response to IE Circular 76-06 which stated that during the 1977 refueling and maintenance out, age additional testing and examination would be performed on piping and selected welds in the containment spray and safety injection systems.

During the 1977 refueling and mainten.Ince outage the boric acid storage tank outlet piping was modified to eliminate all inaccessible portions. The exam-inations and testing consisted of the following:

1. Nine welds in the Boric Acid Piping were ultrasonically examined. As this included the remaining two welds which were previously inaccessible, all the welds of the heat traced boric acid supply piping to the safety injection pumps have been ultrasonically examined.
2. Five welds in the Containment Spray Pump Discharge piping inside con-tainment were ultrasonically examined.
3. The Boric Acid Piping to the Safety Injection Pumps and the containment spray pump suction piping was hydrostatically tested to 280 psig (mini-
mum). .
4. The containment spray pumps discharge piping was.hydrostatically tested to 380 psig (minimum).
5. The Safety Injection Pumps Discharge Piping was hydrostatically tested to 1880 psig (minimum).
6. The Spray Additive Tank was pressure tested, using a nitrogen medium, to 375 psig (minimum). ,

All welds and piping inspected and tested as listed above were found to be acceptable. The welds and piping in the Safety Injection and Containment Spray Systems will continue to be examined in accordance with the require-ments of the Ginna Station Inservice Inspection Program to assure the continued integrity of these systems.

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ROCHESTER GA$ AND ELECTRIC CORPORATION e 89 EAST AVENUE, ROCHESTER, N.Y.14649 ft.cpac ,

LEON O WHITE. JR. e aan. con t.* 5.:6 2700 vica cas e.oene I ro' /

June 8,1977 [- ~

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Mr. James P. O'Reilly, Director U. S. Nuclear Regulatory Commission '2 "*5'To30[s T*M

' x Office of Inspection and Enforcement N Region I 4

631 Park Avenue King of Prussia, Pennsylvania 19406 .

Subject:

Supplemental repcrt on Reportable Occurrence 76-24, leaks in schedule 10 boric acid piping R. E. Ginna Nuclecc Power Plant, Unit No.1 Docket No. 50-244

Dear Mr. O'Reilly:

In a supplemental report dated February'10,1977 on the subject Reportable Occurrence it was stated that during the 1977 refueling and maintenance outage additional testing and examinations would be performed on piping and selected welds in the safety injection and containment spray systems . The attached update report LER 76-24/10 provides the results of this investigation.

Two additional copies of this letter and the attachment are enclosed to conform to the original sub*nittal of LER 76-24/1T.

Very truly yours,

p. .

L. D. White , Jr.

cc: Dr. Ernst Volgenau (40)

Mr. William G. Mcdonald (3) -

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