ML18037A292

Interim Deficiency Rept Re Failure of Matl in Spent Fuel Pool Heat Exchangers to Meet Impact Testing Spec Requirements.Caused by Omission of Test Specimen Parameter from Impact Test Data.Safety Function May Be Jeopardized

ML18037A292
Person / Time
Site:	Nine Mile Point
Issue date:	10/02/1980
From:	Rhode G NIAGARA MOHAWK POWER CORP.
To:	Robert Carlson NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8010100249
Download: ML18037A292 (8)

Text

REGULATORY. INFORMATION DISTRIBUTIO SYSTEM (RIDS)

I ACCESSION NBR:8010100249 DOC ~ DATE: 80/10/02 NOTARIZED: NO DOCKET FACIL:50 BYNAME410 Nine Mile Point Nuclear Stationi Unit 2i Niagara Moha 05000410 AUTH RHODEiG ~ K 'iagara RECIP ~ NAME AUTHOR AFFZL'IATION Mohawk Power Corp.

RECIPIENT AFFILIATION CARLSONiR, T ~ Region ii Philadelphiai Reactor Construction 1

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SUBJECT:

Interim deficiency rept re failure of matl in spent fuel pool heat exchangers to meet impact testing spec requirements Caused by omission of test specimen. parameter

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from impact test data Safety function may be Jeopardized.

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DISTRIBUTION CODE': SOIDS COPIES RECEIVED:LTR TITLE: Construction Deficiency Report (10CFR50 ~ 55E)

+ENCL + SIZE:

NOTES:

RECIPIENT COPIES RECIPIENT COPIES ID CODE/NAME LtTTR ENCL ID CODE/NAME LTTR ENCL ACTION A/D LICENSNG 04 1 1 YOUNGBLOODpB 05 1 1 RVSHBROOKiM, 06 1 1 KIPERi K, 07 1 1 INTERNAL: AD/RC I/IE 17 1 1 AEOD 18 1 1 ASLBP/J ~ HARD 1 1 D/DIR HUM FAC15 1 EDO L STAFF 19 1 1 EQUIP QUAL'R11 1, 1 HYD/GEO BR 22 1. 1 l8E 09 2 2 LIC QUAL BR 12 1 1 MPA 20 1 1 NRC PDR 02 1 1 OELD 21 1 1 PRO RE V 13 1 1 QA BR 14 1 1 EG ILE 01 1 1 RUTHERFORDi'6 ~ IE 1 1 S DEY 21 1 1 EXTERNAL' ACRS 16 16 16 LPDR 03 1 1 NSIC 08 1 OCT xa torso TOTAL NUMBER OF COPIES REQUIRED: LTTR 40 ENCL 40

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~UMQHAWK NIAGARA MOHAWK POWER CORPORATION/300 ERIE 8OULEVARD WEST, SYRACUSE, N.Y. 13202/TELEPHONE (31S) 474-1511 October 2, 1980 Office of Inspection and Enforcement Region I Attention: Mr. R.T. Garison, Chief Reactor Construction and Engineering Support Branch U.S. Nuclear Regulatory Corenission 631 Park Avenue King of Prussia, PA 19406

Dear Mr. Carlson:

Re: Nine Mile Point Unit 2 Docket No. 50-410 On September 2, 1980 Mr. R. Feil of your staff was informed by telephone that Niagara Mohawk was evaluating a potential reportable deficiency in accordance with 10CFR50.55(e). This condition involves the fai lure of certain material in the spent fuel pool heat exchangers to meet specification requirements for impact testing.

The attached interim report is submitted in accordance with Paragraph 50.55{e) {3) of the Commission's regulations. Another report will be provided by December 1, 1980.

Very truly yours, NIAGARA MOHAW POMER CORPORAT ION

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INTERIM REPORT SPENT FUEL POOL COOLING l<ATER HEAT EXCHANGERS POTENTIALLY REPORTABLE DEFICIENCY 10CFR50.55(e)

DOCKET NO. 50-410 DESCRIPTION OF DEFICIENCY The potentially reportable deficiency was discovered during a review of the documentation package for the spent fuel pool cooling water heat exchangers.

The impact test data for several heat exchanger shell materials do not contain sufficient information to determine whether or not the purchase specification and ASME Code impact test acceptance criteria are met. Specifically, the acceptance criteria are based on a test specimen parameter called mils lateral expansion. For the heat exchanger carbon steel shell end plates, nozzles, nozzle reinforcing pads, and cradle supports, the impact test data included in the certified material test reports do not report this parameter.

Furthermore, the impact test data that are reported for the suspect materials indicate that the material used may be deficient for impact values.

It should be noted that the ASME Code does not require impact testing for Class 3 heat exchangers. However, this was an additional requirement in the purchase specification. The heat exchangers successfully passed a shop hydrostatic test and were ASME III, Class 3, stamped.

It has been confirmed that the information is not available, and that the test specimens were not retained by the testing laboratory, therefore precluding additional testing.

Based on the results of our preliminary investigation, this problem is a reportable deficiency. A review of the records as required by the quality assurance procedures established under 10CFR50, Appendix B, Article XI, Test Control, failed to establish that the testing requirements had been evaluated and documented.

ANALYSIS OF THE SAFETY IMPLICATIONS The test data provided indicate that the resistance to brittle fracture of some heat exchanger material is sufficiently low to possibly jeopardize the capability of the units to perform their safety function under all operating conditions.

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0 CORRECTIVE ACTION Information regarding the failure of the guality Assurance'Program to detect the problem in the Vendor's shop; an evaluation of the potential for failure of the heat exchangers, and additional data to determine the acceptability of the heat exchangers is being gathered. Initial corrective action to date has been to temporarily reject the affected heat exchangers for use. Also, the spent fuel pool heat exchanger Vendor has been temporarily identified as a supplier who requires increased surveillance. Final corrective action to resolve the problem and to prevent recurrence will be made after the above information is received and analyzed.

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