ML082420396

Technical Specifications, Issuance of Amendment Revised Operability Requirements for Reactor Coolant System Isolation Valves

ML082420396
Person / Time
Site:	Nine Mile Point
Issue date:	08/27/2008
From:	Plant Licensing Branch 1
To:
References
TAC MD6942
Download: ML082420396 (7)

Text

(3) Pursuant to the Act and 10 CFR Parts -30, 40, and 70 to receive, possess and use at any time any byproduct, source and special nuclear material as sealed neutron sources for reactor startup, sealed sources for reactor instrumentation and radiation monitoring equipment calibration, and as fission detectors in amounts as required; (4) Pursuant to the Act and 10. CFR Parts 30, 40 and.70, to receive, possess.

and use in amounts as required any byproduct, source or special nuclear material without restriction to chemical or physical form, for sample analysis or instrument and equipment calibration or associated with radioactive apparatus or components.

(5) Pursuant to the Act and 10 CFR Parts 30 and 70, to possess, but not separate, such byproduct and special nuclear materials as may be produced by the operation of the facility.

C. This renewed operating license shall be deemed to contain and is subject to the conditions specified in the following Commission regulations in 10 CFR Chapter Part 20, Section 30.34 of Part 30; Section 40.41 of Part 40; Section 50.54 and 50.59 of Part 50; and Section 70.32 of Part 70. This renewed license is subject to all applicable provisions of the Act and to the rules, regulations, and orders of the Commission now or hereafter in effect and is also subject to the additional conditions specified or incorporated below:

(1) Maximum Power Level.

The licensee is authorized to operate the facility at steady state reactor core power levels not in excess of 1850 megawatts (thermal).

(2) Technical Specifications The Technical Specifications contained in Appendix A, which is attached hereto, as revised through Amendment No. 197, is hereby incorporated into this license.. Nine Mile Point Nuclear Station, LLC shall operate the facility in accordance with the Technical Specifications.

(3) Deleted eRdntwd LiNns, NEo. DPR 63 Amendment No. 191, 192, 193, 194, 195, 197

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT 3.2.7 REACTOR COOLANT SYSTEM ISOLATION VALVES 4.2.7 REACTOR COOLANT SYSTEM ISOLATION VALVES Applicability: Applicability:

Applies to the operating status of the system of Applies to the periodic testing requirement for the isolation valves on lines connected to the reactor. reactor coolant system isolation valves.

coolant system.

Objective: Obiective:

To assure the capability of the reactor coolant system To assure the capability of the reactor coolant system isolation valves to minimize reactor coolant loss in the isolation valves to minimize reactor coolant loss in the event of a rupture of a line connected to the nuclear .event of a rupture of a line connected to the. nuclear steam supply system, and to minimize potential leakage steam supply system, and to limit potential leakage paths from the primary containment in the event of a loss- paths from the primary containment in the event ofa,:

of-coolant accident. loss-of-coolant accident.

Specification: Specification:

a. Whenever fuel is in the reactor vessel and the reactor The reactor coolant system isolation valves coolant temperature is greater than 212 0 F, all reactor surveillance shall be performed as indicated below..

coolant system isolation valves on lines connected to the reactor coolant system shall be operable except a.. At least once per operating cycle the operable:,

as specified in Specification 3.2.7.b below. automatically initiated power-operated isolation valves shall be tested for automatic initiation and

b. In the event any isolation valve becomes closure times.

inoperable whenever fuel is in the reactor vessel and the reactor coolant temperature is greater than b. Additional surveillances shall be performed as 2-12'F, the system shall be considered operable; required by. Specification 6.5.4.

provided that within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> at least one valve in each line having an inoperable valve is in the mode corresponding to the isolated condition, except as noted in Specification 3.1.1.e.

AMENDMENT NO.142145, 17-374-84. 197 108

LIMITING CONDITION FOR OPERATION SURVEILLANCE REQUIREMENT

c. If Specifications 3.2.7a and b above are not met, c. At least once per quarter the feedwater and initiate normal orderly shutdown within one hour main-steam line power-operated isolation valves and have reactor in the cold shutdown condition shall be exercised.by partial closure and within ten hours.

• subsequent reopening.

d. Whenever fuel is in the reactor vessel and the reactor d. At least once per plant cold shutdown the coolant temperature is less.than or equal to 2.12 0 F, feedwater and main steam line power-operated the isolation valves on the shutdown cooling system isolation valves shall be fully closed and lines connected to the reactor coolant system shall be

• reopened, unless this test has been performed operable except as specified in Specification 3.2.7.e within the previous.92 days..

below.

e. In the event any shutdown cooling system isolation valve becomes inoperable whenever fuel is. in the reactor vessel and the reactor coolant temperature is less than or equal to 212'F, the system shall be considered operable provided that, within 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />, at least one valve in each line having an inoperable valve is in the mode. corresponding to the isolated condition.

f. If Specifications 3.2.7.d and 3.2.7.e above are not met, either:.

(1) Immediately initiate action to suspend operations with a potential for draining the reactor vessel (OPDRVs); or (2) Immediately initiate action to restore the valve(s) to operable status.

AMENDMENT NO. -142. 197 109

TABLE 3.6.2b INSTRUMENTATION THAT INITIATES PRIMARY COOLANT SYSTEM OR CONTAINMENT ISOLATION Limiting Condition for Operation Minimum No. of Operable Instrument Reactor Mode Switch Minimum No. Channels per Position in Which of Tripped or Operable Function Must Be Parameter Operable Trip Systems Trip System Set Point Operable' 0 0.

"=

co 41 C Cu 4-'

C,, U) ~

PRIMARY COOLANT ISOLATION (Main Steam, Cleanup, and Shutdown Cooling)

(1) Low-Low Reactor Water Level (a) Main Steam and Cleanup 2 2() > 5 inches (i) x x (Indicator Scale)

(b) Shutdown Cooling 2(j) 2(00) *5 inches x x x x (Indicator Scale)

(2) Manual 2 1 x x x X MAIN-STEAM-LINE ISOLATION (3) High Steam Flow Main-Steam Line 2 2(f) < 105 psid x x AMENDMENT NO. 4-42, 197 205

TABLE 3.6.2b (cont'd)

INSTRUMENTATION THAT INITIATES, PRIMARY COOLANT SYSTEM OR CONTAINMENT ISOLATION Limitina Condition for Operation Minimum No. of Operable Instrument Reactor Mode Switch Minimum No. Channels per Position in Which of Tripped or Operable Function Must Be Parameter Operable Trip Systems Trip System Set Point Operable 0.

C-

.1~

(I)

Co CLEANUP SYSTEM ISOLATION (8) High Area Temperature 1 2(g) < 190OF .(i) x X,-.,

SHUTDOWN COOLING SYSTEM ISOLATION (9) High Area Temperature .1 1 <-170°F (i) x x CONTAINMENT ISOLATION (10) Low-Low Reactor Water *2 2(f) > 5 inches (c) x x (Indicator Scale)

AMENDMENT NO. 1.42, 197 207

TABLE 4.6.2b INSTRUMENTATION THAT INITIATES PRIMARY COOLANT SYSTEM OR CONTAINMENT ISOLATION Surveillance Requirement Instrument Instrument Channel Parameter Sensor Check Channel Test Calibration PRIMARY COOLANT ISOLATION (Main Steam, Cleanup and Shutdown Cooling)

(1) Low-Low Reactor Water Once/day Once per 3 months(d) Once per 3 months(d)

Level (2) Manual Once during each major refueling outage MAIN-STEAM-LINE ISOLATION (3) High Steam Flow Main- Once/day Once per.3 rnonths4 a) Once per 3 months(d)

Steam Line (4) Deleted (5) Low Reactor Pressure Once/day Once per 3 months(d) Once per 3 months(d)

AMENDMENT NO. 142-4, 197 209

NOTES FOR TABLES 3.6.2b and 4.6.2b (g). A channel may be placed in an inoperable status forup to 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> for required surveillances without placing the Trip System in tripped condition provided at least one Operable Instrument Channel in the same Trip System is monitoring that Parameter:

With the number of Operable channels one less than required by the Minimum Number of Operable Instrument Channels for the Operable. Trip System, either 1 Place the inoperable channel(s) in the tripped condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />..

or

2. Take the ACTION required by Specification 3.6.2a for that Parameter.

(h) Only applicable during startup mode while operating in IRM range 10.

(i) May be bypassed in the cold shutdown condition.

(j) In the cold shutdown and refueling conditions, only one Operable Trip System is required provided shutdown cooling system integrity is maintained. With one of the two required Operable Channels in the required Trip System not operable, place the inoperable channel in the tripped condition within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. Otherwise,. either:

1. Immediately initiate action to restore the channel to operable status.

or

2. Immediately initiate action to isolate the shutdown cooling system.

AMENDMENT NO. 142_183, 197 213