ML17059A512

Forwards RAI Re Proposed License Amend to Allow Use of Range 10 on Intermediate Range Monitors for Unit 1.Requests to Respond within 30 Days of Receipt of This Ltr

ML17059A512
Person / Time
Site:	Nine Mile Point
Issue date:	11/03/1994
From:	Brinkman D Office of Nuclear Reactor Regulation
To:	Sylvia B NIAGARA MOHAWK POWER CORP.
References
TAC-M89981, NUDOCS 9411090216
Download: ML17059A512 (10)

Text

November 3, 1994 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Hohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Distribution:

Docket File PUBLIC PD I-1 Rdg.

SVarga JZwolinski HCase OGC CVogan ACRS(10)

DBrinkman GGolub RJones CCowgill, RI

SUBJECT:

REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT TO ALLOW USE OF RANGE 10 ON INTERMEDIATE RANGE MONITORS (IRHs)

FOR NINE MILE POINT NUCLEAR STATION UNIT NO.

1 (NMP-1)

(TAC NO. H89981)

Dear Hr. Sylvia:

By letter dated July 21,

1994, Niagara Mohawk Power Corporation (NMPC),

proposed a license amendment to revise NMP-1 Technical Specifications (TSs)

2. 1.2, 3. 1.7, and 3.6.2/4.6.2 and associated Bases to allow the use of Range 10 on the IRHs with the reactor protection system low pressure trip for main steam line isolation valve closure not in bypass.

The NRC staff has begun its review of NHPC's July 21, 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 enclosed request for additional information (RAI), our questions address proposed trip setpoints and the analysis of design basis'vents.

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, Original signed by 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 DOCUMENT NAME:

H:'ItNH189981.RAI To receive a copy of this document, Indicate in the box: "C" ~ Copy without enclosures "E" ~ Copy with enclosures "N" ~ No copy OFFICE LA:PDI-E.

PH: PDI-1 D: PDI-1 NAME CVo an e" C-DBrinkman:c MCase DATE ll/Q./94 11/Z./94 ll/

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 3, 1994 Hr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093

SUBJECT:

RE(UEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT TO ALLOW USE OF RANGE 10 ON INTERMEDIATE RANGE MONITORS (IRHs)

FOR NINE NILE POINT NUCLEAR STATION UNIT NO.

1 (NMP-1)

(TAC NO. H89981)

Dear Hr. Sylvia:

By letter dated July 21,

1994, Niagara Mohawk Power Corporation (NMPC),

proposed a license amendment to revise NMP-1 Technical Specifications (TSs)

2. 1.2, 3. 1.7, and 3.6.2/4.6.2 and associated Bases to allow the use of Range 10 on the IRMs with the reactor protection system low pressure trip for main steam line isolation valve closure not in bypass.

Th'e NRC staff has begun its review of NHPC's July 21, 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 enclosed request for additional information (RAI), our questions address proposed trip setpoints and the analysis of design basis events.

NMPC 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, 8 ~gJ.gwA.

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

1

B. Ralph Sylvia Niagara Mohawk Power Corporation CC:

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

Oswego, NY 13126 Mr. Louis F. Storz Vice President Nuclear Generation Niagara Mohawk 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'rie -Boulevard West

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

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

Albany, NY 12223 Nine Mile Point Nuclear Station Unit No.

1 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 Mile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093 Charles'onaldson, 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 Mohawk Power Corporation Nine Nile Point Nuclear Station P.O.

Box 63

Lycoming, NY 13093

r

RE VEST FOR ADDITIONAL INFORMATION EGARDING ROPOSED LICENSE AMENDMENT TO ALLOW USE OF RANGE 10 ON IN ERMEDIATE RANGE MONITORS IRMs AT INE MILE POINT NUCLEAR STATION UNIT NO.

1 In Niagara Mohawk Power Corporation's submittal, reference is made to GENE-909-16-0393 and GENE-909-39-1093.

These reports provide information on the overlap between average power range monitor (APRM) and IRM ranges and are required for more fully evaluating the proposed changes.

Please provide these documents.

The proposed TSs require recirculation flow to be greater than 20X for entry into range 10, and also require a rod withdrawal block until recirculation flow exceeds 30X.

A minimum flow of 30X is required when reactor power is greater than 20X to satisfy minimum critical power ratio (MCPR) limits, and the proposed rod block is to ensure that power stays near approximately 12X upon entry into range 10 until 30X flow is achieved.

It is not clear that the 20X flow requirement together with the rod withdrawal block will offer sufficient margin to HCPR limits for events that may raise power above 30X.

Provide supporting analysis to show that the rod block with the minimum flow requirement will offer sufficient margin to MCPR limits.

Is the rod withdrawal block in effect for all rods'oes the minimum recirculation flow criteria bound future operating cycles?

Also, provide supporting information on existing limits which ensure 30X recirculation flow in "run" mode.

Increasing the minimum recirculation requirement to 30X for entry into range 10 would provide increased margin against HCPR limits.

The proposed TSs have eliminated the downscale APRM reactor

scram, and have reduced the setpoint for downscale APRM rod withdrawal block.

The submittal states that justification for the change is provided by the increased ove} lap between IRM and APRH with the addition of range 10, and the proposed IRH/APRH overlap surveillance.

Due to the fact that reliance is being placed on this overlap, the licensee will be required to use range 10 when moving between APRH operation and IRH operation.

Provide further information on how the requirement to use range 10 will be incorporated into the TSs.

Although operator error events have been evaluated, address the possibility of other events that are affected by the deletion of the APRH scram and describe the outcome.

What upscale trips are in place for the APRHs for rod withdrawal block and reactor scram when the mode switch is in other than "run" mode.

Specifically, are upscale trips at 15X for reactor scram and 12X for rod withdrawal block in effect for modes other than "run"7 Discuss how operation near 40X power in the "startup" mode will be affected by these APRM trip signals.

Enclosure

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Provide more information on the analysis

done, computer codes and methods used for the control rod withdrawal event and rod drop event, along with the resulting fuel and clad conditions.

Describe how use of the proposed APRH/IRH setpoints will affect these events, particularly noting peak fuel enthalpy limits with and without the use of range 10.

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