ML20207S617

Forwards Safety Evaluation Supporting Util 860122,0812,1028 & 870204 Submittals Re Fracture Toughness Requirements for Protection Against PTS Events.Requests Reevaluation of PTS Shock Values & Comparison W/Predicted Values

ML20207S617
Person / Time
Site:	Yankee Rowe
Issue date:	03/10/1987
From:	Mckenna E Office of Nuclear Reactor Regulation
To:	Papanic G YANKEE ATOMIC ELECTRIC CO.
Shared Package
ML20207S618	List: ML20207S617 ML20207S623
References
NUDOCS 8703200100
Download: ML20207S617 (3)

Text

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Docket No.50-029 10 W Mr. George Papanic, Jr.

Senior _ Project Engineer-Licensing' Yankee Atomic Electric Company 1671 Worcester Road

Framingham, _ Massachusetts 01701

SUBJECT:

YANKEE NUCLEAR POWER STATION - FRACTURE TOUGHNESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SH0CK EVENTS We have reviewed your letters dated January 22, August 12, October 28, 1986, and February 4, 1987 which were submitted in response to the_ Pressurized Thermal Shock (PTS) Rule, 10 CFR 50.61, for'the Yankee Nuclear Power Station.

We have found the material properties of reactor vessel beltline materials, the projected fluence at the inner surface of the reactor vessel for the end of life of the plant, and the calculated RT for the end of life of the plant to be acceptable. The calculated RT $lSbelow the screening criteria of 270" Fat 32EFPY,whichisbeyondtNSexpiration date of the license and, therefore, meets the requirements of the PTS Rule.

The PTS Rule requires that the projected assessment of the RT must be updatedwheneverchangesincoreloadings,surveillancemeasuhNentsofother information'(including changes in capacity factor) indicate a significant change in the projected values. This ensures that the licensees will track the accumulated fluence for the limiting beltline materials throughout the life of the plant to verify that their assumptions remain valid, In this regard we request that you submit a reevaluation of the RT and comparison with the predictedvalueinanyfuturepressure-temperatuhdbsubmittals which are submttted as required by 10 CFR Part 50, Appendix G.

Our associated Safety Evaluation is enclosed.

Sincerely, 8703200100 870310 9 Eileen M. McKenna, Project Manager PDR ADOCK 0500 Project Directorate #1

- P Division of PWR Licensing-A

Enclosure:

As stated cc w/ enclosure See next page g

• SEE PREVIOUS CONCURRENCE Office: PM/ PAD #1 PC/ PAD #1 Surname: *EMcKenna *Glear Date: 03/09/87 03/10/87

Docket No.50-029 Mr. George Papanic, Jr.

Senior Project Ergineer-Licensing Yankee Atomic Electric Company 1671 Worcester Road Framingham, Massachusetts 01701

SUBJECT:

YANKEE NUCLEAR POWER STATION - FRACTURE TOUG ESS REQUIREMENTS FOR PROTECTION AGAINST PRESSURIZED THERMAL SHOC EVENTS We have reviewed your letters dated January 22, Au st 12, October 28, 1986, and February 4, 1987 which were submitted in resp se to the Pressurized Thermal Shock (PTS) Rule, 10 CFR 50.61, for the nkee Nuclear Power Station.

We have found the material properties.of reacto vessel beltline materials, the projected fluence.at the inner surface of the eactor vessel for the end of life of the plant,-and the calculated RT f.r the end of life of the plant to be acceptable. The calculated RT N3b low the screening criteria of 270 F at 32 EFPY, which is beyond t S3 expt' ration date of the license and, therefore, meets the requirements of the PTS Rule.

The.-PTS Rule requires that the project d assessment of the RT must be updated whenever changes in core loa ngs, surveillance measu N kents of other I' information (including changes in c acity factor) indicate a significant change in the projected values. T s ensures that the_ licensees will track the accumulated fluence for the 1 ' iting beltline materials throughout the life of the plant to verify that thei assumptions remain valid, In this regard we request that you submit a re-ev luation of the RT and comparison with the predicted value in any future ressure-Temperatur$Tkubmittalswhichare submitted as required by 10 C R 50, Appendix G.

Our associated Safety Evalu tion is enclosed.

Sincerely.

Eileen M. McKenna, Project Manager Project Directorate #1 Division cf PWR Licensing-A

Enclosure:

As stated cc w/ enclosure See next page gp Office: M'k1 PD/ PAD #1 Surname: EMcKenha Glear Date: 03/f)/87 03/f/87

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

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Chairman Board of Selectmen Town of Rowe Rowe, Massachusetts 01367 Resident Insoector 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 King of Prussia, Pennsylvania 19406 Robert M. Hallisey, Director Radiation Control Program l Massachusetts Department of Public Health 150 Tremont Street, 7th Floor Boston, Massachusetts 02111 1

b A

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