ML081780556

Tech Spec Pages for Amendment 269 Adoption of Changes to TSTF-448, Revision 3, Control Room Habitability.

ML081780556
Person / Time
Site:	Duane Arnold
Issue date:	06/24/2008
From:	NRC/NRR/ADRO/DORL/LPLIII-1
To:
Feintuch K, NRR/DORL/LPL3-1, 415-3079
References
TAC MD6020
Download: ML081780556 (6)

Text

SFU System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Standby Filter Unit (SFU) System LCO 3.7.4 Two SFU subsystems shall be OPERABLE.

---

..--------------- NO TE ------------------------------

The control building envelope (CBE) boundary may be opened intermittently under administrative control.

APPLICABILITY: MODES 1, 2, and 3, During movement of irradiated fuel assemblies in the secondary containment, During CORE ALTERATIONS, During Operations with a Potential for Draining the Reactor Vessel (OPDRVs).

ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One SFU A.1 Restore SFU subsystem to 7 days subsystem OPERABLE status.

inoperable for reasons other than Condition B.

B. One or more SFU B.1 Initiate actions to implement Immediately subsystems mitigating actions.

inoperable due to inoperable CBE AND boundary in B.2 Verify mitigating actions 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> MODES 1, 2, and ensure CBE occupant

3. exposures to radiological hazards will not exceed limits and verify by administrative means that CBE occupants are protected from smoke and chemical hazards.

AND B.3 Restore CBE boundary to 90 days OPERABLE status.

DAEC 3.7-7 Amendment No. 269.

SFU System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME C. Required Action and C.1 Be in MODE 3. 12 hours0.5 days <br />0.0714 weeks <br />0.0164 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 hours1.5 days <br />0.214 weeks <br />0.0493 months <br /> D. Required Action and -- - ---------- NOTE------

associated Completion LCO 3.0.3 is not applicable.

Time of Condition A not met during movement D.1 Place OPERABLE Immediately of irradiated fuel SFU subsystem in the assemblies in the isolation mode.

secondary containment, during OR CORE ALTERATIONS, or during OPDRVs. D.2.1 Suspend movement Immediately of irradiated fuel assemblies in the secondary containment.

AND D.2.2 Suspend CORE Immediately ALTERATIONS.

AND D.2.3 Initiate action to Immediately suspend OPDRVs.

E. Both SFU subsystems E.1 Enter LCO 3.0.3. Immediately inoperable in MODE 1, 2, or 3 for reasons other than Condition B.

(continued) 69 DAEC 3.7-8 Amendment No?

SFU System 3.7.4 ACTIONS (continued)

CONDITION REQUIRED ACTION COMPLETION TIME F. Both SFU subsystems - NOTE -----------

inoperable during LCO 3.0.3 is not applicable.

movement of irradiated fuel assemblies in the F.1 Suspend movement Immediately secondary containment, of irradiated fuel during CORE assemblies in the ALTERATIONS, or secondary during OPDRVs. containment.

OR AND One or more SFU F.2 Suspend CORE Immediately subsystems inoperable ALTERATIONS.

due to an inoperable CBE boundary during AND movement of irradiated fuel assemblies in the F.3 Initiate action to Immediately secondary containment, suspend OPDRVs.

during CORE ALTERATIONS, or during OPDRVs.

SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3.7.4.1 Operate each SFU subsystem for 31 days

> 15 minutes.

SR 3.7.4.2 Perform required SFU filter testing in In accordance accordance with the Ventilation Filter Testing with the VFTP Program (VFTP).

(continued)

DAEC 3.7-9 Amendment No.269

SFU System 3.7.4 SURVEILLANCE REQUIREMENTS (continued)

SURVEILLANCE FREQUENCY SR 3.7.4.3 Verify each SFU subsystem actuates on an 24 months actual or simulated initiation signal.

SR 3.7.4.4 Perform required CBE unfiltered air inleakage In accordance testing in accordance with the Control Building with the Envelope Habitability Program. Control Building Envelope Habitability Program DAEC 3.7-10 Amendment No. 2 6 9

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)

The first Type A test after the September 1993 Type A test shall be performed no later than September 2008.

The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 45.7 psig.

The maximum allowable primary containment leakage rate, La, at Pa, shall be 2.0% of primary containment air weight per day.

Leakage Rate acceptance criteria are:

a. Primary Containment leakage rate acceptance criterion is _<1.0 La. During the first startup following testing in accordance with this program, the leakage rate acceptance criteria are: _<0.60 La for the Type B and Type C tests; and, _<0.75 La forthe Type A tests; and

b. The air lock testing acceptance criterion is overall air lock leakage rate _<0.05 La when tested at _>Pa.

The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.

5.5.13 Control Building Envelope Habitability Program A Control Building Envelope (CBE) Habitability Program shall be established and implemented to ensure that CBE habitability is maintained such that, with an OPERABLE Standby Filter Unit System, CBE occupants can control the reactor safely under normal conditions and maintain it in a safe condition following a radiological event, hazardous chemical release, or a smoke challenge. The program shall ensure that adequate radiation protection is provided to permit access and occupancy of the CBE under design basis accident (DBA) conditions without personnel receiving radiation exposures in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:

a. The definition of the CBE and the CBE boundary.

b. Requirements for maintaining the CBE boundary in its design condition including configuration control and preventive maintenance.

(continued)

DAEC 5.0-18 Amendment No. 2 6 9

Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Control Buildinq Envelope Habitability Progqram (continued)

c. Requirements for (i) determining the unfiltered air inleakage past the CBE boundary into the CBE in accordance with the testing methods and at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors," Revision 0, May 2003, and (ii) assessing CBE habitability at the Frequencies specified in Sections C.1 and C.2 of Regulatory Guide 1.197, Revision 0.

d. Measurement, at designated locations, of the CBE pressure relative to all external areas adjacent to the CBE boundary during the pressurization mode of operation by one subsystem of the SFU System, operating at the flow rate required by the VFTP, at a Frequency of 24 months on a STAGGERED TEST BASIS. The results shall be trended and used as part of the 24 month assessment of the CBE boundary.

e. The quantitative limits on unfiltered air inleakage into the CBE.

These limits shall be stated in a manner to allow direct comparison to the unfiltered air inleakage measured by the testing described in paragraph c. The unfiltered air inleakage limit for radiological challenges is the inleakage flow rate assumed in the licensing basis analyses of DBA consequences. Unfiltered air leakage limits for hazardous chemicals must ensure that the exposure of CBE occupants to these hazards will be within the assumptions in the licensing basis.

f. The provisions of SR 3.0.2 are applicable to the Frequencies for assessing CBE habitability, determining CBE unfiltered inleakage, and measuring CBE pressure and assessing the CBE.boundary as required by paragraphs c and d, respectively.

DAFC 5.0-18a Amendment No. 269