NUREG-0808, Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations

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Forwards Safety Evaluation Accepting Revised Safety Relief Valve & Condensation Oscillation Loads Per NUREG-0802 & NUREG-0808 & Temp Cutoff Value Used for Elimination of Data Base for Load Computations
ML17055D983
Person / Time
Site: Nine Mile Point 
Issue date: 06/29/1988
From: Haughey M
Office of Nuclear Reactor Regulation
To: Mangan C
NIAGARA MOHAWK POWER CORP.
Shared Package
ML17055D984 List:
References
RTR-NUREG-0802, RTR-NUREG-0808, RTR-NUREG-802, RTR-NUREG-808 TAC-63425, NUDOCS 8807120401
Download: ML17055D983 (6)


Text

June 29, 1988 Docket No. 50-410

SUBJECT:

SAFETY EVALUATION CONCERNING POINT, UNIT 2 (TAC 63425)

Mr. Charles V. Mangan Senior Vice President Niagara Mohawk Power Corporation 301 Plainfield Road

Syracuse, New York 13212

Dear Mr. Mangan:

DISTRIBUTION NRCPDR Local PDR SVarga BBoger CVogan MHaughy OGC-WF EJordan BGrimes DOWNCOMERS IN NINE MILE ACRS(10)

JKudrick YLi

REFERENCES:

1.

Letter from W. J.

Donlon to the NRC (NMP2L-1035) dated May 15, 1987 submitting the "Downcomer Reanalysis Report" 2.

Letter from C. V. Mangan to the NRC (NMP2L-1083),

dated October 14, 1987, submitting supplementary information to the revised downcomer analysis 3.

Letter from C. V. Mangan to the NRC (NMP2L-1103),

dated January 12, 1988, submitting responses to

,'staff questions regarding the downcomer reanalysis raised during a meeting on December 7, 1987 Paragraph 2.D.iv of Facility Operating License NPF-69 for Nine Mile Point, Unit 2 (NMP-2) granted a schedular exemption to GDC 2, "Design Bases for Protection Against'atural Phenomena,"

Appendix A to 10 CFR Part 50 until the first refueling outage, to allow additional time to demonstrate the adequacy of the downcomer design under the plant faulted condition (simultaneous occurrence of a Loss-of-Coo'f,a'nt Accident (LOCA)'nd a Safe Shutdown Earthquake (SSE)).

The details of the staff's concerns and the evaluation of the request for a schedular exemption are contained in Section 6.2. 1.7.4 of Supplement 3 to the Safety Evaluation Report (SSER 3).

In Reference 1 Niagara Mohawk provided a

reevaluation, of the expected loads on the downcomers and the resulting stresses.

That reanalysis was further supplemented by References 2 and 3.

The staff has completed its review of the revised downcomer analysis as submitted in the letters referenced above.

On the basis of the information submitted, we have concluded that the revised Safety Relief Valve (SRV) and Condensation Oscillation (CO) loads on -the downcomers have been calculated in conformance with the acceptance criteria described within NUREG-0802, "Safety/Relief Valve Quencher Loads:

Evaluation for BWR Mark II and III Containments" and NUREG-0808, "Mark II Containment Program Evaluation and Acceptance Criteria."

Also, the temperature cutoff value used for the elimination of a portion of the data base for CO load computations represents a conservative value.

Therefore, the staff finds the revised SRV and CO loads to be acceptable.

In addition, the staff has reviewed the reanalysis with respect to the structural SS07>a040>

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adequacy of the:downcomers with the revised loads and has determined that the design of the downcomers is"adequate for the faulted condition and includes an adequate. margin, of safety to accotrmodate the uncertainties previously addressed by the staff in SSER 3.

The staff therefore finds the downcomer design is adequate to withstand the expected loads in the faulted condition and consequently meets the'requirements of GDC 2.

Therefore the schedular exemption is no longer needed.

The enclosed Safety Evaluation contains the bases for the staff's conclusions.

Sincerely, grgmg s1pg @

Enclosure:

As stated Mary F. Haughey, Project Manager Project Directorate 1-1 Division of Reactor Projects, I/II cc:

See next page PDI-l,i ( P CVogan~

6/g(88 PDI-NHaughey:dig 6/Z)/88 RCapra 6/

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c Mr. C. V. Mangan Niagara Mohawk -Power Corporation Nine Mile Point Nuclear Station Unit 2 CC:

Mr. Troy B. Conner, Jr.,

Esq.

Conner 5 Wetterhahn Suite 1050 1747 Pennsylvania

Avenue, N.W.

Washington, D.C.

20006 Mr. Richard Goldsmith Syr acuse Univers ity College of Law E. I. White Hall Campus

Syracuse, New York 12223 Mr. Don Hill Niagara Mohawk Power Corporation Suite 550 4520 East West Highway
Bethesda, MD 20814 Resident Inspector Nine Mile Point Nuclear Powe~ Station P. 0.

Box 99

Lycoming, New York 13093 Mr. Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West
Syracuse, New York 13202 Mr. Peter E. Francisco, Licensing Niagara Mohawk Power Corporation 301 Plainfield Road
Syracuse, New York 13212 Ms.

Donna Ross New York State Energy Office 2 Empire State Plaza 16th Floor

Albany, New York 12223 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, Pennsylvania 19406 Mr. Paul D. Eddy New York State Public Serice Commission Nine Mile Point Nuclear Station-Unit 2 P.O.

Box 63

Lycoming, New York 13093 Mr. Richard M. Kessel Chair and Executive Director State Consumer Protection Board 99 Washington Avenue
Albany, New York 12210 Mr. Richard Abbott, Unit 2 Station Superintendent Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation P. 0.

Box 32

Lycoming, NY 13093 Mr. James L. Willis, General Supt.,

Nuclear Generation Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation P. 0.

Box 32

Lycoming, NY 13093

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