ML17059A515

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Forwards Request for Addl Info Re Proposed License Amend to Allow Use of Range 10 on Intermediate Range Monitors for Plant,Unit 1.Response Requested within 30 Days of Receipt of Ltr
ML17059A515
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 11/09/1994
From: Brinkman D
Office of Nuclear Reactor Regulation
To: Sylvia R
NIAGARA MOHAWK POWER CORP.
References
TAC-89981, NUDOCS 9411140178
Download: ML17059A515 (8)


Text

November 9,

1994 Mr. B. Ralph Sylvia Executive Vice President, Nuclear Niagara Mohawk 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 (IRMs)

FOR NINE MILE POINT NUCLEAR STATION UNIT NO.

1 (NHP-1)

(TAC NO. H89981)

Dear Hr. Sylvia:

By letter dated July 21,

1994, Niagara Mohawk Power Corporation (NMPC),

proposed a license amendment to revise NHP-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 NMPC'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 setpoint methodology, instrumentation drift, and channel overlap.

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, Original signed by Donald S.

Brinkman, Senior Project Manager Project DirectorateI-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: iNH189981. RAI To receive a copy of this document, indicate in the box: "C" ~ Copy without enclosures "E" ~ Copy with enclosures "N" ~ No copy OFFICE NAME DATE LA:PDI-1 CVo an ll/$ /94 PH: PD I-1 L.

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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 9, 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:

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 (NHP-1)

(TAC NO. H89981)

Dear Hr. Sylvia:

By letter dated July 21, 1994, Niagara Hohawk Power Corporation (NHPC),

proposed a license amendment to revise NHP-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 reactol protection system low pressure trip for.:

main steam line isolation valve closure not in bypass.

The NRC staff has begun its review of NMPC'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 setpoint methodology, instrumentation drift, and channel

~

overlap.

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, there'fore, is not subject to Office of Hanagement and Budget review under P.L.96-511.

Sincerely, Donald S. Brinkman, Senior Project Manager Project Directorate I-l 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

B. Ralph Sylvia Niagara Mohawk Power Corporation CC:

Hark J. Wetterhahn, Esquire Winston 5, Strawn 1400 L Street, NW Washington, DC 20005-3502 Supervisor Town of Scriba Route 8, Box 382

Oswego, NY 13126 Hr. Louis F. Storz Vice President Nuclear Generation Niagara Mohawk Power Corporation Nine Nile Point Nuclear Station P.O.

Box 63

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

.. P.O.

Box 126 Ly'coming, 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 Nine Nile 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 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 Mr. Martin J. McCormick, Jr.

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

Box 63

Lycoming, NY 13093

E VEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED LICENSE AMENDMENT TO ALLOW USE OF RANGE 10 0 INTERMEDIATE RANGE MONITORS IRMs AT NINE MILE POINT NUCLEAR STATION UNIT NO.

1 In the licensee submittal, reference is made to NEDC-31336, "GE Instrumentation Setpoint Methodology."

Please state the relevant sections and provide a copy of this document.

Although NEDC-31336 is an important reference

document, the topical report is not to be used by any plant to validate its individual setpoints.

Each plant must provide its own plant unique analysis for the setpoints.

Provide the analyses or calculations in support of the changed setpoints in the Technical Specifications amendment.

Provide the analysis and the graphical display of the instrument as-found drift data collected from the plant-specific installed source range monitors (SRHs) and IRHs in support of the extended surveillance intervals.

Indicate the time span over which these as-found drift data were collected.

What is the existing observed overlap of your average power range monitors (APRM) and IRMA What will be the number of decades on IRH range 107 Provide surveillance acceptance criteria on the overlap between APRH and IRH.

Clarify setpoints on page 227.

What are the reasons for changing the expression in percentage of full scale to fraction of division of full scale7 Encl osure

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