ML20211P313

Notification of 870312 Meeting W/Util & Novetech in Bethesda,Md to Discuss Fracture Mechanics Analysis of Crossover Lines,Per Encl Questions

ML20211P313
Person / Time
Site:	Yankee Rowe
Issue date:	02/20/1987
From:	Mckenna E Office of Nuclear Reactor Regulation
To:	Lear G Office of Nuclear Reactor Regulation
References
NUDOCS 8703020339
Download: ML20211P313 (5)

Text

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. FEB 2 01987 Docket No.50-029 MEMORANDUM FOR: . George E. Lear, Director PWR Project Directorate #1'

' Division of PWR Licensing-A FROM: Eileen M. McKenna, Project Manager Project Directorate #1 Division of PWR Licensing-A

SUBJECT:

FORTHCOMING MEETING WITH YANKEE ATOMIC ELECTRIC COMPANY -

YANKEE NUCLEAR POWER STATION DATE & TIME: Thursday, March 12, 1987 9:00 AM - 3:00 PM LOCATION: P-110 Phillips Building l Bethesda, MD PURPOSE: To discuss fracture mechanics analysis of crossover line (see attached set of questions).

Participants:

NRC YAEC P. Chen G. Papanic E. McKenna B. Holmgren R. Carter NOVETECH R. Gamble

/s Eileen M. McKenca, Project Manager Project Directorate #1 Division of PWR Licensing-A

Enclosure:

As Stated cc's: See Next Page t

Office: P Qth Surname: E c enna/tg D/PMtPl%-

Lear t Date: 02/2b/87 02/.T/874 8703020339 DR 870220 ADOCK 05000029 PDR

Mr. George Papanic, Jr.

Yankee Atomic Electric Company Yankee Nuclear Power Station CC:

Mr. James E. Tribble, President Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701 Thomas Dignan, Esquire Ropes and Gray 225 Franklin Street Boston, Massachusetts 02110 Mr. N. N. St. Laurent Plant Superintendent Yankee Atomic Electric Company Star Route Rowe, Massachusetts 01367 Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Resident Inspector Yankee Nuclear Power Station c/o U.S. NRC Post Office Box 28 Monroe Bridge, Massachusetts 01350 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 631 Park Avenue Kir.g of Prussia, Pennsylvania 19406 Robert M. Hallisey, Director Radiation Control Program Massachusetts Department of Public Health 150 Tremont Street, 7th Floor Boston, Massachusetts 02111

REVIEW OF THE LEAK BEFORE BREAK EVALUATION 4

FOR THE 5-INCH RECIRCULATION CROSSOVER LINE AT THE YANKEE NUCLEAR POWER STATION Evaluation

1. Additional justification is required before the flaw length used in the Level .D integrity analysis can be accepted for the leak before break evaluation. The staff guidance indicates that the flaw length used in the Level D evalua-tion should be twice the length of a flaw that will be readily detected during normal operation. Based on this criterion, confirm that the leakage corresponding to a flaw one-half the length used in the Level D evaluation can be detected reliably during normal operation using in-plant leakage detection equipment. Describe the action to be taken when the applicable unidentified leak rate is detected.

2. It is our understanding that the computational methods in References 5 and 6 are for BWR primary coolant conditions and may not be applicable for-PWR fluid conditions. Confirm that the IMLEAK software contains computational routines that are appropriate for the fluid conditions in the 5-inch recirculation crossover line. Also, provide information in the report to demonstrate that the IMLEAK software has been bench marked with experimental or service data, or with generally available, independently developed software (e.g. an updated version of the software associated with Reference 5, available at EPRI).

3. Specify the magnitude of the IMLEAK input variables used in the leak rate computations (e.g. surface roughness and number of turr.;) .

4. Provide a table listing the individual bending moments (e.g. deadweight, thermal, seismic) for each of the princi-pal coordinate directions and the axial loads at the limiting location. Also, confirm that the axial load entries in Table 4-2 are correct.

5. The one-degree rotation angle indicated in References 3 and 12 is not necessarily applicable for all pipe system and plant configurations. Information should be presented to dc.nonstrate that a one-degree rotation angle is reasonable

! for the plant specific', extreme load evaluation of the 5-inch line.

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6. Recent data for austenitic SMAW (see the reference attached to this evaluation) indicate that the J/T plot for SMAW in Figure 4-1 does not envelope the J/T behavior for austenitic SMAW. Unless the J/T plot in Figure 4-1 can be justified for the actual SMAW welds in the 5-inch recirculation crossover line, the extreme load evaluation for SMAW should be based on the data indicated in the attached reference.

Reference ,

" Evaluation of Flaws in Austenitic Steel Piping" EPRI NP-4690-SR, p.2-23, July 1986, Electric Power Research Institute, Palo Alto, CA, b

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" .-- FED E 0.1987 Distribution Copies:

{WEhle!505029,

.NRC PDR Local PDR ORAS HDenton

'CRossi Glainas DCrutchfield Glear

-EMcKenna

.PShuttleworth.

0GC-Bethesda EJordon BGrimes.

- JPartlow (Emergency Preparedness only)

Receptionist ACRS (10)

OPA-LFMB MSchaaf NRC Participants PAD r/f PAD s/f Licensee / Service List as i . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ . . _ _ . . _ _ _ _ . _ . _ _ . _