ML022180201
| ML022180201 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 08/05/2002 |
| From: | Tam P NRC/NRR/DLPM/LPD1 |
| To: | Conway J Nine Mile Point |
| Tam P | |
| References | |
| TAC MA3208 | |
| Download: ML022180201 (7) | |
Text
SECTION 3.2.0 Reactor Coolant System Limiting Condition for Operation 3.2.1 Reactor Vessel Heatup and Cooldown Rates 3.2.2 Minimum Reactor Vessel Temperature for Pressurization 3.2.3 Coolant Chemistry 3.2.4 Coolant Activity 3.2.5 Leakage Rate 3.2.6 (Deleted) 3.2.7 Isolation Valves 3.2.8 Safety Valves 3.2.9 Solenoid-Actuated Pressure Relief Valves 3.3.0 Primary Containment Limiting Condition for Operation 3.3.1 Oxygen Concentration 3.3.2 Pressure and Suppression Chamber Water Temperature and Level 3.3.3 Leakage Rate flFSrCRIPTION PG80 Surveillance Requirements 4.2.2 Minimum Reactor Vessel Temperature for Pressurization 4.2.3 Coolant Chemistry 4.2.4 Coolant Activity 4.2.5 Leakage Rate 4.2.6 (Deleted) 4.2.7 Isolation Valves 4.2.8 Safety Valves 4.2.9 Solenoid-Actuated Pressure Relief Valves Surveillance Requirements 4.3.1 Oxygen Concentration 4.3.2 Pressure and Suppression Chamber Water Temperature and Level 4.3.3 Leakage Rate AMENDMENT NO. W 173 81 83 96 99 101 105 108 118 120 123 124 127 131 PAGE rII:RGRIPTION
SECTION DESCRIPTION PAGE 6.10 Record Retention 370 6.11 Radiation Protection Program 371 6.12 High Radiation Area 371 6.13 Fire Protection Inspection 373 6.14 Systems Integrity 373 6.15 Iodine Monitoring 373 6.16 10 CFR 50 Appendix J Testing Program Plan 373 6.17 Inservice Testing Program 374 AMENDMENT NO.
173
AMENDMENT NO. W 173 (Deleted) 105
(Deleted)
AMENDMENT NO. W 173
i mriMit-z rOniunITION FOR OPERATION SRELAC EURMN 3.2.7 REACTOR COOLANT SYSTEM ISOLATION VALVES Applicability:
Applies to the operating status of the system of isolation valves on lines connected to the reactor coolant system.
Objective:
To assure the capability of the reactor coolant system isolation valves to minimize reactor coolant loss in the event of a rupture of a line connected to the nuclear steam supply system.
Specification:
- a.
During power operating conditions whenever the reactor head is on, all reactor coolant system isolation valves on lines connected to the reactor coolant system shall be operable except as specified in "b" below.
- b.
In the event any isolation valve becomes inoperable the system shall be considered operable provided 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.
4.2.7 REACTOR COOLANT SYSTEM ISOLATION VALVES Applcability:
Applies to the periodic testing requirement for the reactor coolant system isolation valves.
Obiective:
To assure the capability of the reactor coolant system isolation valves to minimize reactor coolant loss in the event of a rupture of a line connected to the nuclear steam supply system.
Specification:
The reactor coolant system isolation valves surveillance shall be performed as indicated below.
- a.
At least once per operating cycle the operable automatically initiated power-operated isolation valves shall be tested for automatic initiation and closure times.
- b.
Additional surveillances shall be performed as required by Specification 6.1 7.
AMENDMENT NO.
i',
W, 173 SURVEILLANCE REQUIREMENT 108
6.9.3 Special Reports Special reports shall be submitted in accordance with 10 CFR 50.4 Regional Office within the time period specified for each report. These reports shall be submitted covering the activities identified below pursuant to the requirements of the applicable reference specification:
- a.
Reactor Vessel Material Surveillance Specimen Examination, Specification 4.2.2(b) (12 months).
- b.
(Deleted)
- c.
(Deleted)
- d.
(Deleted)
- e.
(Deleted)
- f.
(Deleted)
- g.
Sealed Source Leakage In Excess Of Limits, Specification 3.6.5.2 (Three months).
- h.
Calculate Dose from Liquid Effluent in Excess of Limits, Specification 3.6.1 5.a(2)(b) (30 days from the end of the affected calendar quarter).
- i.
Calculate Air Dose from Noble Gases Effluent in Excess of Limits, Specification 3.6.1 5.b(2)(b) (30 days from the end of the affected calendar quarter).
- j.
Calculate Dose from 1-131, H-3 and Radioactive Particulates with half lives greater than eight days in Excess of Limits, Specification 3.6.15.b(3)(b) (30 days from the end of the affected calendar quarter).
- k.
Calculated Doses from Uranium Fuel Cycle Source in Excess of Limits, Specification 3.6.15.d (30 days from the end of the affected calendar year).
I.
Inoperable Gaseous Radwaste Treatment System, Specification 3.6.1 6.b (30 days from the event).
- m.
Environmental Radiological Reports. With the level of radioactivity (as the result of plant effluents) in an environmental sampling medium exceeding the reporting level of Table 6.9.3-1, when averaged over any calendar quarter, in lieu of a Licensee Event Report, prepare and submit to the Commission within thirty (30) days from the end of the calendar quarter a special report identifying the cause(s) for exceeding the limits, and define the corrective action to be taken.
AMENDMENT NO. W, 173 368
- 4.
The combined Local Leak Rate Test (Type B & C Tests including airlocks) acceptance criteria is less than 0.6 La, calculated on a minimum pathway basis, at all times when containment integrity is required.
The provisions of Specification 4.0.1 do not apply to the test frequencies specified in the 10 CFR 50 Appendix J Testing Program Plan.
6.17 Inservice Testing Program This program provides controls for inservice testing of Quality Group A, B, and C pumps and valves.
- a.
Inservice testing of Quality Group A, B, and C pumps and valves shall be performed in accordance with requirements for American Society of Mechanical Engineers (ASME) Code Class 1, 2, and 3 components specified in Section Xl of the applicable ASME Boiler and Pressure Vessel Code Edition and Addenda, subject to the applicable provisions of 10CFR50.55a;
- b.
The provisions of Specification 4.0.1 are applicable to the normal and accelerated testing frequencies for performing inservice testing activities;
- c.
Nothing in the ASME Boiler and Pressure Vessel Code shall be construed to supersede the requirements of any Technical Specification.
374 AMENDMENT NO 4-1, 173