ML050350079
| ML050350079 | |
| Person / Time | |
|---|---|
| Site: | Monticello  |
| Issue date: | 01/28/2005 |
| From: | NRC/NRR/DLPM |
| To: | |
| Padovan L | |
| Shared Package | |
| ML050350094 | List: |
| References | |
| TAC MC1899 | |
| Download: ML050350079 (7) | |
Text
Table 3.2.3 Continued Instrumentation That Initiates Rod Block Notes:
'Required conditions when minimum conditions for operation are not satisfied.
A. Reactor in Shutdown mode.
B. No rod withdrawals permitted while in Refuel or Startup mode.
C. Reactor in Run mode.
D. No rod withdrawals permitted while in the Run mode.
E. Power on IRM range or below and reactor in Startup, Refuel, or Shutdown mode.
"Allowable Bypass Conditions
- a. SRM Detector-not-fully-inserted rod block may be bypassed when the SRM channel count rate is 2100 cps or when all IRM range switches are above Position 2.
- b. IRM Downscale rod block may be bypassed when the IRM range switch is in the lowest range position.
- c. (deleted)
3.214.2 a-Amendment No. 2-9 141
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION .1. 4.0 SURVEILLANCE REQUIREMENTS 3.7 CONTAINMENT SYSTEMS 4.7 CONTAINMENT SYSTEMS Applicability: Applicability:
Applies to the operating status of the primary and secondary Applies to the primary and secondary containment integrity.
containment systems.
Objective: Objective:
To assure the integrity of the primary and secondary To verify the integrity of the primary and secondary containment systems. containment.
Specification: Specification:
A. Primary Containment. A. Primary Containment
- 1. Suppression Pool Volume and Temperature 1. Suppression Pool Volume and Temperature When irradiated fuel is in the reactor vessel and either the reactor water temperature is greater than a. The suppression chamber water temperature 212'F or work is being done which has the potential shall be checked once per day.
to drain the vessel, the following requirements shall be met, except as permitted by Specification b. Whenever there is indication of relief valve 3.5.E.2: operation which adds heat to the suppression pool, the pool temperature shall be continually
- a. Water temperature during normal operating monitored and also observed and logged every shall be < 900F.
5 minutes until the heat addition is terminated.
- b. Water temperature during test operation which adds heat to the suppression pool shall be c. A visual inspection of the suppression chamber
- 1000 F and shall not be > 90'F for more than interior including water line regions and the 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. interior painted surfaces above the water line
- c. If the suppression chamber water temperature shall be made at each refueling outage.
is > 1100F, the reactor shall be scrammed immediately. Power operation shall not be resumed until the pool temperature is s900F.
3.7/4.7 56 Amendment No. 63.93, 141
3.0 LIMITING CONDITIONS FOR OPERATION l4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 1. 4.0 SURVEILLANCE REQUIREMENTS
- 2. Primary Containment Integrity 2. Primary Containment Integrity
- a. (1) Primary Containment Integrity as defined in a. Perform required visual examinations and Section 1, shall be maintained at all times leakage rate testing except for primary when the reactor is critical or when the containment air lock testing, in accordance with reactor water temperature is above 2120 F the Primary Containment Leakage Rate Testing and fuel is in the reactor vessel, except as Program.
specified in 3.7.A.2.a.(2), 3.7.A.2.a.(3) or I 3.7.D.
(2) Primary Containment Integrity is not required when performing low power physics tests at atmospheric pressure during or after refueling at power levels not to exceed 5 MW(t).
(3) Primary Containment Integrity is not required when performing reactor vessel hydrostatic or leakage tests with the reactor not critical.
(4) If requirements of 3.7.A.2.a.(1) cannot be met, restore Primary Containment Integrity within one hour or be in at least Hot Shutdown within the next 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and Cold Shutdown within the following 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.7/4.7 -1458- 141 Amendment No. 30, 55, 60, 95, 107, 132
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION + 4.0 SURVEILLANCE REQUIREMENTS
- 3. Pressure Suppression Chamber - Reactor Building 3. Pressure Suppression Chamber - Reactor Building Vacuum Breakers Vacuum Breakers
- a. Except as specified in 3.7.A.3.b below, two a. The pressure suppression chamber-reactor pressure suppression chamber-reactor building building vacuum breakers and associated vacuum breakers shall be operable at all times instrumentation including set point shall be when the primary containment integrity is checked for proper operation every three required. The set point of the differential months.
pressure instrumentation which actuates the pressure suppression chamber-reactor building I vacuum breakers shall be <0.5 psi.
- b. From and after the date that one of the pressure suppression chamber-reactor building vacuum breakers is made or found to be inoperable for any reason, reactor operation is permissible only during the succeeding seven days unless such vacuum breaker is sooner made operable, provided that the repair procedure does not violate primary containment integrity.
- c. If requirements of 3.7.A.3 cannot be met, the reactor shall be placed in a Cold Shutdown condition within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
3.7/4.7 -163- 1 41 Amendment No. 0, 130
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3
- 4. Pressure Suppression Chamber-Drywell Vacuum 4. Pressure Suppression Chamber-Drywell Vacuum Breakers Breakers
- a. When primary containment integrity is required, a. Operability and full closure of the all eight drywell-suppression chamber vacuum drywell-suppression chamber vacuum breakers breakers shall be operable and positioned in shall be verified by performance of the the closed position as indicated by the position following:
indication system, except during testing and except as specified in 3.7.A.4.b through (1) Monthly each operable drywell-suppression 3.7.A.4.d below. chamber vacuum breaker shall be exercised through an opening-closing
- b. Any drywell-suppression chamber vacuum cycle.
breaker may be nonfully closed as indicated by the position indication and alarm system (2) Once each operating cycle, drywell to provided that drywell to suppression chamber suppression chamber leakage shall be differential pressure decay does not exceed demonstrated to be less than that that shown on Figure 3.7.1 equivalent to a one-inch diameter orifice and each vacuum breaker shall be visually
- c. Up to two drywell-suppression chamber vacuum inspected. (Containment access required) breakers may be inoperable provided that: (1) the vacuum breakers are determined to be fully (3) Once each operating cycle, vacuum closed and at least one position alarm circuit is breaker position indication and alarm operable or (2) the vacuum breaker is secured systems shall be calibrated and functionally in the closed position or replaced by a blank tested. (Containment access required) flange. (4) Once each operating cycle, the vacuum
- d. Drywell-suppression chamber vacuum breakers breakers shall be tested to determine that may be cycled, one at a time, during the force required to open each valve from containment inerting and deinerting operations fully closed to fully open does not exceed to assist in purging air or nitrogen from the that equivalent to 0.5 psid acting on the I suppression chamber vent header. suppression chamber face of the valve disc. (Containment access required.)
3.714.7 4T64-Amendment No. ,36, 80,1-04, 141
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REIQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS reactor core, operations with a potential for reducing the shutdown margin below that specified in specification 3.3.A, and handling of irradiated fuel or the fuel cask in the secondary containment are to be immediately suspended if secondary containment integrity is not maintained.
D. Primary Containment Isolation Valves (PCIVs) D. Primary Containment Isolation Valves (PCIVs)
- 1. During reactor power operating conditions, all 1. The primary containment automatic isolation valve Primary Containment automatic isolation valves and surveillance shall be performed as follows:
all primary system instrument line flow check valves shall'be operable except as specified in 3.7.D.2 and a. At least once per operating cycle the operable I 3.7.D.3. isolation valves that are power operated and automatically initiated shall be tested for simulated automatic initiation and closure times.
- b. At least once per operating cycle the primary system instrument line flow check valves shall be tested for proper operation.
- c. All normally open power-operated isolation valves shall be tested in accordance with the Inservice Testing Program. Main Steam isolation valves shall be tested (one at a time) with the reactor power less than 75% of rated.
- d. At least once per week the main steam-line power-operated isolation valves shall be exercised by partial closure and subsequent reopening.
3.7/4.7 4-O Amendment No. 3, 71, 77, 122, 130, 141
3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4. 4.0 SURVEILLANCE REQUIREMENTS
- 3. a. The inerting and deinerting operations 3. Whenever containment purge and vent valves are permitted by TS 3.7.A.5.b shall be via the isolated to meet the requirements of TS 3.7.D.3.b, 18-inch purge and vent valves (equipped with the position of the deactivated and isolated valves 40-degree limit stops) aligned to the Reactor outside primary containment shall be recorded Building plenum and vent. All other purging monthly."
and venting, when primary containment integrity is required, shall be via the 2-inch purge and vent valve bypass line and the Standby Gas Treatment System.
- b. In the event one or more penetration flow paths with one or more containment purge and vent valves not within purge and vent valve leakage limits, reactor operation in the run mode may continue provided that within the subsequent 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, restore the valve(s) to within leakage limits, or at least one valve in each line having a purge and vent valve not within leakage limits is deactivated in the isolated position. This requirement may be satisfied by use of one closed and deactivated automatic valve, closed manual valve, or blind flange. (Deactivated means electrically or pneumatically disarm or 4. The seat seals of the drywell and suppression otherwise secure the valve.) chamber 18-inch purge and vent valves shall be I
replaced at least once every six operating cycles. If
- 4. If Specification 3.7.D.1, 3.7.D.2 and 3.7.D.3 cannot periodic Type C leakage testing of the valves be met, initiate normal orderly shutdown and have reactor in the Cold Shutdown condition within identifies a common mode test failure attributable to seat seal degradation, then the seat seals of all I
24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. drywell and suppression chamber 18-inch purge and vent valves shall be replaced.
- Isolated valves in high radiation areas may be verified by use of administration means.
3.7/4.7 -74a.
Amendment No. 430, 141