ML18038A666

Revised Pages to Tech Specs Re Triple Low Reactor Water Level Setpoint.Changes Involve Replacing 147.1 Inch Indicator Scale w/-10 Inch Indicator Scale

ML18038A666
Person / Time
Site:	Nine Mile Point
Issue date:	04/02/1984
From:	NIAGARA MOHAWK POWER CORP.
To:
Shared Package
ML17054A598	List: ML17054A597 ML18038A666
References
NUDOCS 8404060321
Download: ML18038A666 (16)

Text

SAFETY LIMIT LIMITING SAFETY SYSTEM SETTING

c. The neutron flux shall not exceed its d. The reactor water low level scram trip scram setting for longer than 1.5 seconds setting shall be no lower than -12 inches as indicated by the process computer. (53 inches indicator scale) elative to When the process computer is out of the minimum normal water level (302'9").

service, a safety limit violation shall be assumed if the neutron flux exceeds the e. The reactor water low-low level setting scram setting and control rod scram does for core spray initiation shall be no less not occur. than -5 feet (5 inches indicator scale) relative to the minimum normal water level To ensure that the Safety Limit (Elevation 302'9").

established in Specifications 2.1.la and 2.l.lb is not exceeded, each required f. ~

The flow biased APRM rod block trip scram shall be initiated by its expected settings shall be less than or equal to scram signal. The Safety Limit shall be that shown in Figure 2.l.l.

assumed to be exceeded when scram is accomplished by a means other than the expected scram signal.

d. Whenever the reactor is in the shutdown condition with irradiated fuel in the reactor vessel, the water level shall not be more than 6 feet, 3 inches (-10 inches indicator scale) below minimum normal water level (Elevation 302'9") except as specifed in "e" below.

e. For the purpose of performing major maintenance (not to exceed 12 weeks in duration) on the reactor vessel; the reactor water level may be lowered the minimum normal water leve) 9'elow (Elevation 302'9"). Whenever the reactor

.water level is to be lowered below the low-low-low level setpoint redundant instrumentation will be provided to monitor the reactor water level.

840406032i 840402 PDR ADOCK 05000220 P PDR

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BASES FOR 2.1.1 FUEL CLADDING SAFETY LIMIT During periods when the reactor is shut down, consideration must also be given to water level requirements, due to the effect of decay heat. If reactor water level should drop below the top of the active fuel during this time, the ability to cool the core is reduced. This reduction in core cooling capability could lead to elevated cladding temperatures and clad perforation. The core will be cooled sufficiently to prevent clad melting should the water level be reduced to two-thirds of the core height.

The lowest point at which the reactor water level can normally be monitored is approximately 7 feet 11 inches below minimum normal water level or 4 feet 8 inches above the top of the active fuel. This is the location of the reactor vessel tap for the low-low-low water level instrumentation. The actual low-low-low water level trip point is 6 feet 3 inches (-10 inches indicator scale) below minimum norma) water level (Elevation 302'-9"). The 20 inch difference resulted from an evaluation of the recomnendations contained in General Electric Service Information Letter 299 "High Drywell Temperature Effect on Reactor Vessel Water Level Instrumentation." The low-low-low water level trip point was raised 20 inches to conservatively account for possible differences in actual to indicated water level due to potentially high drywell temperatures. The safety limit has been established here to provide a point which can be monitored and also can provide adequate margin. However, for performing major maintenance as specified in Specification 2.1. l.e, redundant instrumentation will be provided for monitoring reactor water level below the low-low-low water level set point. (For example, by installing temporary instrument lines and reference points to redundant level transmitters so that the reactor water level may he monitored over the required range.) In addition written procedures, which identify all the valves which have the potential of lowering the water level inadvertently, are established to prevent their operation during the major maintenance which requires the water level to he below the low-low level set point.

The thermal power transient resulting when a scram is accomplished other than by the expected scram signal (e.g.,

scram from neutron flux following closure of the main turbine stop valves) does not necessarily cause fuel damage.

However, for this specification a safety limit violation wi]l be assumed when a scram is only accomplished by means of a backup feature of the plant design. The concept of nqt approaching a safety limit provided scram signals are operable is supported by the extensive plant safety analysis.

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REFERENCES FOR BASES 2.1.1 AND 2.1.2 FUEL CLADDING (1) General Electric BHR Thermal Analysis Basis (GETAB) Data, Correlation and Design Application, NEDO-10958 and NE DE-10958.

(2) Linford, R. B., "Analytical Methods of Plant Transient Evaluations for the General Electric Boiling plater Reactor," NED0-10801, February 1973.

(3) FSAR, Volume II, Appendix E.

(4) FSAR, Second Supplement.

(5) FSAR, Volume II, Appendix E.

(6) FSAR, Second Supplement.

(7) Letters, Peter A. Horr is, Director of Reactor Licensing, USAEC, to John E. Logan, Vice-President, Jersey Central Power and Light Company, dated November 22, 1967 and January 9, 1968.

(8) Technical Supplement to Petition to Increase Power Level, dated April 1970.

(9) Letter, T. J. Brosnan, Niagara Mohawk Power Corporation, to Peter A. Morris, Division of Reactor Licensing, USAEC, dated February 28, 1972.

(10) Letter, Philip D. Raymond, Niagara Mohawk Power Corporation, to A. Giambusso, USAEC, dated October 15, 1973.-

(ll) Nine Mile Point Nuclear Power Station Unit 1 Load Line Limit Analysis, NEDO 24012, May, 1977.

(12) Licensing Topical Report General Electric Boiling Mater Reactor Generic Reload Fuel Application, NEOE-24011-P-A, August, 1978.

(13) Nine Mile Point Nuclear Power Station UJ)it 1, Extended Load Line Limit Analysis, License A)))end)vent Submittal (Cycle 6), NED0-24185, April 1979.

(14) General Electric SIL 299 "High Oryuel1 Temperature Effect on Reactor Vessel Water Level Instrusientation."

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LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT c~ If a redundant component in each of the core spray systems becomes inoperable, both systems shall be considered operable provided that the .component is returned to an operable condition within 7 days and the additional surveillance required is performed.

d. If a core spray system becomes inoperable d. Core spray header < P instrumentation and all the components are operable in the other system, the reactor may remain in check Once/day operation for a period not to exceed 7 calibrate Once/3 months days. test Once/3 months

e. If Specifications a, b, c and d are not met, e. Surveillance with Inoperable Components a normal orderly shutdown shall be initiated within one hour and the reactor shall be in llhen a component or system becomes the cold shutdown condition within ten inoperable its redundant component or system hours. shall be demonstrated to be operable immediately and daily thereafter.

If both core spray systems become inoperable the reactor shall be in the cold shutdown f. Surveillance during control rod 'drive condition within ten hours and no work maintenance which is simultaneous with the (except as specified in "f" and "h" below) suppression chamber unwatered shall include shall be performed on the reactor or its at least hourly checks that the conditions connected systems which could result in listed in 3.1.4f are met.

lowering the reactor water level to more than six feet, three inches below minimum normal water level (-10 inches indicator scale).

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREf1ENT

h. For the purpose of performing major maintenance (not to exceed 12 weeks in duration) on the reactor vessel, the reactor water level may be lowered to 9'elow the minimum normal water level (elevation 302'9"). Whenever the reactor water level is to be lowered below the low-.low-low level set point redundant isntrumentation will be provided to monitor the reactor water level and written procedures will be developed and followed whenever the reactor water level is lowered below the low-low level set point.

The procedures will define the valves that will be used to lower the vessel water level. All other vaves that have the potential of lowering the vessel water level will be identified by valve number in the procedures and these valves will be red tagged to preclude their operation during the major maintenance with the water level below the low-low level set point.

During the period of major maintenance requiring lowering the water level to more than 6 feet, 3 inches below minimum normal water level (-10 inches indicator scale),

either both Core Spray Systems must be operable or, if one Core Spray System is inoperable because of the maintenance, all of the redundant components of the other Core Spray System must be operable.

53a

BASES FOR 3.1.5 AND 4.1.5 SOLENOID-ACTUATED PRESSURE RELIEF VALVES Pressure Bl owdown In the event of a small line break, substantial coolant loss could occur from the reactor vessel while it was stil I at relatively high pressures. A pressure blowdown system is provided which in conjunction with the core spray system will prevent significant fuel damage for all sized line breaks (Appendix E-11.2.0*).

Operation of three solenoid-actuated pressure relief valves is sufficient to depressurize the primary system to 110 psig which wi 11 permit full flow of the core spray system within required time limits (Appendix E-11.2~). Requiring

-'all six of the relief valves to be operable, therefore, provides twice the minimum number required. Prior to or following refueling at low reactor pressure, each v'alve will be <aanually opened to verify valve operability. The malfunction analysis (Section II.XV, "Technica'I Supplement to Petition to Increase Power Level," <late>i 4

Minimum No. of Minimum No. Operable Instrument Reactor Mode Switch of Tripped or Channels per Position in Which Operable Operable Function Must Be Parameter ~Tri Systems T~ri System Set-Point Operable INITIATION (1) a. Low-Low-Low Reactor Water (a) (a) ~ -10 inches*

2 2 (b) (b) x Level ( Indicator scale)

b. High Orywell 2 (a) < 3.5 psig (b) (b) x Pressure

• greater than ( >) means less negative 213