ML20199D280

Informs That on 981204,NMP Submitted Rev to TSs Bases for NMPNS Unit 1.Rev Update Bases for 3.6.2 & 4.6.2 Protective Instrumentation. Forwards Modified Pages for NMP Unit 1 TS Bases for Insertion Into TSs

ML20199D280
Person / Time
Site:	Nine Mile Point
Issue date:	01/12/1999
From:	Hood D NRC (Affiliation Not Assigned)
To:	Mueller J NIAGARA MOHAWK POWER CORP.
References
TAC-MA4399, NUDOCS 9901200058
Download: ML20199D280 (10)

Text

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anuary 12, 1999

. Mr. John H. Mu:ll:r Chi f NucinrOfficar Nirgira Mohlwk Pow:r Corporction Nine Mile Point Nuclear Station Operations Building, Second Floor P.O. Box 63 Lycoming, NY 13093

SUBJECT:

REVISION TO TECHNICAL SPECIFICATION BASES FOR NINE MILE POINT '

NUCLEAR STATION, UNIT NO.1 (TAC NO. MA4399)

Dear Mr. Mueller. I By letter dated December 4,1998, Niagara Mohawk Power Corporation (NMPC) submitted revisions to the Technical Specifications (TSs) Bases for Nine Mile Point Nuclear Station, Unit No.1 (NMP1). The revisions update the " Bases for 3.6.2 and 4.6.2 Protective Instrumentation" to (1) reflect the removal of the Condenser Low Vacuum scram function from the TSs and the plant design based upon prior License Amendment No. 37 and Modification N1-88-053, and (2) correct and clarify the information regarding a Reactor Protection System bypass feature.

The revisions also update the NMP1 TS " Bases for 3.6.3 and 4.6.3 Emergency Power Sources" to (1) reflect changes to the Emergency Diesel Generator (EDG) ratings, design basis load limits, and loading profiles that resulted from NMPC's previous reconstitution of the EDG design basis loading analysis, and (2) replace references to the Final Safety Analysis Report with their corresponding Updated Final Safety Analysis Report references.

The modified pages for the NMP1 TS Bases are enclosed, for insertion into the Technical Specifications.

If you have questions regarding this letter, contact me by phone at (301) 415-3049 or by electronic mail at dsh@nrc. gov. j 1

Sincerely, Original signed by:  ;

Darl S. Hood, Senior Project Manager I Project Directorate 1-1 Division of Reactor Projects - l/11 Office of Nuclear Reactor Regulation

]

Docket No. 50-220

Enclosure:

Bases Pages cc w/ encl: See next page DISTRIBUTION: See attached page ,, }

DOCUMENT NAME: G:\NMP1\LTRA4399.WPD To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure "E" = Copy with attachment / enclosure "N" = No copy 0FFICE PM:PDI 1 lE LA:PDI 1 ,g6 l D:PDI 1 n7L l l l l [

NAME DHood/tec K r (4 SLi t t le // " g'A SBaJwa M8 i'A DATE 01/,s /99 " ~' ' I 01/ f[199 /: 01/ /k/99 'N

'" 0'fficial Record Copy

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9901200058 990112 PDR ADOCK 05000220 P PDR Vy [7') q r * *

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e - Mr. John H. Mu;ll:r January 12, 1999 Chi;f Nuc!2:rOfficer l Nirgira Mohrwk Pow:r Corpor tion

_ Nine Mile Point Nuclear Station Operations Building, Second Floor P.O. Box 63 Lycoming, NY 13093

SUBJECT:

REVISION TO TECHNICAL SPECIFICATION BASES FOR NINE MILE POINT NUCLEAR STATION, UNIT NO.1 (TAC NO. MA4399)

Dear Mr. Mueller:

By letter dated December 4,1998, Niagara Mohawk Power Corporation (NMPC) submitted revisions to the Technical Specifications (TSs) Bases for Nine Mile Point Nuclear Station, Unit No.1 (NMP1). The revisions update the " Bases for 3.6.2 and 4.6.2 Pmter': Instrumentation" to (1) reflect the removal of the Condenser Low Vacuum scram function f. e TSs and the plant design based upon prior License Amendment No. 37 and Modification .1-88-053, and (2) correct and clarify the information regarding a Reactor Protection System bypass feature.

The revisions also update the NMP1 TS " Bases for 3.6.3 and 4.6.3 Emergency Power Sources" to (1) reflect changes to the Emergency Diesel Generator (EDG) ratings, design basis load limits, and loading profiles that resulted from NMPC's previous reconstitution of the EDG design basis loading analysis, and (2) replace references to the Final Safety Analysis Report with their corresponding Updated Final Safety Analysis Report references.

The modified pages for the NMP1 TS Bases are enclosed, for insertion into the Technical Specifications.

If you have questions regarding this letter, contact me by phone at (301) 415-3049 or by electronic mail at dsh@nrc. gov.

Sincerely, Original signed by:

Darl S. Hood, Senior Project Manager i Project Directorate I-1 Division of Reactor Projects - t/11 l

Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosure:

Bases Pages cc w/ encl. See next page DISTRIBUTION: See attached page DOCUMENT NAME: G:\NMP1\LTRA4399.WPD To receive a copy of this document, indicate in the box: "C" = Copy without attachment / enclosure

! *E" = Copy with attachment / enclosure "N" = No copy 0FFICE PM:PDI 1 lEl LA:PDI-1 , f i'Y l l D:PDI 1 M'k l I l l l mE Dsoodnce ua suttte rw ss.w. + &\

DATE 01/,pp/99 "'l 01/ !/M99 / 01// M 99 K

'" 0'fficial Record Copy l

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, *p ut:0 g 4 UNITED STATES

r j NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2055Hm1

% # Danuary 12, 1999 Mr. John H. Mueller  !

Chief Nuclear Officer Niagara Mohawk Power Corporation Nine Mile Point Nuclear Station Operations Building, Second Floor P.O. Box 63 Lycoming, NY 13093

SUBJECT:

REVISION TO TECHNICAL SPECIFICATION BASES FOR NINE MILE POINT ,

NUCLEAR STATION, UNIT NO.1 (TAC NO. MA4399) l l

Dear Mr. Mueller. l By letter dated December 4,1998, Niagara Mohawk Power Corporation (NMPC) submitted I revisions to the Technical Specifications (TSs) Bases for Nine Mile Point Nuclear Station, Unit No.1 (NMP1). The revisions update the " Bases for 3.6.2 and 4.6.2 Protective Instrumentation' "

to (1) reflect the removal of the Condenser Low Vacuum scram function from the TSs and the plant design based upon prior License Amendment No. 37 and Modification N1-88-053, and (2) correct and clarify the information regarding a Reactor Protection System bypass feature.

The revisions also update the NMP1 TS

• Bases for 3.6.3 and 4.6.3 Emergency Power Sources" to (1) reflect changes to the Emergency Diesel Generator (EDG) ratings, design basis load limits, and loading profiles that resulted from NMPC's previous reconstitution of the EDG design basis loading analysis, and (2) replace references to the Final Safety Analysis Report with their corresponding Updated Final Safety Analysis Report references.

The modified pages for the NMP1 TS Bases are endosed, for insertion into the Technical Specifications.

If you have questions regarding this letter, contact me by phone at (301) 415-3049 or by electronic mail at dsh@nrc. gov.

Sincerely, a s l' / M Dari S. Hood, Senior Project Manager p Project Directorate I-1 '

l Division of Reactor Projects - 1/11 t

Office of Nuclear Reactor Regulation Docket No. 50-220

Enclosure:

Bases Pages cc w/ encl: See next page l

l

i

.. .- . j DATED: January 12, 1999 i

l REVISION TO TECHNICAL SPECIFICATION BASES FOR NINE MILE POINT NUCLEAR STATION, UNIT NO.1 MP$i"3 PUBLIC

PDI-1 Reading l J. Zwolinski l S. Bajwa l- S. Little D. Hood OGC i G. Hill (2), T-5 C3 i W. Beckner i ACRS l C. Hehl, Region I i

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cc: Plant Service list t

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J DATED: January 12, 1999 REVISION TO TECHNICAL SPECIFICATION BASES FOR NINE MILE POINT NUCLEAR STATION, UNIT NO.1 Docket File PUBLIC PDI-1 Reading i J. Zwolinski S. Bajwa S. Little D. Hood 1 OGC j G. Hill (2), T-5 C3 '

W. Beckner ACRS C. Hehl, Region I cc: Plant Service list i

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John H. Mueller Nine Mile Point Nuclear Station Niagara Mohawk Power Corporation Unit No.1 cc:

Regional Administrator, Region i U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Resident inspector U.S. Nuclear Regulatory Commission P.O. Box 126 Lycoming, NY 13093 Charles Donaldson, Esquire Assistant Attorney General New York Department of Law 120 Broadway New York, NY 10271 Mr. Paul D. Eddy State of New York Department of Public Service Power Division, System Operations 3 Empire State Plaza Albany, NY 12223 Mr. F. William Valentino, President New York State Energy, Research, and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mark J. Wetterbahn, Esquire Winston & Strawn 1400 L Street, NW Washington, DC 20005-3502 Gary D. Wilson, Esquire <

Niagara Mohawk Power Corporation 300 Erie Boulevard West Syracuse, NY 13202 Supervisor Town of Scriba Route 8, Box 382 Oswego, NY 13126

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. 1 REVISED TECHNICAL SPECIFICATION BASES PAGE LIST Nine Mile Point Nuclear Station. Unit No.1 Replace the following pages of the Technical Specifications Bases with the attached pages.

The revised page contains verticallines in the page margin indicating the areas of change.

I Remove Insert 250 250 251 251 l

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T Enclosure i l

BASES FOR 3.6.2 AND 4.6.2 PROTECTIVE INSTRUMENTATION

s. The set points included in the tables are those used in the transient analysis and the accident analysis. The high flow set point for 6

the main steam line is 105 psi differential. This represents a flow of approximately 4.4x10 lb/hr. The high flow set point for the emergency cooling system supply line is s 11.5 psi differential. This represents a flow of approximately 9.8x10 5 lb/hr at rated conditions.

The automatic initiation signals for the emergency cooling systems have to be sustained for more than 12 seconds to cause opening of the return valves. If the signals last for less than 12 seconds, the emergency cooling system operating will not be automatically initiated.

The high level in the scram dischstge volume is provided to assure that there is still sufficient free volume in the discharge system to receive the control rod drives discharge. Following a scram, bypassing is permitted to allow draining of the discharge volume and resetting of the reactor protection system relays. Since all control rods are completely inserted following a scram and since the bypass of this particular scram initiates a control rod block, it is permissible to bypass this scram function. The scram trip associated with the shutdown position of the mode switch can be reset after 10 seconds.

The condenser low-low-low vacuum and the main steam line isolation valve position signals are bypassed in the startup and refuel l positions of the reactor mode switch when the reactor pressure is less than 600 psig. These are bypassed to allow warmup of the main steam lines and to provide a heat sink during startup. l 250 AMENDMENT NO. /dd,149

I BASES FOR 3.6.2 AND 4.6.2 PROTECTIVE INSTRUMENTATION l

The set points on the generator load rejection and turbine stop valve closure scram trips are set to anticipata and minimize the  ;

consequences of turbine trip with failure of the turbine bypass system as described in the bases for Specification 2.1.2. Since the severity cf the transients is dependent on the reactor operating power level, bypassing of the scrams below the specified power levelis permissible.

Although the operator will set the setpoints et the values indicated in Tables 3.6.2.a-1, the actual values of the various set points can differ cppreciably from the value the operator is attempting to set. The deviations include inherent instrument error, operator setting error and drift of the set point. These errors are compensated for in the transient analyses by conservatism in the controlling parameter assumptions cs discussed in the bases for Specification 2.1.2. The deviations associated with the set points for the safety systems used to mitigate .

cccidents have negligible effect on the initiation of these systems. These safety systems have initiation times which are orders of m:gnitude greater than the difference in time between reaching the nominal set point and the worst set point due to error. The maximum cllowable set point deviations are listed below:

Neutron Flux i APRM Scram,12.3% of rated neutron flux (analytical limit is 120% of rated flux)

APRM Rod Block,12.3% of rated neutron flux (analytical limit is 110% of rated flux)  ;

IRM, *2.5% of rated neutron flux i The APRM downscale rod block setpoint has been derived based on GE setpoint methodology as outlined in NEDC-31336, "GE instrumentation Setpoint Methodology." In this methodology, the setpoint is defined as three values, Nominal Trip Setpoint, Allowable Value, and Analytical Limit. Table 3.6.2g shows the nominal trip setpoints. The corresponding allowable value is as follows.

APRM Downscale Rod Block, allowable value'is hl4.24/125] divisions of full scale Recirculation Flow Upscale,

• 1.6% of rated recirculation flow (analytical limit is 107.1% of rated flow)

Recirculation Flow Comparator,12.09% of rated recirculation flow (analytical limit is 10% flow differentiell i

RIactor Pressure,

• 15.8 psig  !

Containment Pressure, *0.053 psig R: actor Water Level, *2.6 inches of water ,

i Main Steam Line isolation Valve Fosition,

• 2.5% of stem position ,

i Scram Discharge Volume, +0 and -1 gallon I!

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AMENDMENT NO. //I,153 251

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e BASES FOR 3.6.3 AND 4.6.3 EMERGENCY POWER SOURCES I

i Other than the Station turbine generator, the Station is supplied by four independent sources of a-c power; two 115 kv transmission lines, and two diesel-generators. Any one of the required power sources will provide the power required for a LOCA. Engineering calculations show that a LOCA concurrent with a loss of offsite power and the single failure of one of the diesel-generators results in a loading for the remaining diesel-generator that is below the unit's 2000 hour0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> / year rating. This loadmg is greater than that required during a Station shutdown condition. The monthly test run paralleled with the system is based on the manufacturer's recommendation for these units in this type of service. The testing during operating cycle will simulate the accident conditions under which operation of the diesel-generators is r; quired. The major equipment comprising the maximum diesel-generator loading is given in Figure IX-6*.

Aa mentioned above, a single diesel-generator is capable of providing the required power to equipment following a LOCA. Two fuel oif l Etorage tanks are provided with piping interties to permit supplying either diesel-generator. A two-day supply will provide adequate time to arrange for fuel makeup if needed. The full capacity of both tanks will hold a four-day supply.

i it has been demonstrated in Section XV.B.3.23' that even with complete d-c loss the reactor can be safely isolated and the emergency l

cooling system will be operative with makeup water to the emergency cooling system shells maintained manually. Having at least one d-c battery available will permit: automatic makeup to the shells rather than manual, closing of the d-c actuated isolation valve on alllines from the primary system and the suppression chamber, maintenance of electrical switching functions in the Station and providmg emergency lighting and communications power.

A battery system shall have a minimum of 106 volts at the battery terminals to be considered operable.

'FSAR 258 AMENDMENT NO.142

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