ML20210Q979

Responds to 860417 Request for NRR to Provide Position Re Performance of Sys Pressure Test (Leakage & Hydrostatic) Using Nuclear Heating & Definition of Plant Startup W/Regard to Pressure Testing (ASME Code,Section XI)

ML20210Q979
Person / Time
Site:	Hatch
Issue date:	04/29/1986
From:	Bernero R Office of Nuclear Reactor Regulation
To:	Gibson A NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20210Q983	List: ML20210Q979 ML20212A870 ML20212N511
References
NUDOCS 8605150634
Download: ML20210Q979 (5)

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. April . 29, .l.986

. . MENORANQl#4. FOR :, Albert.F..Gibson[Di. rector; .

Division of Riatto'r Safety '

Region II:

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FROM:

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. Robert.d..Bernero, Director

. Div'is ion' of .BWR' L i.cens ing

SUBJECT:

INTERPRETATION OF SYSTEM PRESSURE TEST REQUIREMENTS

~ This' respondst'o 'your memor'anduin dat5d Apfil 17', 1986, requesting"NRR to-provide a' position regarding .the performance .of system, pressure tests (Leakage and Hydrostatic) using nuclear heating and .a definition of

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plant stiart-up with regsrd"to pres'sure testing.

The ASME Code,Section XI requires that the System Leakage Test be performed prior to startup following each refueling outage (Table IWB-2500-1, Note 5). The examination method required is a visual, Type VT-2. Later ' additions of Section XI permit system hydrostatic tests to be performed in lieu of the system leakage test. Further, the Code

-states that reactor coolant shall be used as the pressurizing medium.

Also, the Code permits visual examination to be performed at 200*F with appropriate pressure corresponding to a pres'sure consistent.with, fracture prevention for system components that ' require a test temperature aboe 200 F.

As you are aware, ASME Section XI is incorporated by reference as part of NRC regulations. Therefore, this is an issue whether regulations are being met, not just a simple code compliance question.

The position of the staff is that System Pressure Tests (Leakage and Hydrostatic) are to be performad before the reactor goes critical from a refueling outage. The System Leakage Test is a test to determine if any abnormal' leakage is occurring in the reactor coolant pressure boundary after its opening and closing. The Hydrostatic Test is. a proof test of repairs on the reactor coolant pressure boundary or other component. Prudence dictates that both of these tests be performed at the lowest temperatures that are consistent with the fracture prevention criteria for the reactor vessel or other component so that stored energy can be minimized during testing conditions by having the system water solid. The temperature correction terms are provided to account for

, changes in material properities when the vessel must be heated for fracture provention. We do not believe the temperature corrections are an invitation to perform the testing at higher temperature to minimize the test pressures. The pressurizing medium is to be reactor coolant rather than steam. We recognize that some flashing to steam of any -

potential leakage could occur when temperatures in excess of boiling are necessary for the , test.

Cont.act: "R.' liennann .

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4 We;believe-the Code.section allowing reduc' tion of. tempera'tures 5elow 200.

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.- 'at correspondi~ng pressures' is prudent for*'thec visual examination.in that

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,. " risk:t'o. plant personnel.is reduced and any leakage would be liquid and;

. therefore, more.readily detect.able. .With regard to a d.efinition of .

. . start-up, start-up occurs when the mode s' witch is placed in "startup/ hot

~ .* :stan_dby" and' control rod withdrawal,is begun. - The ASME sude : intended .-

both Sy' stem lhakage' and Hydrostatic Tests t'o ~ t5e perf'orined prior to'. react'or' '

criticality _from a r'efueling. The later Code position (footnote 7 to l- . Table IWB-2500-1, Category B-P) permitting the System Hydrostatic Test to b.e used in lieu of the Leakage, Test is a clear indication that the code 4* .

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.i.ntended .the. system. hydrostatic also,.be. performed at 1ow temperatures , .

! ' consistent'with fracture ' prevention considerations prior to reactor start-up.

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Robert M. Bernero, Director Division of BWR Licensing t

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- - . . June 16, .1'986 - .

Nuclear Operations '

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, -ASME Section XI, Division 1. .

' Inquiry-System' Pressure Te'sts

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. File: X7GJ12-H000 Log: SL-873 2777N Key Words:' ASME Code Inquiries,

- , . System. Pressure LTests, .

Inservice' Inspection Secretary , . .

ASME Boiler and Pressure Vessel Committee 345 East 47th Street New York, New York 10017

Dear Sir:

Pursuant to a request by the United States Nuclear Regulatory Commission (NRC) on May 11,1986 and our related commitment, Georgia Power Company (GPC) encloses he. rein several Code inquiries and proposed respo.nses for interpretation by' the Bo'iler and Pressure Vessel Committee. The . inqui ries

'primarily pertain to the ' acceptability of conducting system ' pressure tests

? required by ASME Section XI, Division 1 (1980 Edition with Addenda through Winter 1981) using nuclear heating. It is requested that the Boiler and Pressure Vessel Committee provide i ts interpretations ~ to .the enclosed inquiries by October 1,1986. The NRC has indicated to GPC that it would help expedite through -ASME 'the interpretation of our Code inquiries since the NRC similarly wishes to resolve the issue of whether nuclear heating is acceptable during the condact of system pressure tc:: ting.

By copy of this letter,. the NRC is being provided . documentation of GPC's Code inquiries submittal ' to ASME and our fulfillment of our May 1,.1986 commitment made to Mr. Robert Bernero of the NRC relative to system pressure testing at Plant Hatch.

Should you have any questions in this regard, please contact this office.

Sincerely, L. T. Gucwa h

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c(w): . Georgia Power Cempany .

Mr. J. . P. 0lReilly .

Mr. J. T. ' Beckham, -J r.

Mr. H. C. Nix, Jr.

GO-NORMS

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Mr. T. N. Epps, III U. -S. Nuclear Reguisory Commission.. . -

Director of Nuclear Reactor Regulation Dr. J. N. Grace (NRC Region II)

Senior Resident Inspector - Plan't Hatch ASME Code Participents Dr. W. F. Anderson 'NRC I&E)

Mr. J. A. Birkle (Consumers Power Company)

Dr. S. H. Bush (Pacific Northwest Laborattry)

Mr. W. C. Ham (Pacific Gas & Electric Company)

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. Question (1).:

IWA-5211(d) of . the ~ 1986 Edition .of . ASME 'Section ' XI, '

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.- . , , ., .Dhision' 1,' sitih Adden' a 'd thhiugh Win't'er.1981' requires

...that'.. hydrostatic testing bd conducted during a' plant

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'shu'td6wn. "D'oss Eths c6ndittori'" plant shutdown" require that .the. r,eactor be in a . noncritical state?

Proposed Reply (1): No. The. term "p'lant shutd'own" refers .to the condition

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(where'.the t plant.:is not on-line producing electric power.

Question (2): Table IWB '2500-1. (Note 5.) .of. the 1980 Edition of ASME Section . XI,' Division 1, with. Addenda through . Winter 1981- requires'that system leakage tests -conducted per

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' Examination Category B-P be performed prior to plant startup .following each refueling' outage. Does the

. statement' " prior - to_ pl ant startup"- require . that- the reacter be in a' noncritical state?

Proposed Reply (2): No. The term " prior .to plant startup" refers to the condition' where the plant i_ s not on-line , . producing electrical power.

Question (3): IWB-5222 and IWB-5230 of the 1980 Edition of ASME Section XI, Divisfor 1, with Addenda through Winter 1981 requires the modi ficat.f on of. . hydrostatic ' test .

temperatures .a'nd pressur6s to meet- fracture prevention 1

cri teria. Is it the intent of ~ ASME Section XI to adoress the techniques by which the elevated temperatures are produced during the conduct of the hydro:tatic test?

Proposed Reply (3): No.

Question (4): IWB-5210(b) .of the 1980 Edition .of ASNE Section XI, Division 1, with Addenda through Winter 1981 states that reactor coolant shall be used as the pressurizing medfum when performing system pressure tests. May a mixture of steam, water and non-condensible gases be used as the pressurizing medium to meet the requirements of IWB-5210( b) when performing system pressure tests of the primary reactor coolant system (Boiling Water Reactor)?

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Proposed Reply (4): Yes.

Submitted by: L. T. Gucwa Georgia Power Company P. O. Box 4545 Atlanta, Gsorgia' 303'J2 6

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