PLA-6695, Amend. Request No. 308 to License NPF-14 & Amend. Request No. 279 to License NPF-22: Adoption of Technical Specification Task Force Traveler TSTF-514, Rev. 3, Revise BWR Operability Requirements & Actions RCS Leakage Instrumentation
| ML111010588 | |
| Person / Time | |
|---|---|
| Site: | Susquehanna  |
| Issue date: | 04/08/2011 |
| From: | Rausch T Susquehanna |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| PLA-6695, TATF-514, Rev 3 | |
| Download: ML111010588 (31) | |
Text
Timothy S. Rausch PPL Susquehanna, LLC 1
1 Sr. Vice President & Chief Nuclear Officer 769 Salem Boulevard Berwick, PA 18603 Tel. 570.542.3445 Fax 570.542.1 504 tsrausch@pplweb.com APR 0 8 2011 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Stop OP1-17 Washington, DC 20555 SUSQUEHANNA STEAM ELECTRIC STATION AMENDMENT REQUEST NO. 308 TO LICENSE NPF-14 AND AMENDMENT REQUEST NO. 279 TO LICENSE NPF-22:
ADOPTION OF TECHNICAL SPECIFICATION TASK FORCE TRAVELER TSTF-514, REVISIQN 3, "REVISE BWR OPERABILITY REQUIREMENTS AND ACTIONS FOR RCS LEAKAGE INSTRUMENTATION" Docket Nos. 50-387 PLA-6695 and 58-388
Reference:
Technical Specification Task Force Traveler TSTF-514, Revision 3, "Revise B WR Operability Requirements and Actions for RCS Leakage InstmmentaZion. "
Tn accordance with the provisions of Section 50.90 of Title 10 of the Code of Fedewl Regulations (10 CFR), PPL Susquehanna, LLC (PPL) is submitting a request for amendments to the Technical Specifications (TS) for the Susquehanna Steam Electric Station, Units 1 and 2.
The proposed amendment would revise the TS to define a new time limit for restoring inoperable Reactor Coolant System (RCS) leakage detection instmmentation to operable status, establish alternate methods of monitoring RCS leakage when one or more required monitors are inoperable, and make TS Bases changes which reflect the proposed changes and more accurately reflect the contents of the facility design basis related to operability of the RCS leakage detection instrumentation. These changes are consistent with the NRC-approved Revision 3 to Standard Technical Specification (STS) Change Traveler TSTF-5 14, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation." The availability of this TS improvement was announced in the Federal Register on 12/17/20 10 (75 FR 79048) as part of the consolidated line item improvement process (CLIIP). provides an evaluation of the proposed changes.
- Attachment 2 provides the marked up pages of the existing TS to show the proposed changes.
Document Control Desk PLA-6695 provides the marked up pages of the existing TS Bases to show the proposed changes.
PPL requests approval of the proposed license amendment by 12/30/2011, with the amendment being implemented within 60 days of approval.
In accordance with I0 CFR 50.91(a)(l), "Notice for Public Comment," the analysis of No Significant Hazards Consideration, using the standards in 10 CFR 50.92, is provided to the Commission in accordance with the distribution requirements in 10 CFR 50.4. In accordance with 10 CFR 50.91(b)(l), "State Consultation," a copy of this application is provided to the designated Pennsylvania Official.
If you should have any questions about this submittal, please contact Ms. Margaret Rochester at (570) 542-3028.
I declare under penalty of perjury that the foregoing is correct and true.
Executed on - Evaluation of Proposed Changes - Markups of Existing Technical Specifications - Markups of Existing Technical Specification Bases Copy: NRC Region I Nr. P. W. Finney, NRC Sr. Resident Inspector Mi. R. R. Janati, DEPBRP LW. B. K. Vaidya, NRC Project Manager to PLA-6695 PPL Susquehanna, LLC, Unit 1 and Unit 2 Proposed Technical Specification Amendment for Adoption of Task Force Traveler TSTF-514, Revision 3, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation',
DESCRIPTION PROPOSED CHANGES BACKGROUND TECHNICAL ANALYSIS REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration Determination 5.2 Applicable Regulatory Requirements/Criteria ENVIRONMENTAL CONSIDERATIONS REFERENCES to PLA-6695 Page 1 of 6 PPL EVALUATION I
Subiect: PPL Susquehanna, LLC, Unit 1 and Unit 2 Proposed Technical Specification Amendment for Adoption of Task Force Traveler TSTF-514, Revision 3, Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation.
1.0 DESCRIPTION
The proposed amendment would revise the Technical Specifications (TS) to define a new time limit for restoring inoperable Reactor Coolant System (RCS) leakage detection instrumentation to operable status, establish alternate methods of monitoring RCS leakage when one or more required monitors are inoperable, and make conforming TS Bases changes. These changes are consistent with NRC-approved Revision 3 to Technical Specification Task Force (TSTF) Standard Technical Specification (STS)
Change Traveler TSTF-5 14, "Revise BWR Operability Requirements and Actions for RCS Leakage Instrumentation." The availability of this TS improvement was announced in the Federal Register on 12/17/2010 (75 FR 79048) as part of the consolidated line item improvement process (CLIIP).
2.0 PROPOSED CHANGE
S The proposed changes revise and add a new Condition C to TS 3.4.6. "RCS Leakage Detection Instrumentation" and revise the associated bases. New Condition C is applicable when the primary containment atmosphere gaseous radiation monitor is the only operable TS-required instrument monitoring RCS leakage, i.e., TS-required particulate and sump monitors are inoperable. New Condition C Required Actions require monitoring RCS leakage by obtaining and analyzing grab samples of the primary containment atmosphere every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, monitoring RCS leakage using administrative means every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, and taking action to restore monitoring capability using another monitor within 7 days.
Additionally, minor editorial revisions are proposed to ensure continuity of the TS format. These changes are the result of new Condition C and consist of re-lettering existing conditions C and D as conditions D and E respectively. Revisions to the TS Bases are also provided to clarify the specified safety function for each required instrument in Limiting Condition for Operation (LCO), delete discussion from the TS Bases that could be construed to alter the meaning of TS operability requirements, and reflect the proposed changes to TS 3.4.6.
to PLA-6695 Page 2 of 6 PPL is not proposing variations or deviations from the TS changes described in TSTF-514, Revision 3, or the NRC staff's model safety evaluation (SE) published in the Federal Register on 12/17/2010 (75 FR 79048) as part of the CLIIP Notice of Availability.
3.0 BACKGROUND
NRC Information Notice (IN) 2005-24, "Nonconservatism in Leakage Detection Sensitivity," dated August 3, 2005, informed addressees that the reactor coolant activity assumptions for primary containment atmosphere gaseous radioactivity monitors may be non-conservative. This means the monitors may not be able to detect a one gallon per minute leak within one hour. Some licensees, in response to IN 2005-24, have taken action to remove the gaseous radioactivity monitor from the TS list of required monitors.
However, industry experience has shown that the primary containment atmosphere gaseous radiation monitor is often the first monitor to indicate an increase in RCS leak rate. As a result, the TSTF and the NRC staff met on April 29,2008 and April 14,2009 to develop an alternative approach to address the issue identified in IN 2005-24. The agreed solution is to retain the primary containment atmosphere gaseous radiation monitor in the LC0 list of required equipment, revise the specified safety function of the gas monitor to specify the required instrument sensitivity level, revise the Required Actions to require additional monitoring, and provide less time before a plant shutdown is required when the primary containment atmosphere gaseous radiation monitor is the only operable monitor.
4.0 TECHNICAL ANALYSIS
PPL has reviewed TSTF-5 14, Revision 3, and the model Safety Evaluation (SE) published on 12/17/2010 (75 FR 79048) as part of the CLIIP Notice of Availability. PPL has concluded that the technical bases presented in TSTF Traveler-5 14, Revision 3, and the model SE prepared by the NRC staff are applicable to Susquehanna.
The RCPB and the leak detection system are designed to meet the requirements of Criterion 30. Means are provided for detecting reactor coolant leakage. The leak detection system consists of sensors and instruments to detect, annunciate, and in some cases, isolate the RCPB from potentially hazardous leaks before predetermined limits are exceeded. Small leaks are detected by temperature and pressure changes, increased frequency of sump pump operation, and by measuring fission product concentration. In addition to these means of detection, large leaks are detected by changes in flow rates in process lines, and changes in reactor water level. The allowable leakage rates have been based on the predicted and experimentally determined behavior of cracks in pipes, the ability to make up coolant system leakage, the normally expected background leakage due to equipment design, and the detection capability of the various sensors and instruments. The total leakage rate limit is established so that, in the absence of normal AC power with a loss of feedwater supply, makeup capabilities are provided by the RCTC to PLA-6695 Page 3 of 6 system. While the RCIC system provides protection from small leaks, the ECCS network provides protection for the complete range of discharges from ruptured pipes. Thus, protection is provided for the full spectrum of possible discharges.
Primary containment leak detection is discussed in the Susquehanna FSAR in section 5.2.5.1.2 "Detection of Abnormal Leakage Within the Primary Containment (Non-NSSS)." Leakage through the reactor coolant pressure boundary within the primary containment is detected by monitoring temperatures, pressures, airborne gaseous and particulate radioactivity, and changes of levels in the floor drain sumps. The following systems are used to monitor unidentified primary coolant pressure boundary leakage.
- Primary containment atmosphere monitoring system (containment radiation detection)
- Drywell floor drain sump level monitoring and drywell equipment drain tank level monitoring system These leak detection systems are designed in accordance with recommendations of Regulatory Guide 1.45, Revision 0.
The primary containment atmosphere monitoring system includes a noble gas radiation monitor, and a particulates radiation monitor. The two radiation monitors sample the drywell for activity levels on the assumption that flashing coolant leakage will result in radioactivity in the atmosphere.
The administrative means of monitoring include diverse alternative mechanisms from which appropriate indicators may be selected based on plant conditions. PPL will utilize the following method or methods as appropriate considering current plant conditions and historical or expected sources of unidentified leakage: primary containment pressure, primary containment temperature, component cooling water system outlet temperatures, component cooling water system makeup, reactor recirculation system pump seal pressure and temperature, reactor recirculation system pump motor cooler temperatures, primary containment cooling fan outlet temperatures, reactor building chiller amperage, control rod drive system flange temperatures, safety relief valve tailpipe temperature, flow, pressure, or other approved methods.
The proposed Required Actions to analyze primxy contaiment atmospheric grab samples and monitor RCS leakage by the administsative means above are sufficient to alert the operating staff to an unexpected increase in RCS leakage.
to PLA-6695 Page 4 of 6 5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration Determination PPL has evaluated the proposed changes to the TS using the criteria in 10 CFR 50.92 and has determined that the proposed changes do not involve a significant hazards consideration. An analysis of the issue of no significant hazards consideration is presented below:
Description of Amendment Request: The proposed amendment would revise TS 3.4.6, "Reactor Coolant System (RCS) Leakage Detection Instrumentation" by adding Condition C and Required Actions and the licensing basis for the primary containment atmospheric gaseous radiation monitor. Additionally, existing Conditions C and D would be re-lettered as Conditions D and E. Revisions to the associated TS Bases for TS 3.4.6 are also included.
Basis for proposed no significant hazards consideration determination: As required by 10 CFR 50.91(a), the PPL analysis of the issue of no significant hazards consideration using the standards in 10 CFR 50.92 is presented below:
- 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change clarifies the operability requirements for the RCS leakage detection instrumentation and reduces the time allowed for the plant to operate when the only TS-required operable RCS leakage detection instrumentation monitor is the primary containment atmospheric gaseous radiation monitor. The monitoring of RCS leakage is not a precursor to any accident previously evaluated. The monitoring of RGS leakage is not used to xnitigate the consequences of any accident previously evaluated. Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change clarifies the operability requirements for the RCS leakage detection instrumentation and reduces the time allowed for the plant to operate when the only TS-required operable RCS leakage detection instrumentation monitor is the primary containment atmospheric gaseous radiation monitor. The proposed change does not involve a physical alteration of the plant (no new or different type of equipment will be to PLA-6695 Page 5 of 6 installed) or a change in the methods governing normal plant operation. Therefore, it is concluded that the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The proposed change clarifies the operability requirements for the RCS leakage detection instrumentation and reduces the time allowed for the plant to operate when the only TS-required operable RCS leakage detection instrumentation monitor is the primary containment atmospheric gaseous radiation monitor. Reducing the amount of time the plant is allowed to operate, with only the primary containment atmospheric gaseous radiation monitor operable, increases the margin of safety by limiting continued plant operation during the timeframe of reduced monitoring capabilities. Therefore, it is concluded that the proposed change does not involve a significant reduction in a margin of safety.
Based upon the above analysis, PPL concludes that the requested change does not involve a significant hazards consideration, as set forth in 10 CFR 50.92(c), "Issuance of Amendment."
5.2 Applicable Regulatory RequirementsICriteria A description of the proposed TS change and its relationship to applicable regulatory requirements were published in the Federal Register Notice of Availability on 12/17/2010 (75 FR 79048). PPL has reviewed the NRC staff's model SE referenced in the CLIIP Notice of Availability and concluded that the regulatory evaluation section is applicable to Susquehanna.
The RCPB and the leak detection system are designed to meet the requirements of Criterion 30. Means are provided for detecting reactor coolant leakage. The leak detection system consists of sensors and instruments to detect, annunciate, and in some cases, isolate the RCPB from potentially hazardous leaks before predetermined limits are exceeded. Small leaks are detected by temperature and pressure changes, increased frequency of sump pump operation, and by measuring fission product concenbation. In addition to these means of detection, large leaks are detected by changes in flow rates in process lines, and changes in reactor water level. The allowable leakage rates have been based on the predicted and experimentally determined behavior of cracks in pipes, the ability to make up coolant system leakage, the normally expected background leakage due to equipment design, and the detection capability of the various sensors and instruments. The total leakage rate limit is established so that, in the absence of normal AC power with a loss of feedwater supply, makeup capabilities are provided by the RCIC system. While the RCIC system provides protection from small leaks, the ECCS network to PLA-6695 Page 6 of 6 provides protection for the complete range of discharges from ruptured pipes. Thus, protection is provided for the full spectrum of possible discharges.
Primary containment leak detection is discussed in the Susquehanna FSAR in section 5.2.5.1.2 "Detection of Abnormal Leakage Within the Primary Containment (Non-NSSS)." Leakage through the reactor coolant pressure boundary within the primary containment is detected by monitoring temperatures, pressures, airborne gaseous and particulate radioactivity, and changes of levels in the floor drain sumps. The following systems are used to monitor unidentified primary coolant pressure boundary leakage
- Primary containment atmosphere monitoring system (containment radiation detection)
- Drywell floor drain sump level monitoring and drywell equipment drain tank level monitoring system The primary containment atmosphere monitoring system includes a noble gas radiation monitor, and a particulates radiation monitor. The two radiation monitors sample drywell for the activity levels on the assumption that flashing coolant leakage will result in radioactivity in the atmosphere.
These leak detection systems are designed in accordance with recommendations of Regulatory Guide 1.45, Revision 0.
6.0 ENVIRONMENTAL CONSIDERATION
S The proposed change would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR Part 20, and would change an inspection or surveillance requirement. However, the proposed change does not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amounts of any effluents that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure.
Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in 10 CFR 5 1.22(~)(9). Therefore, pursuant to 10 CFR 5 1.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed change.
7.0 REFERENCES
7.1 Susquehanna FSAR section 5.2 7.2 Susquehanna FSAR section 3.1 7.3 Susquehanna FSAR section 3.1 3 to PLA-6695 PPL Susquehanna, LLC, Unit 1 and Unit 2 Markups of Existing Technical Specifications
PPL Rev. 24-I RCS Leakage Detection Instrumentation 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Leakage Detection Instrumentation LC0 3.4.6 The following RCS leakage detection instnrmentation shall be OPERABLE;
- a.
Drywell floor drain sump moniroring system; and
- b.
One channel of either primary containment atmospheric particulate or atmospheric gaseous monitoring system.
APPLICABlLITY:
MODES 1 and 2, and 3.
ACTIONS A.
Drywetl floor drain A. 1 Restore drywell floor 30 days sump monitoring drain sump monitoring system inoperable.
system to OPERABLE
- stabs, CONDITION SUSQUEHANNA - UNIT 1 Amendment 1~8,219 REQtltRED ACTION COMPLETlON TIME I
PPL Rev. 21 f RCS Leakage Detection Instrumentation 3.4.6 B,
Required primary 8.7 Analyze grab samples containment of primary containment atmospheric monitoring atmosphere.
system inoperable.
AND -
ACTIONS (continued)
B.2 Restore required primary containment atmospherii monitoring system to OPERABLE status.
CONDITION Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 30 days REQUIRED ACTION
NOTE ---- --- --------
COMPLETION TIME monitor.
atmospheric qaseous radiation monitor is the oniv OPERABiE 6.2 Moni"ior RCS LEAICAGE 4
AND -
to OPERABLE status.
Required Action and associated Completion Time of Condition A %
E3 or C not met.
2 All required leakage detection systems inoperable.
AND -
GQ.2 Be in MODE 4.
6Q.l Be in MODE 3.
36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> 12 hours SUSQUEHANNA - UNIT 1 DE. t Enter LC0 3.0.3.
Amendment l$, S4-43 1 ammediately I
PPL Rev. gf-I RGS Leakage Detection Instrumentation 3.4.6 SURVEILLANCE REQUIREMENTS SURVEILLANCE SR 3.4.6.1 Perform a CHANNEL CHECK of required primary containment atmospheric monitoring system.
SR 3.4.6.2 Perform a CHANNEL FUNCTIONAL TEST of required leakage detection instrumentation.
SR 3.4.6.3 Perform a CHANNEL CALIBRATlQN of required leakage detection instrumentation.
SUSQUEHANNA - UNIT 1 FREQUENCY 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 31 days 24 months Amendment 178
PPL Rev. 2 1 RCS Leakage Detection Instrumentation 3.4.6 3.4 REACTOR COOLANT SYSTEM (RCS) 3.4.6 RCS Leakage Detection Instrumentation LC0 3.4.6 The following RCS leakage detection instrumentation shall be OPERABLE:
- a.
Dryw~l! floor drain sump monitoring system; and
- b.
One channel of either primary containment atmospheric particulate or atmospheric gaseous monitoring system.
APPLICABILITY:
MODES 1 and 2, and 3.
CONDITION SUSQUEHANNA - UNIT 2 A.
Drywell floor drain sump monitoring system inoperable.
(continued)
REQUIRED ACTION Amendment 141, 195 COMPLETION TIME A. 1 Restore drywell floor drain sump monitoring system to OPERABLE status.
30 days
PPL Rev. 4-2 ]
RGS Leakage Detection instrumentation 3.4.6 B.
Required primary containment atmospheric monitoring system inoperable.
ACTIONS (continued)
B.l Analyze grab samples of primary containment atmosphere.
CONDITION AND -
B.2 Restore required primary containment atmospheric monitoring system to OPERABLE status.
REQUIRED ACTION Once per 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> COMPLETION TIME 30 days
NOTE ------------- --
monitor.
AND v
C.2 Monitor RCS LEAKAGE AND to OPERABLE status.
~ £ 3, or C not met.
I CQ.2 Be in MODE 4.
GQ. Required Action and associated Completion Time of Condition A, 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> 36 hours 6Q.1 Be in MODE 3.
AND Qg.
All rquired leakage detection systems inoperable.
Qg.1 Enter LC0 3.0.3.
Immediately I
SUSQUEHANNA - UNIT 2 Amendment 1f/1, 4%
1
PPL Rev. -1.2 1 RCS Leakage Detection Instrumentation 3.4.6 SURVEILLANCE REQUIREMENTS SR 3.4.6.1 Perform a CHANNEL CHECK of required primary containment atmospheric monitoring system.
SURVEILLANCE 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> FREQUENCY SR 3.4.6.2 Perform a CHANNEL FUNCTIONAL TEST of required 31 days leakage detection instrumentation.
Sf3 3.4.6.3 Perform a CHANNEL CALIBRATION of required leakage detection instrumentation.
SUSQUEHANNA - UNIT 2 Amendment 1 St to PLA-6695 PPL Susquehanna, LLC, Unit 1 and Unit 2 Markups of Existing Technical Specification Bases
PPL Rev, 1
RCS Leakage Detection Instrumentation B 3.4.6 B 3.4 REACTOR COOLANT SYSTEM (RCS) 8 3.4.6 RCS Leakage Detection Instrumentation BASES BACKGROUND GDC 30 of 10 CFR 50, Appendix A (Ref. 11, requires means for detecting and, to the extent practical, identifying the location of the source of RCS LEAKAGE. Regulatory Guide I
.45,F(evision 0, (Ref. 2) describes acceptable methods for selecting leakage detection systems.
I Limits on LEAKAGE from the reactor coolant pressure boundary (RCPB) are required so that appropriate action can be taken before the integrity of the RCPB is impaired (Ref. 2)" Leakage detection systems for the RCS are provided to alert the operators when leakage rates above normal background levels are detected and also to supply quantitative measurement of leakage rates. The Bases for LC0 3.4.4, "RCS Operational LEAKAGE,"
discuss the limits on RCS LEAKAGE rates.
Systems for separating the LEAKAGE of an identified source from an unidentified source are necessary to provide prompt and quantitative information to the operators to permit them to take immediate corrective action.
LEAKAGE from the RCPB inside the drywell is detected by at least one of two or three independently monitored variables, such as sump level changes and drywell gaseous and particulate radioactivity levels. The primary means of quantifying LEAKAGE in the drywelf is the dryweft floor drain sump monitoring system which consists of two drywetl floor drain sump level Channels. Both Channels are required to be Operable 10 satisfy the LCO.
The dwell floor drain sump monitoring system monitors the LEAKAGE coilected in the floor drain sump. This unidentified LEAKAGE consists of LEAKAGE from control rod drives, valve flanges or packings, floor drains, the Closed Cooling Water System, and drywet! air cooling unit condensate drains, and any LEAKAGE not collected in the dwell equipment drain tank.
The level of each drywelt sump is confinuousQ recorded in the Main Control Room. The change in (continued)
SUSQUEWANNA - UNIT 1 TS / B 3.4-30 Revision 4-2 1
PPL Rev. % 1 RCS Leakage Detection Instrumentation B 3.4.6 BASES BACKGROUND sump level per unit time determines the leak rate and is calculated from the (continued) recorder.
The floor drain sump levef indicators have svvitches that start and stop the sump pumps when required. If the sump fills to the high high level setpoint, an alarm sounds in the control room.
The primary containment air monitoring systems continuously monitor the primary containment atmosphere for air$orne particulate and gaseous radioactivity. A sudden increase of radioactivity, which may be attributed to RCPB steam or reacbr water LEAKAGE, is annunciated in the control room.
APPLICABLE A threat of significant compromise to the RCPB exists if the barrier contains SAFETY a crack that is large enough to propagate rapidly. LEAKAGE rate limits are ANALYSES set tow enough to detect the LEAKAGE emitted from a single crack in the RCPB @an occur.
RCS leakage detection instrumentation satisfies Criterion 1 of the NRC Policy Statement (Ref. 7).
tca condition. \\athen ACS LEAUGE indiwt (continued)
SUSQUEHANNA - UNiT I TS I B 3.4-31 Revision &1_1 I
PPL Rev. &J 1 RCS Leakage Detection Instrumentation B 3.4.6 BASES I
LC0 (continued)
The LC0 is satisfied when mcrnitsw of diverse measurement me-ans are (continued)
SUSQUEHAMNA - UNIT 7 7s I B 3.4-32 Revision Q-1 1
PPL Rev. @ 1 RCS Leakage Detection Instrumentation B 3.4.6 BASES LC0 (continued)
APPLICABILITY In MODES 1,2, and 3, leakage detection systems are required to be OPERABLE to support LC0 3.4.4. This Applicability is consistent with that for LC0 3.4.4.
ACTIONS A. 1 With the drywell floor drain sump monitoring system inoperable, the primary containment atmospheric activity monitor will provide indication of changes in teakage.
With the drywell floor drain sump monitoring system inoperable, operation may continue for 30 days. However, RCS unidentified and total LEAKAGE is still required to be determined every 12 haurs (SR 3.4.4.1 3. The 30 day Completion Time of Required Action A. 1 is acceptable, based on operating experience, considering the multiple forms of leakage detection that are still available.
B.l and 8.2 With both gaseous and particulate primary containment atmospheric monitoring channels inoperable, grab samples of the primary containment atmosphere must be taken and analyzed to provide periodic leakage information. Provided a sample is obtained and analyzed once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the plant may be operated for up to 30 days to allow restoration of at Iast one of the required monitors.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval provides peridic infomation that is adequate to detect LEAKAGE. The 30 day Completion Time for restoration recognizes that at least one other form of leakage detection is available.
(continued)
SUSQUEHANNA - UNIT 7 TS / B 3.4-33 Revision 4-2 I
PPL Rev. % f RCS Leakage Detection Instrumentation B 3.4.6 BASES ACTIONS 6.1, C.2, and 6.3.
(continued) unidentified LEAMBGE.
(continued)
SUSQUEHANNA - UN1T 1 TS / B 3.4-34 Revision 4-2 1
PPL Rev. Cg 1
RCS Leakage Detection instrumentation 6 3.4.6 BASES ACTIONS GD.1 ancSD.2 (mntinued)
I If any Required Action of Condition A, e~ 6 or C cannot be met within the 1
associated Completion Time, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to perform the actions in an orderly manner and without challenging plant systems.
With alf required monitors inoperable, no required automatic means of monitoring LEAKAGE are available, and immediate plant shutdown in accordance with LC0 3.0.3 is required.
SURVEILLANCE SR 3.4s6,1 REQUIREMENTS This SR is for the performance of a CHANNEL CHECK of the required primary containment atmospheric monitoring system. The check gives reasonable confidence that the channel is operating properly. The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is based on instrument reliability and is reasonable for detecting off normal conditions.
This S R is for the performance of a CHANNEL FUNCTIONAL TEST of the required RCS leakage detection instrumentation. The test ensures that the monitors can perform their function in the desired manner. The Frequency of 31 days considers instrument reiiability, and owrating experience has shown it proper for detecting degradation.
This SR is for the performance of a CHANNEL CALrBRATlON of required leakage detection instrumentation channels. The calibration verifies the accuracy of the instnrment string, including the instruments lo~stted inside containment. The Frquency of 24 months is a typical refueling cycle and considers channel refiabiliw.
(continued)
SUSQUEHANNA - UNIT 1 TS / B 3.4-34a Revision 4-g 1
PPL Rev, a4 1 RCS Leakage Detection Instrumentation B 3.4.6 BASES REFERENCES
- 2. Regulatory Guide 1.45, Revision 0. "Reactor Coolant: Pressure May 1973.
I
- 43. GEAP-5620, April 1968.
I
- s.
NUREG-75/067, October 1975.
I FSAR, Section 5.2.5.4.
I
- 6. FSAR, Section 5.2.7.2.1.
I
- 7. Final Poky Statement on Technical Specifications Improvements, July 22, 1 993 (58 FR 391 32).
SUSQUEWANNA - UNIT 1 TS I !3 3.4-343 Revision @-I 1
PPL Rev. 2pj I RCS Leakage Detection Instrumentation B 3.4.6 6 3.4 REACTOR COOLANT SYSTEM (RCS)
B 3.4.6 RCS Leakage Detection Instrumentation BASES BACKGROUND GDC 30 of 10 CFR 50, Appendix A (Ref. I), requires means for detecting and, to the extent practical, identifying the location of the source of RCS LEAKAGE. Regulatory Guide 1.45, Revision 0, (Ref. 2) describes acceptable methods for selecting leakage detection systems.
Limits on LEAKAGE from the reactor coolant pressure boundary (RCPB) are required so that appropriate action can be taken before the integrity of the RCPB is impaired (Ref. 2). Leakage detection systems for the RCS are provided to alert the operators when leakage rates above normal background levels are detected and also to supply quantitative measurement of leakage rates. The Bases for LC0 3.4.4, "RCS Operational LEAKAGE,'"
discuss the limits on RCS LEAKAGE rates.
Systems for separating the LEAKAGE of an identified source from an unidentified source are necessary to provide prompt and quantitative information to the operators to permit them to take immediate corrective action.
LEAKAGE from the RCPB inside the drywell is detected by at least one of two or three independently monitored variables, such as sump level changes and drywelt gaseous and particulate radioactivity lievels. The primary means of quantifying LEAKAGE in the drywell is the drywell floor drain sump monitoring system which consists of two drywell floor drain sump level Channels. Both Channels are required to be Operable to satisfy the LCO.
The dwell floor drain sump monitoring system monitors the LEAUGE collected in the floor drain sump. This unidentified LEAWGE consists of LEAKAGE from control rod drives, valve flanges or packings, floor drains, the Closed Cooling VVater System, and drpelt air cooling unit condensate drains, and any LEAWiGE not collected in the dwell equipment drain tank.
The level of each dwefl sump is continuously recorded in the Main Controt Room. The change in (continued)
SUSQUEHANNA - UNIT 2 TS / B 3.4-30 Revision 4-2 I
PPL Rev. @ f RCS Leakage Detection Instrumentation 8 3.4.6 BASES BACKGROUND sump level per unit time determines the leak rate and is calculated from the (continued) recorder.
The floor drain sump level indicators have switches that start and stop the sump pumps when required. If the sump fills tc? the high high level setpoint, an alarm sounds in the control room.
The primary containment air monitoring systems continuously monitor the primary containment atmosphere for airborne particulate and gaseous radioactivity. A sudden increase of radioactivity, which may be attributed to RCPB steam or reactor water LEAKAGE, is annunciated in the control room.
APPLf CABLE A threat of significant compromise to the RCPB exists if the barrier contains SAFETY a crack that is large enough to propagate rapidly. LWKAGE rate limits are ANALYSES set low enough to detect the LEAKAGE emitted from a single crack in the The allowed LEAKAGE rates are well al crack sizes (Ref. 6). Therefore, these
- provide adequate response before a significant break in the 1
RCPB can occur.
RCS leakage detection instrumentation satisfies Criterion 1 of the NRC Policy Statement (Ref. 7).
s two instruments to be OPERABLE.
1 (continued)
SUSQUEHANNA - UNIT 2 TS / B 3.4-31 Revision 81 f
PPL Rev. @ 1 RCS Leakage Detection fnstrumentation 8 3.4.6 BASES LC0 (continued)
The LC0 is satisfied when monitors of diverse measurement means are available. Thus, theJ (continued)
SUSQUEHAMNA - UNIT 2 TS / B 3.4-32 Revision 91 I
PPL Rev. % 1 RCS Leakage Detection Instrumentation B 3.4.6 BASES 1
LC0 (continued)
APPLfCABfLfN In MODES 1,2, and 3, leakage detection systems are required to be OPERABLE to support LC0 3.4.4. This Applicability is consistent with that for LC0 3.4.4.
ACTIONS A.l With the drywell floor drain sump monitoring system inoperable, the primary containment atmospheric activity monitor will provide indication of changes in leakage.
With the dryvvell floor drain sump monitoring system inoperable, operation may continue for 30 days. However, RCS unidentified and total LEAKAGE is still required to be determined every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> (SR 3.4.4.1). The 30 day Completion Time of Required Action A.l is acceptable, based on operating experience, considering the multiple forms of leakage detection that are still available.
3.1 and 8.2 With both gaseous and particulate primary containment atmospheric monitoring channels inoperable, grab samples of the primary containment atmosphere must be taken and analyzed to provide periodic leakage information, Provided a sample is obtained and analyzed once every 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />, the piant may be operated for up to 30 days to allow restoration of at least one of the requird monitors.
The 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> interval provides periodic information that is adequate to detect LEAKAGE. The 30 day hmpletion Time for restoration recognizes that at least one other form of leakage detection is available.
(continued)
SUSQUEHANNA - UNIT 2 TS I B 3.4-33 Revision 2 2 I
PPL Rev. 3 1 RCS Leakage Detection Instrumentation B 3.4.6 BASES ACTtONS C.1. C.2, and C.3.
(continued)
(conthued)
SUSQUEHANNA - UNIT 2 TS / B 3.4-34 Revision -12 1
PPL Rev. a 1
RCS Leakage Detection Instrumentation B 3.4.5 BASES ACT1 ONS GD.1 and GD.2 (continued)
I If any Required Action of Condition A+wB&
cannot be met within the
/
associated Completion Time, the plant must be brought to a MODE in which the LC0 does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> and MODE 4 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to perform the actions in an orderly manner and without challenging plant systems.
With all required monitors inoperable, no required automatic means of monitoring LEAKAGE are available, and immediate plant shutdown in accordance with LC0 3.0.3 is required.
SURVElLLANCE SR 3,4 REQUIREMENTS This SR is for the performance of a CHANNEL CHECK of the required primary containment atmospheric monitoring system. The check gives reasonable confidence that the channel is operating properly. The Frequency of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> is based on instrument reliability and is reasonable for detecting off normal conditions.
This SR is for the performance of a CHANNEL FUNCTIONAL TEST of the required RCS leakage detection instrumentation. The test ensures that the monitors can perform their function in the desired manner. The Frequency of 31 days considers instrument reliability, and operating experience has shown it proper for detming degradation.
This SR is for the performance of a CHANNEL CAtlESRATlON of required teakage detection instrumentation channels. The mlibration verifies the accuracy of the instrument string, including the instntments located inside containment. The Frequency of 24 months is a &pica1 refueling cycle and considers channel reliability.
(continued)
SUSQUEHANNA - UNIT 2 TS / B 3.4-34a Revision 4-2 I
PPL Rev. &@ 1 RCS Leakage Detection Instrumentation B 3.4.6 BASES REFERENCES
- 2. Regulatory Guide 1.45, e Detection Svsterns,'"May 1973.
I
- e.
GEAP-5620, April 1968.
1
- w.
NUREG-75/067, October 1975.
1 FSAR, Section 5.2.5.4.
I
- 6. FSAR. Section 5.2.5.1 -2.
I
- 7. Final Policy Statement on Technical Specifications Improvements, July 22, 1993 (58 FR 391 32).
SUSQUEHANNA - UNIT 2 Revision 8.1 f