ML20203C207

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Summary of Third Progress Rept 860410 Meeting W/Epri,S&W, Novetech Corp & Rl Cloud Assoc to Discuss Progress in Whipjet Program Re Use of leak-before-break Assumption on balance-of-plant Piping
ML20203C207
Person / Time
Site: Beaver Valley
Issue date: 04/16/1986
From: Tam P
Office of Nuclear Reactor Regulation
To:
Office of Nuclear Reactor Regulation
References
TAC-62883, NUDOCS 8604210043
Download: ML20203C207 (7)


Text

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APR 16 1986 l

Docket No. 50-412 DISTRIBUTION,

  1. Dectet_r.1Ieel P.' Tam NRC PDR OELD Local PDR E. Jordan APPLICANT:

Duquesne Light Company et al.

PAD #2 Rdg B. Grimes J. Partlow ACRS (10)

FACILITY:

Beaver Valley Unit 2 L. Rubenstein NRC Participants

SUBJECT:

SUMMARY

OF MEETING ON APRIL 10, 1986 - THIRD PROGRESS REPORT ON WHIPJET The subject meeting was held to discuss with Duquesne Light Company (DLC) its progress in the WHIPJET program (use of leak-before-break assumption on balance-of-plant piping).

Previous meetings were held on March 4 and March 12, 1986. is the agenda of the meeting. Enclosure ? is the meeting attendee list.

Prior te the meeting, DLC informally provided to the staff a copy of the draft progress report.

Copies of the draft, revised, were distributed in the meeting.

Since the draft is not yet considered a formal report, and since it will be submitted in final form in the near future, it is not being included as part of this summary.

The staff distributed a document which provided the staff's positions en a number of issues (Enclosure 3). This document was discussed in detail. The staff indicated that formal positions will be prepared and transmitted by letter to the applicant in about I to 2 weeks.

The next meeting has been scheduled for May 20, 1986, in Bethesda. The staff expects to tour the site on WHIPJET issues shortly after the next meeting.

Isl Peter S. Tam, Project Manager PWR Project Directorate #2 Division of PWR Licensing-A Office of Nuclear Reactor Regulation

Enclosures:

As stated cc: See next page 4/[/86 4/g/8

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8604210043 860416 PDR ADOCK 05000412 A

PDR

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i Mr. J. J. Carey g

Duquesne Light Company Beaver Valley 2 Power Station 4

cc:

Gerald Charnoff, Esq.

Mr. R. E. Martin, Manager Jay E. Silberg, Esq.

Regulatory Affairs Shaw, Pittman, Potts & Trowbridge Duquesne Light Company 1800 M Street, N.W.

Beaver Valley Two Pro,iect Washington, DC 20036 P. O. Rox 328 Pittsburgh, Pennsylvania 15077 1

Mr. C. W. Ewing, Quality Assurance Zori Ferkin Manager Assistant Counsel Quality Assurance Department Governor Energy Council Duquesne Light Company 1625 N. Front Street P. O. Box 186 Harrisburg, PA 15105 Shippingport, Pennsylvania 15077 Director, Pennsylvania Emergency Management Agency Room B-151 Transportation & Safety Building Harrisburg, Pennsylvania 17120 Mr. T. J. Lex Mr. Thomas Gerusky Westinghouse Electric Corporation Bureau of Radiation Protection Power Systems PA Department of Environmental P. O. Box 355 Resources Pittsburgh, Pennsylvania 15230 P. O. Box 2063 Harrisburg, Pennsylvania 17120 Mr. P. RaySircar Stone & Webster Engineering Corporation BVPS-2 Records Management Supervisor P. O. Box 2325 Duquesne Light Company i

Boston, Massachusetts 02107 Post Office Box 4 Shippingport, Pennsylvania 15077 Mr. W. Troskoski U. S. NRC John A. Lee, Esq.

P. O. 181 Duquesne Light Company

.i Shippingport, Pennsylvania 15077 1 0xford Centre-i 301 Grant Street j

Mr. Thomas E. Murley, Regional Admin.

Pittsburgh, Pennsylvania 15?79 U. S. NRC, Region I 631 Park Avenue King of Prussia, Pennsylvania 15229

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t BEAVER VALLEY UNIT 2 WHIPJET PROGRESS REPORT MEETING 3 April 10, 1986 10:00 a.m. - 1:15 p.m.

Part A -

Opening Remarks - NRC Opening Remarks - DLC (5 minutes)

Part B -

Presentations and Discussions I. Overtiew (5 - 10 minutes)

II. Water Hammer (10 - 15 minutes) 0 III. System Descriptions IV. Piping Materials & Specifications V. Initial Screening VI. Crack Propagation Analysis VII. Critical Crack Size r

VIII. Stability Check (1 iour)

~l IX. Leak Rate Calculations X. Material Property Data (1 Hour r 15 min.)

XI. Testing 1

Part C -

Summary and Conclusions

' Future Meetings Site Visits, Correspondence 9

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Positions Reached at April 9, 1986, NRR Meeting 1.

Subject:

Representativeness of plant materials to test materials Position: a.

DLC will review t,he design, fabrication, and quality assurance records for the piping systems of interest to characterize the materials and fabrication procedures used i

in constru:: ting the piping systems. DLC will verify that i

the materials in the plant are represented by the test materials, b.

DLC will cataloa the materials available for fabrication into test spectinens (ferritic pipe and weld rod).

DLC will choose the three heats (pipe and weldment) based on upper and lower bound values of yield and average yield strength.

If there is not enough material in a given heat with ifmiting yield strength (e.g. upper bound value) the matrix of three tests of each heat may be altered in order to use the bounding material, provided the total number of tests is unchanged.

c.

DLC still have all the material certifications available for staff review.

I 2.

Subject:

Test methods related to development of J-R curves.

Position: a.

The staff recommends testing only 6" and 8" pipe rather than including 3" and 4" pipe specimens.

b.

DLC will test an uncracked 6" or 8" pipe to verify the assumption that the plastic displacement in the bend tests are only due to the crack. Span length and other experimental conditions must be the same for cracked and uncracked pipe.

3.

Subject:

PICEP/ Leak Detection Position: a.

DLC should define on a system-by-system basis the smallest leak rate that can reasonably be found in a timely manner consiutent with their inservice leakage detection method.

b.

Unless the licensee provides justification for considering lower leak rate margins, the staff's position is that a factor of 10 must be applied to a. to determine the leakage size crack from PICEP.

Item C contains factors to be considered when providing justification.

o 2-

's c.

The staff considers that the following factors contribute to the need for the one order of magnitude safety margin:

1)

Computational reliability of PICEF as influenced by parameters such as. flaw size and shape and as evidenced by comparisons of experimental and analytical results,

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Uncertainty in stress distributions, 3)

Effect of plugging of cracks by corrosion

products, 4)

Human response, and 5)

Equipment response.

6)

Background leakage d.

Consistent with the position taken in NUREG 1061, Vol. 3, redundancy in leak detection methods will be 6

required. Acceptable methods of achieving redundancy include:

1) mass balance, 2) temperature or humidity monitors, 3) visual inspection, 4) acoustic monitoring, and 5) augmented ISI for ferritic piping.

4.

Subject:

Susceptibility to corrosion and fatigue Position: DLC will demonstrate by reference to service experience that the piping systems in the WHIPJET program are not susceptible to corrosion or fatigue. DLC should document the sources of their conclusions.

DLC should also specify the thresholds for corrodants and temperature in the austenitic materials review for corrosion screening.

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Subject:

Fatigue crack growth analysis Position: a.

DLC will perfom as realistic analysis as possible using service level A and B loads, b.

The aspect ratio for the crack in the fatique evaluation should be 6.

Cracks can not grow deeper than 75% of the wall thickness. The length of the fatique crack must be less than both.

1) the length of the instability thru-wall at MtJ+ 5SE) 2)

1/2 (instability thru-wall flaw at (N+SSE)).

Clarification-Will DLC do fatique crack growth analysis when CUF<,1for Class 1, 2, 3 and Non Nuclear Grade piping?

6.

Subject:

Post-Weld Heat Treatment Position DLC will detemine where there are welds in the program scope that have not been post weld heat treated. DLC will either heat treat the welds or develop the infomation needed to 6

assure that the test program will be representative of these walds.

Clarification-For non-post weld heat treated pipe,r 1 residual weld stress effect the depth of the flaw in itique evaluation?

7.

Subject:

Ferritic Pipe Behavior Below the Upper Shelf Energy (USE)

Temperature Position: DLC will determine whether there are any ferritic piping systems in the program that will be below USE temperatures when a failure from postulated loading (such as SSE) could result in a safety concern.

If this is possible, DLC will have to use appropriate fracture mechanics methods and material properties.

8.

Subject:

Positive Displacement Pumps Position: DLC will detemine the systems still in the WHIPJET program that have positive displacement pumps and will indicate for those pumps how vibration fatigue has been minimized to acceptable levels.

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