ML19208C803

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Responds to IE Circular 76-06.Submits Schedule & Results of Tests on Piping Containing Boric Acid Solution
ML19208C803
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 01/03/1977
From: Burstein S
WISCONSIN ELECTRIC POWER CO.
To: James Keppler
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19208C798 List:
References
NUDOCS 7909270523
Download: ML19208C803 (10)
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Text

__r~d$f'E I WISCONSIN Elecinc me cowna

.231viEST MIClilGArd.uitwAUK[E,Wl;CONSIN 53201 January 3, 1977 m Mr. James G.

Keppler, Regional Director Office of Inspection and Enforcement, Region III D op 0 U.S. NUCLCAR REGULATORY COMMISSION es eg 799 Roosevelt Road Glen Ellyn, Illinois 60137 cs 7--_, ev JU_Jj_Ju";,

Dear Mr. Kcppler:

DOCKETS 50-266 AND 50-301 SCl!EDULE AND RESULTS OF SPECIAL TESTS ON PlPING CONTAlNING BCRIC ACID SOLUTION POINT BEACH NUCLEAR PLAUT (IE Circular 76-06 dated November 23, 1976, enclosed with your letter of November 26, 1976, listed three recent occurrences of through-wall cracking found in stainless steel piping containing boric acid solution.

The circular requested that we submit a program and schedule for ultrasonic and hydrostatic testing of similar piping at Point Beach Nuclear Plant, and that a summary report of the results of those tests be submitted.

This letter is in response to those requests.

The program and schedule for the tests are included in this letter.

A summary report showing welds tested, an isometric drawing of the boric acid piping, the calibration standard used, and the results of the testing is attached to this letter.

..In our review of the circumstances involved in the three instances of cracking mentioned in IE Circular 76-06, we note that the physical arrangements and methods of operation for the boric acid systems of concern at Point Beach Nuclear Plant do not correspond to any of the three.

In the first instance, the circular stated that chlorides and sulfides were possibly introduced during testing of sodium thiosulfate

' discharge valves.

Point Beach does not use sodium thiosulfate.

In the second :".tuation, it was stated in the circular that chlorides and potential oxygen were assumed present since original construction.

No evidence of chloride contamination has been found at Point Deach.

Possible air entrapment in the lines at Point Beach is minimized because the horizontal piping runs are relatively short, and the lines are self-venting through the boric acid tanks.

After the valves have been cycled 1042 212 7m27o d -

Mr. James G. Ecppler January 3, 1977 a few times, any air in the lines is vented.

In the third case, the circular stated that the chlorides were introduced due to in-lcakage of contaminated water through a faulty recirculation spray heat exchanger.

At Point Beach, recirculation spray is cooled through the residual heat exchangers with component cooling water on the other side of the tubes, not service water.

Our program for assuring the integrity of the safety class lines containing generally non-flowing boric acid solution Jeonsists of the following:

1.Inspecting a representative sample of piping welds using manual ultrasonic techniques to establish final integrity.

2.Verifying continued integrity by performing periodic hydrostatic pressure tests in conformance with Section XI of the ASME Boiler and Pressure Vessel Codc.

3.Verifying that no chlorides enter these pipes by periodically sampling the water sources that can enter-the boric acid tanks.

A manual ultrasonic testing of selected welds was performed during the Point Beach Nuclear Plant Unit 1 refueling outtge in November 1976, shortly after plant personnel became aware of the experience at the Ginna Nuclear facility.

This testing was performed before Circular 76-06 was issued by the NRC, but was conducted with the knowledge of the Region III NRC

-specialist on in-service inspection.

The results of these inspections are covered in the attached report.

The hydrostatic pressure tests will be perfor.1ed at the frequency required by Section XI of the 1974 edition of the ASME Boiler and Pressure Vessel Code when it becomes effedtive at the plant.Performance of additional hydrostatic pressure tests was not considered necessary because of the diff erences in circumstances and design between the Point Beach Nuclear Dlant and the plants referenced in the NRC circular and because of the fact that no problems of this nature have previously occurred at Point Beach.

In addition, as you will note., the ultrasonic testing of selected representative welds confirmed their integrity.

We believe the information supplied in this letter and the attached summary report are responsive to the concerns expressed in IE Circular 76-06.

Please advise us if you require.further information.

0=D D Very truly yours, oo M3 I~I.o__Jk" aExec tive Vice President

  • Sol Burstein

.,.Copy to NRC Office of Inspection and Enforcement 042 217Washington, D. C.

20555 ULTRASONIC TESTING OF CLASS II SAFETY INJECTION PIPING AT POINT BEACH NtlCLEAR PLANT t! NIT 1 During November 1976 selected welds in the Class II and Class III portions of the safety injection piping at Point Beach Nuclear Plant Unit I were examined using ultrasonic testino techniques. The examinations were performed af ter plant personnel were infonned of cracks in similar piping fnund at the Ginna Nuclear Plant. These tests were conducted with knowledge of the Region III NRC specialist on inservice inspection.

The safety injection piping inspected was eight-inch nominal diameter schedule 10 type 304 stainless steel . This piping is heat traced, insulated and contains boric acid solution at concentrations of up to 20,000 The examinations were performed by Southwest Research parts per million.

Institute personnel concurrently with the regular inservice examination activities.

Fifteen representative welds were selected for examination on the basis of the areas where cracking occured at Ginna.

Some of the nondestructive

.test personnel present during these examinations were also present at Ginna during their examinations. The welds and between two and three inches of base metal on each side of the welds were examined tsing manual ultrasonic techniques.

No cracking or other defects were found by this testing in either the welds or adjacent base metal. The examinations revealed two indications of weld root geometry and no defect indications. The welds examined and the results are shown in Appendix 1 Nondestructive Examinations Summary Table.

An isometric drawing of the safety injection line is included as Appendix 2.

The specific welds which were inspected have been circled.

A drawing of the ultrasonic calibration standard used for these tests is included as Appendix 3.

The examinations were conducted in accordance with Southwest Research Institute procedure SwRi-NDT-800-36 Revision 9, " Manual Ultrasonic Examination of Thin llall Piping Welds".

[D D wa y-r e LX L" 2-.1042 214

..APPENDIX 1 NONDESTRUCTIVE EXAMINATIONS SUtWARY TABLE.6 J t.o]'~o r w JG.5)L.E 2 104221f D.8M>_b POINT DEACll NUCLEAR PLANT,IJNIT 1

/.1 1976 SPECIAL INSERVICE EIAMINATION OF 1.3 ({ y:L)M3 Cl. ASS 2 Lott PRESS 11RC SAFETY INSPECTION PIPING N*b-, NONDESTimCTIVE EXAMINATIONS S14 NARY TABLE g 9 Piping Q*m ASYE ASVE S*RI WELO INDICA TIONS xA IN HON EXAM SEC MI SEC x, ,ROCE DUR t E X AM. SUM RE M AR KS r T E M NO CA TGY, NO/REV.SHE E T NO.

NO RECORDABLE INSIGNIFICAN T GE OME TRf C OTHER

^'C"" SIS-8-BA-151R

,----SIS B A- 151 R- 4 UT 800-36/9 300046 0*L,45*, No examination downstream due to Elbow-to Valve 45'T the valve configuration.

Cal. Std. 8-S5-40 .140-71.

SlS-8-BA-151R-5 (IT 300-36/9 300136 0*L,45*, No examination upstrese due to the Valve-to-Tee 45*T valve configuration.

Cal. Std. 3-55-10 .140-71.

SIS-8-BA-151R-6 (IT 800-36/9 300137 0* L,4 5* , No examination downstream 45'T due to the vatwe configuration.

Pipe-to-Valve Cat. Std. 8-SS-10 .140-71.

  • ----SIS-8-BA-15tR-7 LIT R00-36/9 300138 0* L ,4 5 * , No examination upstream due to the Valve-to-Tee 45*T valve configuration.

Cal. Std. 8 55-10 .140-71.

SIS-8-BA-151R-8 UT 800-?$/9 300139 0* L,45*Cal. Std. 8-55-10 .140-71.

Tee-to-Elbow 45'T----SIS B A- 151R- 12 IIT 300-36/9 300140 0*L,45*, No examination downstream due to Tee to Valve 45*T the valve configuration.

Cal. Std. 8-SS-10 .140-71.

S I S B A- 151R- 13 UT 890-36/9 300141 0* L,4 5* , No examination upstream due to the Valve-to-Pipe 45*T valve configuration.

Cal. Std. 8-55-10 .140-71.

SIS-8-BA-151R-14 UT A00-36/9 300142 0*L,45*, Cal. Std. 8-55-10 .140-71.

Pipe-to-Tee 45*T----SIS-8-BA-151R-15 IIT 500-36/9 300143 0*L,45'45'T one 45*T indication due to the weld root geomet ry of the adjacent longi-Tee-to-Valve tudinal wcld.

See Indication Resolu-tion Record No. 31026R. Cal. Std.

8-55 10 .140 71.

S I S B A- 151R- 16 tTT A00-36/9 300144 0* L,4 5'T 45*One 45' indication due to the weld rmat geomet ry of the adjacent longi-Valve-to-Pipe todinal weld.

Sec Indication Resolu-tion Record No. 310269.

Cal. Std.8-S5-10 .110-71.

6 (.

..*-APPENDIX 2 ISOMETRIC DRAWING SAFETY INJECTION LINE S15-8-BA-151R

....0.Dl ~s og y 7-a Jb aJ_1 1042 217.

ItlN1 BLACll NUCLLAR l' TANT, tNIT I 1976 SI't.CI Al. INSf'RVlw L X AMINSTION (T

  • CIAss 2 IDW PRt.sSimfi SAFITV INSI'l(TlfW Pil'IP

'aoNtiLSTittx.TIVE ExetlNATIONS StBf tARY TABI E ]

/Piping (Cont'd)

  • ASME ASME SwRt MtO tND?CAf tO*45 8 SE C x1 SE C.11 t'ROCE DURE E X AM Stw ARE A IDENTIFICA TION METHOO MEMARKS MNO OTGr NO /RE Y.SHE E T NO NO PECORDA8tt

'NStGNt F ICANT GEOMETRIC OTHER gg i I SIS-8-BA-151R (Cont'd)

SIS-8.BA-151R-19 LTT 800-36/9 300145 0*L,4 5'No examination downstream due to the ribow-to. valve 45*T valve configuration.

Cal. Std. 8-SS- 10 .140-71.

SIS-8-BA-151R-20 (Tr 800-36/9 300047 0*L,45*, No examination upstream due to the Valve-to-Pipe 45*T valve configuration.

Cal. Std. 8-55-10 .140-71.

SIS-8-BA-151R-20A UT 800-36/9 300043 0*L,45'Cal. Std. 8-SS-10 .140-71.

Pipe-to-Elbow 45'T----Sis-8-BA-151R-21 UT 300-36/9 300044 0

  • L ,4 5* , Cal . St d. 8- SS- 10 .14 0-71.

Elbow-to-Pipe 45*T----SIS-8-BA-15tR-22 tJT 800-36/9 300045 0* L,4 5*Cal. Std. 8-SS-10 .140-71.

Pipe-to-Tee 4 5*T (R>=$,M.-IsPJ C=ED , ,g W_.,g ED&_4 N N-lDIO

  • .I B.,, TANK p (;g M.[2 W EB R 3 , ,,~@6'd b/N827 B , 7 827A C@-,9 ,>-,10 , LOA O/ N826A'q p 4$$@i C , 20 A g/20@0 Indicates those welds inspected

., .7 ,, c IU IOD,. - *,, , II O.b.8" LOW PRESSURE N#e g SAFETY INJECTION PIPING .

N g_5'm-Y-A 2367 I20 1-..s_APPENDIX 3 CALIBkATI0t1STATIDARD

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