ML080860474
| ML080860474 | |
| Person / Time | |
|---|---|
| Site: | Dresden, Quad Cities  |
| Issue date: | 03/20/2008 |
| From: | Joel Wiebe NRC/NRR/ADRO/DORL/LPLII-2 |
| To: | Pardee C Exelon Generation Co |
| Wiebe, Joel NRR/DORL/LPL3-2, 415-6606 | |
| References | |
| TAC MD5275, TAC MD5276, TAC MD5284, TAC MD5285 | |
| Download: ML080860474 (11) | |
Text
CREV System 3.7.4 ACTIONS (continued)
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 AND B 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. CREV System inoperable ------------NOTE----------- I during movement of LCO 3.0.3 is not applicable.
recently irradiated -----------------------------
fuel assemblies in the secondary containment D.1 Suspend movement of Immediately or during OPDRVs. recently irradiated fuel assemblies in OR the secondary containment.
CREV System inoperable due to an inoperable AND CRE boundary'during movement of recently D.2 Initiate action to Immediately irradiated fuel suspend OPDRVs.
assemblies in the secondary containment or during OPDRVs.
Dresden 2 and 3 3.7.4-2 Amendment No. 226/218
CREV System 3.7.4 SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY
(
SR 3.7.4.1 Operate the CREV System for : 10 continuous 31 days hours with the heaters operating.
SR 3.7.4.2 Perform required CREV filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).
SR 3.7.4.3 Verify the CREV System actuates on a manual 24 months initiation signal.
SR 3.7.4.4 Perform required CRE unfiltered air In accordance inleakage testing in accordance with the with the Control Room Envelope Habitability Program. Control Room Envelope Habitability Program Dresden 2 and 3 3.7.4-3 Amendment No. 226/218
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)
- 2. NEI 94-01 - 1995, Section 9.2.3: The first Unit 3 Type A test performed after the July 14, 1994, Type A test shall be performed no later than July 13, 2009.
- b. The peak calculated primary containment internal pressure for the design basis loss of coolant accident, Pa, is 43.9 psig.
&. The maximum allowable primary containment leakage rate, La, at P, is 3% of primary containment air weight per day.
- d. Leakage rate acceptance criteria are:
- 1. Primary containment overall leakage rate acceptance criterion is
- 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are
- 0.60 La for the combined Type B and Type C tests, and < 0.75 La for Type A tests.
- 2. Air lock testing acceptance criteria is the overall air lock leakage rate is
- 0.05 La when tested at Ž Pa.
- e. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
5.5.13 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450-1995, "IEEE Recommended Practice for Maintenance, Testing,, and Replacement of Vented Lead-
.Acid Batteries for Stationary Applications," including the following:
- a. Actions to restore battery cells with float voltage
< 2.13 V, and
- b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the minimum established design limit.
(continued)
Dresden 2 and 3 5.5-12 Amendment No. 226/218
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.14 Control Room Envelooe Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such thdL, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE 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 radiati~on protection is provided to permit access and occupancy of the CRE 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:
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive maintenance.
- c. Requirements for (i) determining the unfiltered air inleakage past the CRE boundary into the CRE 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 CRE-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 CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation by the CREV system, operating at the flow rate required by the VFTP, at a Frequency of 24 months. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.
- e. The quantitative limits on unfiltered air inleakage into the CRE. 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 inleakage limits for hazardous chemicals must ensure that exposure of CRE 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 CRE habitability, determining CRE unfiltered (continued)
Dresden 2 and 3 5.5-13 Amendment No. 226/218
Programs and Manuals 5.5 5.5 Programs and Manuals 5..5.14 Control Room EnvelQoe Habitability Program (continued) inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraphs c and d, respectively.
Dresden 2 and 3 5.5-14 Amendment No. 226/218
CREV System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Room Emergency Ventilation (CREV) System LCO 3.7.4 The CREV System shall be OPERABLE.
NOTE------------------
The main control room envelope (CRE) boundary may be opened intermittently under administrative I control.
APPLICABILITY: MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPDRVs).
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CREV System inoperable A.1 Restore CREV System 7 days in MODE 1, 2, or 3 for to OPERABLE status.
reasons other than Condition B.
B. CREV system B.1 Initiate action to Immediately inoperable due to implement mitigating inoperable CRE actions.
boundary in MODE 1, 2, or 3. AND B.2 Verify mitigating 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> actions ensure CRE occupant exposures to radiological chemical, and smoke hazards will not exceed limits.
AND B.3 Restore CRE boundary 90 days to OPERABLE status.
(continued)
Quad Cities I and 2 3.7.4-1 Amendment No. 238/233
CREV 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 AND B 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. CREV System inoperable - ----------- NOTE------------
during movement of LCO 3.0.3 is not applicable.
r e c e n t l y i r r ad i a t e d . . .. .. . .. . .. . .. . .. .. .. .. . .. ..
fuel assemblies in the secondary containment D.1 Suspend movement of Immediately or during OPDRVs. recently irradiated fuel assemblies in OR the secondary containment.
CREV System inoperable due to an inoperable AND
- CRE boundary during movement of recently D.2 Initiate action to Immediately irradiated fuel suspend OPDRVs.
assemblies in the secondary containment or during OPDRVs.
Quad Cities I and 2 3.7.4-2 Amendment No. 238/233
CREV System 3.7.4 SURVEILLANCE REQUIREMENTS SURVEI LLANCE FREQUENCY SR 3.7.4.1 Operate the CREV System for.Ž 10 continuous 31 days hours with the heaters operating.
SR 3.7.4.2 Perform required CREV filter testing in In accordance accordance with the Ventilation Filter with the VFTP Testing Program (VFTP).
SR 3.7.4.3 Verify the CREV System isolation dampers 24 months close on an actual or simulated initiation signal.
SR 3.7.4.4 Perform required CRE unfiltered air In accordance inleakage testing in accordance with the with the Control Room Envelope Habitability Program. Control Room Envelope Habitability Program Quad Cities I and 2 3.7.4-3 Amendment No. 238/233
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.12 Primary Containment Leakage Rate Testing Program (continued)
- 2. NEI 94 1995, Section 9.2.3: The first Unit 2 Type A test performed after the May 17, 1993, Type A test shall be performed no later than May 16, 2008.
- b. The peak calculated primary containment internal pressure for the design basis loss of coolant accident, P,, is 43.9 psig.
- c. The maximum allowable primary containment leakage rate, La, at Pa, is 3% of primary containment air weight per day.
- d. Leakage rate acceptance criteria are:
- 1. Primary containment overall leakage rate acceptance criterion is S 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are
- 0.60 La for the combined Type B and Type C tests, and s 0.75 La for Type A tests.
- 2. Air lock testing acceptance criteria is the overall air lock leakage rate is ! 0.05 La when tested at Ž Pa.
- e. The provisions of SR 3.0.3 are applicable to the Primary Containment Leakage Rate Testing Program.
5.5.13 Control Room Envelope Habitability Program A Control Room Envelope (CRE) Habitability Program shall be established and implemented to ensure that CRE habitability is maintained such that, with an OPERABLE Control Room Emergency Ventilation (CREV) System, CRE 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 CRE under design basis accident (DBA) conditions without personnel receiving radiation exposure in excess of 5 rem total effective dose equivalent (TEDE) for the duration of the accident. The program shall include the following elements:
- b. Requirements for maintaining the CRE boundary in its design condition including configuration control and preventive (continued)
Quad Cities I and 2 55-ý-12 Amendment No. 238/233
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.13 Control Room Envelooe Habitability Program (continued) maintenance.
- c. Requirements of (i) determining the unfiltered air inleakage past the CRE boundary into the CRE in accordance with the testing methods and at the Frequencies specified in Section C.1 and C.2 of Regulatory Guide 1.197, "Demonstrating Control Room Envelope Integrity at Nuclear Power Reactors,"
Revision.O, May 2003, and (ii) assessing CRE habitability at the Frequencies specified in Section C.1 and C.2 of Regulatory Guide 1.197, Revision 0.
- d. Measurement, at designated locations, of the CRE pressure relative to all external areas adjacent to the CRE boundary during the pressurization mode of operation of the CREV system, operating at the flow rate required by the VFTP, at a Frequency of 24 months. The results shall be trended and used as part of the 24 month assessment of the CRE boundary.
- e. The quantitative limits on unfiltered air inleakage into the CRE. 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 inleakage limits for hazardous chemicals must ensure that exposure of CRE 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 CRE habitability, determining CRE unfiltered inleakage, and measuring CRE pressure and assessing the CRE boundary as required by paragraph c and d, respectively.
QudCte n .- 1 mnmn o 3/3 Quad Cities I and 2 5.5- 13 Amendment No. 238/233
CREV System 3.7.4 3.7 PLANT SYSTEMS 3.7.4 Control Room Emergency Ventilation (CREV) System LCO 3.7.4 The CREV System shall be OPERABLE.
-NOTE The main control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY: MODES 1, 2, and 3, During movement of recently irradiated fuel assemblies in the secondary containment, During operations with a potential for draining the reactor vessel (OPORVs).
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. CREV System inoperable A.1 Restore CREV System 7 days in MODE 1, 2, or 3 for to OPERABLE status.
reasons other than Condition B.
B. CREV system inoperable B.1 Initiate action to Immediately due to inoperable CRE implement mitigating boundary in MODE 1, 2, actions.
or 3.
AND B.2 Verify mitigating 24 hours1 days <br />0.143 weeks <br />0.0329 months <br /> actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
AND B.3 Restore CRE boundary 90 days to OPERABLE status.
(continued)
Dresden 2 and 3 3.7.4-1 Amendment No. 226/218