ML050350079

Tech Spec Pages for Amendment 141 Revision to Technical Specifications Table 3.2.3 and Section 3.7/4.7

ML050350079
Person / Time
Site:	Monticello
Issue date:	01/28/2005
From:	NRC/NRR/DLPM
To:
Padovan L
Shared Package
ML050350094	List: ML042940080 ML050350079
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)

d.

SRM Upscale block may be bypassed when associated IRM range switches are above Postion 6.

3.214.2 a-Amendment No. 2-9 1 41

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS

.1.

3.7 CONTAINMENT SYSTEMS Applicability:

Applies to the operating status of the primary and secondary containment systems.

Objective:

To assure the integrity of the primary and secondary containment systems.

Specification:

A.

Primary Containment.

1. Suppression Pool Volume and Temperature When irradiated fuel is in the reactor vessel and either the reactor water temperature is greater than 212'F or work is being done which has the potential to drain the vessel, the following requirements shall be met, except as permitted by Specification 3.5.E.2:

a. Water temperature during normal operating shall be < 900F.

b.

Water temperature during test operation which adds heat to the suppression pool shall be

• 1 000 F and shall not be > 90'F for more than 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.

c.

If the suppression chamber water temperature is > 1100F, the reactor shall be scrammed immediately. Power operation shall not be resumed until the pool temperature is s900F.

4.7 CONTAINMENT SYSTEMS Applicability:

Applies to the primary and secondary containment integrity.

Objective:

To verify the integrity of the primary and secondary containment.

Specification:

A.

Primary Containment

1. Suppression Pool Volume and Temperature

a. The suppression chamber water temperature shall be checked once per day.

b.

Whenever there is indication of relief valve operation which adds heat to the suppression pool, the pool temperature shall be continually monitored and also observed and logged every 5 minutes until the heat addition is terminated.

c.

A visual inspection of the suppression chamber interior including water line regions and the interior painted surfaces above the water line shall be made at each refueling outage.

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 4.0 SURVEILLANCE REQUIREMENTS 1.

I

2. Primary Containment Integrity

a. (1) Primary Containment Integrity as defined in Section 1, shall be maintained at all times when the reactor is critical or when the reactor water temperature is above 2120 F and fuel is in the reactor vessel, except as specified in 3.7.A.2.a.(2), 3.7.A.2.a.(3) or 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 />.

2.

Primary Containment Integrity

a.

Perform required visual examinations and leakage rate testing except for primary containment air lock testing, in accordance with the Primary Containment Leakage Rate Testing Program.

3.7/4.7

-1458-1 41 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

+

I

3. Pressure Suppression Chamber - Reactor Building Vacuum Breakers

a. Except as specified in 3.7.A.3.b below, two pressure suppression chamber-reactor building vacuum breakers shall be operable at all times when the primary containment integrity is required. The set point of the differential pressure instrumentation which actuates the pressure suppression chamber-reactor building 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. Pressure Suppression Chamber - Reactor Building Vacuum Breakers

a.

The pressure suppression chamber-reactor building vacuum breakers and associated instrumentation including set point shall be checked for proper operation every three months.

-163-1 41 Amendment No. 0, 130 3.7/4.7

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3

4.

Pressure Suppression Chamber-Drywell Vacuum Breakers

a. When primary containment integrity is required, all eight drywell-suppression chamber vacuum breakers shall be operable and positioned in the closed position as indicated by the position indication system, except during testing and except as specified in 3.7.A.4.b through 3.7.A.4.d below.

b.

Any drywell-suppression chamber vacuum breaker may be nonfully closed as indicated by the position indication and alarm system provided that drywell to suppression chamber differential pressure decay does not exceed that shown on Figure 3.7.1

c.

Up to two drywell-suppression chamber vacuum breakers may be inoperable provided that: (1) the vacuum breakers are determined to be fully closed and at least one position alarm circuit is operable or (2) the vacuum breaker is secured in the closed position or replaced by a blank flange.

d.

Drywell-suppression chamber vacuum breakers may be cycled, one at a time, during containment inerting and deinerting operations to assist in purging air or nitrogen from the suppression chamber vent header.

4.

Pressure Suppression Chamber-Drywell Vacuum Breakers

a.

Operability and full closure of the drywell-suppression chamber vacuum breakers shall be verified by performance of the following:

(1) Monthly each operable drywell-suppression chamber vacuum breaker shall be exercised through an opening-closing cycle.

(2) Once each operating cycle, drywell to suppression chamber leakage shall be demonstrated to be less than that equivalent to a one-inch diameter orifice and each vacuum breaker shall be visually inspected. (Containment access required)

(3) Once each operating cycle, vacuum breaker position indication and alarm systems shall be calibrated and functionally tested. (Containment access required)

(4) Once each operating cycle, the vacuum breakers shall be tested to determine that the force required to open each valve from fully closed to fully open does not exceed that equivalent to 0.5 psid acting on the suppression chamber face of the valve disc. (Containment access required.)

I 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)

1. During reactor power operating conditions, all Primary Containment automatic isolation valves and all primary system instrument line flow check valves shall'be operable except as specified in 3.7.D.2 and 3.7.D.3.

I D. Primary Containment Isolation Valves (PCIVs)

1. The primary containment automatic isolation valve surveillance shall be performed as follows:

a. At least once per operating cycle the operable 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.

4-O Amendment No. 3, 71, 77, 122, 130, 1 41 3.7/4.7

3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 3.0 LIMITING CONDITIONS FOR OPERATION 4.0 SURVEILLANCE REQUIREMENTS 4.

3. a. The inerting and deinerting operations permitted by TS 3.7.A.5.b shall be via the 18-inch purge and vent valves (equipped with 40-degree limit stops) aligned to the Reactor Building plenum and vent. All other purging 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 otherwise secure the valve.)

4.

If Specification 3.7.D.1, 3.7.D.2 and 3.7.D.3 cannot be met, initiate normal orderly shutdown and have reactor in the 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. Whenever containment purge and vent valves are isolated to meet the requirements of TS 3.7.D.3.b, the position of the deactivated and isolated valves outside primary containment shall be recorded monthly."

4.

The seat seals of the drywell and suppression chamber 18-inch purge and vent valves shall be replaced at least once every six operating cycles. If periodic Type C leakage testing of the valves identifies a common mode test failure attributable to seat seal degradation, then the seat seals of all drywell and suppression chamber 18-inch purge and vent valves shall be replaced.

I I

• • Isolated valves in high radiation areas may be verified by use of administration means.

3.7/4.7

-74a.

Amendment No. 430, 1 41