ML081560633

Tech Spec Pages for Amendment No. 125 Implementation of Alternative Radiological Source Term

ML081560633
Person / Time
Site:	Nine Mile Point
Issue date:	05/29/2008
From:	NRC/NRR/ADRO/DORL/LPLI-1
To:
Guzman R, NRR/DORL, 415-1030
References
TAC MD5758
Download: ML081560633 (11)

Text

(1) Maximum Power Level Nine Mile Point Nuclear Station, LLC, is authorized to operate the facility at reactor core power levels not in excess of 3467 megawatts thermal (100 percent rated power) in accordance with the conditions specified herein.

(2) Technical Specifications and Environmental Protection Plan The Technical Specifications contained In Appendix A and the Environmental Protection Plan contained In Appendix B, both of which are attached hereto, as revised through Amendment No. 125 are hereby incorporated into this license. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications and the Environmental Protection Plan.

(3) Fuel Storage and Handling (Section 9.1, SSER 4)*

a. Fuel assemblies, when stored in their shipping containers, shall be stacked no more than three containers high.

b. When not in the reactor vessel, no more than three fuel assemblies shall be allowed outside of their shipping containers or Storage racks in the New Fuel Vault or Spent Fuel Storage Facility.

c. The above three fuel assemblies shall maintain a minimum edge-to-edge spacing of twelve (12) inches from the shipping container array and approved storage rack locations.

d. The New Fuel Storage Vault shall have no more than ten fresh fuel assemblies uncovered at any one time.

(4) Turbine System Maintenance Program (Section 3.5,1.3.10, SER)

The operating licensee shall submit for NRC approval by October 31, 1989, a turbine system maintenance program based on the manufacturer's calculations of missile generation probabilities.

(Submitted by NMPC letter dated October 30, 1989, from C.D. Terry and approved by NRC letter dated March 15, 1990, from Robert Martin to Mr. Lawrence Burkhardt, Ill).

The parenthetical notation following the title of many license conditions denotes the section of the Safety Evaluation Report (SER) and/or its supplements wherein the license condition is discussed.

Renewed License No. NPF-69 Amendment No. 125

Definitions 1.1 1.1 Definitions (continued)

CHANNEL FUNCTIONAL TEST A CHANNEL FUNCTIONAL TEST shall be the injection of a simulated or actual signal into the channel as close to the sensor as practicable to verify OPERABILITY, including required alarm, interlock, display, and trip functions, and channel failure trips. The CHANNEL FUNCTIONAL TEST may be performed by means of any series of sequential, overlapping, or total channel steps so that the entire channel is tested.

CORE ALTERATION CORE ALTERATION shall be the movement of any fuel, sources, .or reactivity control components, within the reactor vessel with the vessel head removed and fuel-in the-vessel. The following exceptions are not considered to be CORE ALTERATIONS:

a. Movement of source range monitors, local power range monitors, intermediate range monitors, traversing incore probes, or special movable detectors (including undervessel replacement);

and

b. Control rod movement, provided there are no fuel assemblies in the associated core cell.

Suspension of CORE ALTERATIONS shall not preclude completion of movement of a component to a safe position.

CORE OPERATING LIMITS The COLR is the unit specific document that REPORT (COLR) provides cycle specific parameter limits for the current reload cycle. These cycle specific limits shall be determined for each reload cycle in accordance with Specification 5.6.5. Plant operation within these limits is addressed in individual Specifications.

DOSE EQUIVALENT 1-131 DOSE EQUIVALENT 1-131 shall be that concentration of 1-131 (microcuries/gram) that alone would produce the same dose as the quantity and isotopic mixture of 1-131, 1-132, 1-133,1-134, and 1-135 actually present. The dose conversion factors used for this calculation shall be the Committed Effective Dose Equivalent dose conversion" factors listed in Table 2.1 of Federal Guidance Report No. 11, EPA, "Limiting Values of Radionuclide Intake and Air Concentration and Dose Conversion Factors for Inhalation, Submersion, and Ingestion," 1988.

(continued)

NMP2 1 .1-2 Amendment 94, 125

Definitions 1.1 1.1 Definitions (continued)

EMERGENCY CORE COOLING The ECCS RESPONSE TIME shall be that time interval SYSTEM (ECCS) RESPONSE from when the monitored parameter exceeds its ECCS TIME initiation setpoint at the channel sensor until the ECCS equipment is capable of performing its safety function (i.e., the valves travel to their required positions, pump discharge pressures reach their required values, etc.).- Times shall include diesel generator starting and sequence loading delays, where applicable. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

END OF CYCLE The .EOC-RPT SYSTEM RESPONSE TIME shall be that RECIRCULATION PUMP TRIP time interval from initial movement of the (EOC-RPT) SYSTEM RESPONSE associated turbine stop valves or turbine control TIME valves to complete suppression of the electric arc between the fully open contacts of the recirculation pump circuit breaker. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

ISOLATION SYSTEM The ISOLATION SYSTEM RESPONSE TIME shall be that RESPONSE TIME time interval from when the monitored parameter exceeds its isolation initiation setpoint at the channel sensor until the isolation valves travel to their required positions. The response time may be measured by means of any series of sequential, overlapping, or total steps so that the entire response time is measured.

LEAKAGE LEAKAGE shall be:

a. Identified LEAKAGE

1. LEAKAGE into the drywell such as that from pump seals or valve packing, that is captured and conducted to a sump or collecting tank; or (continued)

NMP2 1.1-3 Amendment 91-, 125

SLC System 3.1.7 3.1 REACTIVITY CONTROL SYSTEMS 3.1.7 Standby Liquid Control (SLC) System LCO 3.1.7 Two SLC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, and 3. I ý ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SLC subsystem A.1 Restore SLC subsystem 7 days inoperable. to OPERABLE status.

B. Two SLC subsystems B.1 Restore one SLC 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> inoperable. subsystem to OPERABLE status.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> associated Completion Time not met. AND C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.1.7.1 Verify available volume of sodium 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> pentaborate solution is within the limits of Figure 3.1.7-1.

(continued)

NMP2 . 1.-7-I A me n* 94, 1255, APmnd

CREF System Instrumentation 3.3.7.1 Table 3.3.7.1-1 (page 1 of 1)

Control Room Envelope Filtration System Instrumentation APPLICABLE CONDITIONS MODES OR REQUIRED REFERENCED OTHER CHANNELS FROM SPECIFIED PER TRIP REQUIRED SURVEILLANCE ALLOWABLE FUNCTION CONDITIONS SYSTEM ACTION A. 1 REQUIREMENTS VALUE

1. Reactor Vessel Water 1.2,3, 2 B SR 3.3.7.1.1 Ž101.8 inches Level - Low Low, Level 2 SR 3.3.7.1.2 (a)' SR 3.3.7.1.3 SR 3.3.7.1.4 SR 3.3.7.1.5

2. Drywell Pressure - High 1,2,3 2 C SR 3.3.7.1.1 *1.88 psig SR 3.3.7.1.2 SR 3.3.7.1.3 SR 3.3.7.1.4 SR 3.3.7.1.5

2. Main Control-Room. 1,2,3, 2 B SR 33.7.1.1 s 5.92 x 10a' Ventilation Radiation SR 3.3.7.1.2 pCi/cc Monitor - High (a),(b) SR 3.3.7.1.4 SR 3.3.7.1.5 (a) During operations with a potential for draining the reactor vessel.

(b) During movement of recently irradiated fuel assemblies in the secondary containment.

NMVP2 .3.3.7. 1-4 Amendment 94, 125,

CREF System 3.7.2 3.7 PLANT SYSTEMS 3.7.2 , Control Room Envelope Filtration (CREF) System LCO 3.7.2 Two CREF subsystems shall be OPERABLE.

NOTE---

The control room envelope boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CREF subsystem A.1 Restore CREF 7 days inoperable, subsystem(s) to OPERABLE status.

OR Two CREF subsystems inoperable with safety function maintained.

B. Two CREF subsystems B.1 Restore control room 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable due to inoperable envelope boundary to control room envelope OPERABLE status.

boundary in MODES 1, 2, and 3.

C. Required Action and C.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Associated Completion Time of Condition A or B AND not met in MODE 1, 2, or 3. C.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)

NMP2 3.7.2-1 Amendment 9----, 125

CREF System 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME D. Required Action and associated Completion Time LCO 3.0.3 is not applicable.

of Condition A not met during movement of recently irradiated fuel assemblies in D. 1 Place OPERABLE Immediately the secondary containment components of CREF or during OPDRVs. subsystem(s) equivalent to a single CREF subsystem in emergency pressurization mode.

OR D.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.

AND D.2.2 Initiate action to suspend Immediately OPDRVs.

E. Two CREF subsystems E.1 Enter LCO 3.0.3. Immediately inoperable with safety function not maintained in MODE 1, 2, or 3 for reasons other than Condition B.

(continued)

NMP2/ 3.7.2-2 Amendment 94-,97, 125

CREF System 3.7.2 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Two CREF subsystems ....-NOTE inoperable with safety LCO 3.0.3 is not applicable.

function not maintained during movement of recently irradiated fuel assemblies in F..I Suspend movement of Immediately I

the secondary containment recently irradiated or during OPDRVs. fuel assemblies in the secondary containment.

AND F.2 Initiate action to suspend Immediately OPDRVs.

SURVEILLANCE REQUIREMENTS _

SURVEILLANCE FREQUENCY SR 3.7.2.1 Operate each CREF subsystem for >_1 continuous 31 days hour.

SR 3.7.2.2 Perform required CREF System filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).

SR 3.7.2.3 Verify each CREF subsystem actuates on an actual 24 months or simulated initiation signal.

(continued)

NMP2 30.7.2-3 Amendment 94,-9, :7, 125

Control Room Envelope AC System 3.7.3 3.7 PLANT SYSTEMS 3.7.3 Control Room Elnvelope Air Conditioning (AC) System LCO 3.7.3 Two cohtrol room envelope AC subsystems shall be OPERABLE.

APPLICABILITY: MODES 1, 2, .and 3,

• During movement of recently irradiated fuel assemblies in the secondary. containment, During operations with a potential for draining the reactor vessel (OPDRVs).

. I ACTIONS CONDITION REQUIRED ACTION COIMIPLETION TIME A. One control room A. 1 Restore control room 30 days envelope AC subsystem envelope AC inoperable, subsystem(s) to OPERABLE status:

OR Two control room envelope AC subsystems inoperable with'safety function maintained.

B. Required Action and B.1 Be in MODE 3. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> Associated Completion Time of Condition A . AND not met in MODE 1, 2, or 3. B.2 Be in MODE 4. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> (continued)

NMP2 3.7.3-i Amendment 94, 125

Control Room Envelope AC System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and

.associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement of recently C. 1 Place OPERABLE Immediately irradiated fuel assemblies components of control in the secondary room envelope AC containment or during subsystem(s)

OPDRVs. equivalent to a single control room envelope AC subsystem in operation.

OR C.2.1 Suspend movement of Immediately recently irradiated fuel assemblies in the secondary containment.

AND C2.2 Initiate action to Immediately suspend OPDRVs.

D. Two control room D.1 Enter LCO 3.0.3. Immediately envelope AC subsystems inoperable with safety function not maintained in MODE 1, 2, or3.

(continued)

NMP2 11) -7 n-11 0 , I . 1; 4 Amendmen*t +, 125

Control Room Envelope AC System 3.7.3 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME E. Two control room envelope AC subsystems LCO 3.0.3 is not applicable.

inoperable with safety function not maintained during E. 1 Suspend movement of Immediately movement of recently . recently irradiated fuel irradiated fuel assemblies assemblies in the in the secondary secondary containment or during containment.

OPDRVs.

AND E.2 Initiate action to Immediately suspend OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.3.1 Verify each control room envelope AC 24 months subsystem has the capability to remove the assumed heat load.

NMP2 3.7.3-3 Amendment CU 1 25