ML17059A538

Forwards Request for Addl Info Re Util 940901 Proposed License Amend to Revise pressure-temp Limits for Reactor Vessel.Response Requested within 30 Days of Ltr Receipt

ML17059A538
Person / Time
Site:	Nine Mile Point
Issue date:	11/21/1994
From:	Brinkman D Office of Nuclear Reactor Regulation
To:	Sylvia B NIAGARA MOHAWK POWER CORP.
References
TAC-M90288, NUDOCS 9411280241
Download: ML17059A538 (10)

Text

November 21, 1994 Hr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, New York 13093

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION CHANGE TO REVISE THE PRESSURE-TEMPERATURE LIMITS FOR NINE MILE POINT NUCLEAR STATION UNIT NO.

1 (NMP-1)

(TAC NO. H90288)

By letter dated September 1,

1994, Niagara Mohawk Power Corporation (NMPC),

proposed a license amendment to revise the pressure-temperature limits for the NHP-1 reactor vessel.

The NRC staff has begun its review of NMPC's September 1,

1994, submittal.

However, we have determined that additional information, as identified in the enclosure, is required to complete our review of the submittal.

As indicated in the attached request for additional information (RAI), additional information is required regarding the calculation of the proposed pressure-temperature limits for the NHP-1 reactor vessel.

NHPC is requested to respond to this RAI within 30 days of receipt of this letter in order for us to complete our review in a timely manner.

This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.

Sincerely,

/s/

Donald S. Brinkman, Senior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosure:

Request for Additional Information cc w/encl:

See next page DISTRIBUTION:

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PUBLIC PDI-1 Reading SVarga JZwolinski HCase CVogan DBrinkman AWilford JStrosnider OGC ACRS (4)

CCowgi 1 1, RGN-I DOCUMENT NAME:

H: 'ILNMPIiNM190288. LTR To receive a copy of this document, indicate in the box: "C" a Copy without enclosures "E" a Copy with enciosures "N" a No copy OFFICE LA:PDI-1 PM: PDI-1 A D: PD -1 DBrinkman:cn 11/g( /94 HCase CVo an DATE II/gl/94 ll/y /94 "q4IgSSOZ4I cy4IISI l

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November 21, 1994 I

Hr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Hohawk Power Corporation Nine Hile Point Nuclear Station P.O.

Box 63

Lycoming, New York 13093

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION CHANGE TO REVISE THE PRESSURE-TEMPERATURE LIMITS FOR NINE NILE POINT NUCLEAR STATION UNIT NO.

1 (NMP-1)

(TAC NO. H90288)

By letter dated September 1,

1994, Niagara Mohawk Power Corporation (NHPC),

proposed a license amendment to revise the pressure-temperature limits for the NMP-1 reactor vessel.

The NRC staff has begun its review of NHPC's September 1,

1994, submittal.

However, we have determined that additional information, as identified in the enclosure, is required to complete our review of the submittal.

As indicated in the attached request for additional information (RAI), additional information is required regarding the calculation of the proposed pressure-temperature limits for the NHP-1 reactor vessel.

NHPC is requested to respond to this RAI within 30 days of receipt of this letter in order for us to complete our review in a timely manner.

This requirement affects one respondent and, therefore, is not subject to Office of Management and Budget review under P.L.96-511.

Sincerely,

/s/

Donald S. Brinkman,'enior Project Manager Project Directorate I-1 Division of Reactor Projects I/II Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosure:

Request for Additional Information cc w/encl:

See next page

~UIBTRIBUTIU Docket File PUBLIC PDI-1 Reading SVarga JZwolinski HCase CVogan DBrinkman AWilford JStrosnider OGC ACRS (4)

CCowgill, RGN-I DOCUMENT NAME:

H: iNMPliNH190288. LTR To receive e copy ot this document, indicete in the box: "C" ~ Copy without enclosures "E

~ Copy with enclosures "N

~ No copy OFFICE LA:PDI-1 g

PH: PDI-1 A D:PD -1 NAME CVo an DBrinkman:cn HCase DATE ll/7.I/94 ll/2(/94 ll/z /94 OFFICIAL R CORD COPY

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B. Ralph Sylvia Niagara Hohawk Power Corporation Nine Mile Point Nuclear Station Unit No.

1 CC:

Mark J. Wetterhahn, Esquire Winston 8 Strawn 1400 L Street, NW Washington, DC 20005-3502 Supervisor Town of Scriba Route 8, Box 382

Oswego, NY 13126 Mr. Louis F. Storz Vice President Nuclear Generation Niagara Hohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Resident Inspector U.S. Nuclear Regulatory Commission P.O.

Box 126

Lycoming, NY 13093 Gary D. Wilson, Esquire Niagara Mohawk Power Corporation 300 Erie Boulevard West

Syracuse, NY 13202 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Hs.

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

Albany, NY 12223 Hr. Richard B. Abbott Unit 1 Plant Manager Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Hr. David K. Greene Manager Licensing Niagara Mohawk Power Corporation Nine Nile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Hr. Paul D.

Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza

Albany, NY 12223 Hr. Martin J.

McCormick, Jr.

Vice President Nuclear Safety Assessment and Support Niagara Hohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093

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VEST FOR ADDIT ON L

NFORMA 0

REGARDING PRO OSED CHANGES TO THE REACTOR V SSEL PRESSURE-TEMPERATURE LIMITS NIAGARA MOHAWK OW R

COR ORA ION NIN MI POIN NUCL A S

0 U IT O.

1 DOC E

NO. 50-220

1. 'co e St tus of Rev'ew The fracture toughness requirements for ferritic materials in the pressure-retaining components of the reactor coolant pressure boundary are specified for testing and operational conditions, including anticipated operational occurrences, in Section IV of Appendix G of 10 CFR Part 50.

This appendix requires the acceptance and performance criteria of Appendix G of Section III of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code (ASME Code).

Pressure-temperature calculation procedures are described in Appendix G

of the ASME Code.

Changes in the fracture-toughness properties of materials in the beltline region, resulting from neutron irradiation and the thermal environment, are monitored by a surveillance program in compliance to the requirements of Appendix H of 10 CFR Part 50.

The effect of neutron fluence on the shift in the nil-ductility temperature of pressure vessel steel is predicted by Regulatory Guide 1.99 (RG 1.99), "Effect of Residual Elements on Predicted Radiation Damage to Reactor Vessel Materials."

The licensee, Niagara Mohawk Power Corporation, has prepared an application for amendment to the operating license in order to revise TS 3.2.2, "Minimum Reactor Vessel Temperature for Pressurization."

2.

Additional Information Re uired Based on the review of the licensee's submittal, the NRC staff has concluded that the following information and/or clarification is required to complete the review of the amendment request:

A.

For the surveillance plate material, Criteria 1 of RG 1.99, Rev.

2 was not met because the limiting material (upper plate G-307-4) is not the surveillance material.

Criteria 3 was not met because the method described in Regulatory Position 2.1 was not used to obtain the best-fit line of the plant specific data..

Verify and provide the basis for determining that the surveillance. data are credible.

Enclosure

A

For equation (2-2) on Page 5 of the submittal (calculation of MT~, for the beltline plate material);

(1) Identify all raw data used to arrive at this equation, Figure 2-1 on Page ll of the submittal compares the RG 1.99, Rev.

2 model with the plant specific MT~, model.

For each data point:

(1) Provide the copper and nickel content, (2) Identify the plant from which each data point was obtained, and (3) Identify which data were not used in development of the curve.

Provide the basis and data used to conclude that "... most BWRs operate at fluences below the fluence threshold for significant Cu precipitation."

(Page 3 of submittal)

Provide the basis for using a margin of 17 'F as opposed to 34 'F as specified in RG 1.99 in the calculation of the adjusted reference temperature for the beltline plates.

Provide applicable information, with respect to questions 1-6 above, regarding the beltline welds.

IVg le 47 g

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