RA-18-0232, Proposed Editorial Error Correction of Technical Specification (TS) 3.0, Surveillance Requirement Applicability, SR 3.0.5 and Proposed Removal of Expired TS Footnotes from the MNS
ML19042A117 | |
Person / Time | |
---|---|
Site: | Mcguire, McGuire ![]() |
Issue date: | 02/05/2019 |
From: | Teresa Ray Duke Energy Carolinas |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
RA-18-0232 | |
Download: ML19042A117 (30) | |
Text
Thomas D. Ray, P.E.
e.(~DUKE Site Vice President McGuire Nuclear Station
~ ENERGY Duke Energy MG01VP I 12700 Hagers Ferry Road Hyntersville, NC 28078 I o: 980.875.4805
- f: 980.875.4809 Tom.Ray@duke-energy.com Serial No. RA-18-0232 10 CFR 50.90 February 5, 2019 U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, D.C. 20555
Subject:
Duke Energy Carolinas, LLC (Duke Energy)
McGuire Nuclear Station (MNS), Units 1 and 2 Docket Numbers 50-369 and 50-370 Renewed Facility Operating License Nos. NPF-9 and NPF-17 Proposed editorial error correction of Technical Specification (TS) 3.0, SURVEILLANCE REQUIREMENT (SR) APPLICABILITY, SR 3.0.5 and proposed removal of expired TS footnotes from the MNS Unit 1 and Unit 2 TSs.
Pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (10 CFR), _Duke Energy Carolinas herein submits a license amendment request (LAR) for McGuire Nuclear Station (MNS) Unit 1 and 2. This request for amendment proposes to correct an editorial error contained in Technical Specification (TS) 3.0, SURVEILLANCE REQUIREMENT (SR)
APPLICABILITY, SR, 3.0.5 and proposes _removal of expired TS. footnotes from the M~S Unit 1 and Unit 2 TSs.
The proposed changes have been evaluated in accordance with 10 CFR 50.91(a)(1) using criteria in 10 CFR 50.92(c), and it has been determined that the proposed changes involve no significant hazards consideration. The bases for these determinations are included in the Enclosure.
U.S. Nuclear Regulatory Commission RA-18-0232 Page 2 The Enclosure provides the SR 3.~.5 and TS footnote descriptions, the proposed change~.
technical evaluation, regulatory evbluation, and environmental consideration for the requested changes. Attachment 1 provides markup copies of the affected TSs. Attachment 2 provides MNS TS Bases page markups for those TS Bases requiring changes (for information only). The TS Bases changes will be processed after LAR approval under the Duke Energy TS Bases Control Program. Reprinted (clean) TS pages will be provided to the NRC prior to issuance of the approved amendment.
In accordance with Duke Energy administrative procedures and Quality Assurance Program, this LAR has been reviewed and approved by the MNS Operations Review Committee.
Duke Energy requests approval of the proposed license amendments within one year of NRC acceptance, with the amendment being implemented within 120 days following approval.
Pursuant to 10 CFR 50.91, Duke *Energy is notifying the State of North Carolina of this LAR by transmitting a copy to the designated official.
This LAR contains no regulatory commitments.
Implementation of this proposed LAR will not impact the MNS Updated Final Safety Analysis Report (UFSAR).
If you have any questions concerning this LAR, or require additional information, please contact Joseph Hussey at 980-875-5045.
I declare under penalty of perjury that the foregoing is true and correct. Executed on February 5, 2019.
McGuire Nuclear Station Enclosure
U.S. Nuclear Regulatory Commission RA-18-0232 Page 3 cc:
C. Haney Region II Administrator U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Avenue NE, Suite 1200 Atlanta, GA 30303-1257 M. Mahoney Project Manager (MNS)
Michael.Mahoney@nrc.gov G.A. Hutto NRC Senior Resident Inspector McGuire Nuclear Station aridy.hutto@nrc.gov W.L. Cox, Ill Section Chief, North Carolina Department of Health and Human Services lee .cox@d hhs. nc.gov
U.S. Nuclear Regulatory Commission RA-18-0232 Page 4 bee (with Attachments):
E. R. Pigott N. E. Kunkel N. A. Smith Ill A. H. Zaremba J. F. Hussey (For MNS Licensing/Nuclear Records Files)
ELL (EC2ZF, NRCCorrespondences@duke-energy.com)
MNS Master File - MG02DM (file MC 801.01)
ENCLOSURE RA-18-0232 Page 1 of 7 EvalJation of the Proposed Changes
Subject:
License Amendment Request Proposing to correct an editorial error contained in Technical Specification (TS) 3.0, SURVEILLANCE REQUIREMENT (SR) APPLICABILITY, SR 3.0.5 and removal of expired TS notes from McGuire Nuclear Station (MNS) Unit 1 and Unit 2 TS.
- 1.
SUMMARY
DESCRIPTION
- 2. DETAILED DESCRIPTION
- 3. TECHNICAL EVALUATION
- 4. REGULATORY EVALUATION 4.1. Applicable Regulatory Requirements/Criteria 4.2. No Significant Hazards Consideration Determination Analysis 4.3. Conclusion
- 5. ENVIRONMENTAL CONSIDERATIONS ATTACHMENTS
- 1. Technical Specification Page Markups
- 2. Bases Page Markups
ENCLOSURE RA-18-0232
.Page 2 of 7
- 1. Summary Description Pursuant to Section 50.90 of Title 10 of the Code of Federal Regulations (1 O CFR), Duke Energy Carolinas (DEC) herein proposes to correct an editorial error contained in Technical Specification (TS) 3.0, SURVEILLANCE REQUIREMENT (SR) APPLICABILITY, SR 3.0.5 and proposes removal of expired Technical Specification (TS) footnotes from the MNS Unit 1 and Unit 2 TSs.
- 2. Detailed Description The proposed changes to Renewed Facility Operating License (FOL) NPF-9 and to Renewed FOL NPF-17 for the MNS Units 1 and 2, respectively, described below are administrative non-technical changes only.
Proposed correction to FOL NPF-9 and NPF-17 TS 3.0, SR APPLICABILITY, SR 3.0.5 2.1. By letter dated April 11, 2006, (Adams Accession Number ML061080409), DEC submitted a license amendment application for Technical Specification Change to Add/Revise LCO 3.0.8 on the lnoperability of Snubbers Using the Consolidated Line Item Improvement Process (CLIIP). By letter dated March 29, 2007, (Adams Accession Number ML063100490), the U.S. Nuclear Regulatory Commission issued Amendment No. 238 to FOL NPF-9 and Amendment No. 220 to FOL NPF-17. In the amendment application DEC proposed to renumber existing TS 3.0.8 to TS 3.0.9. DEC failed to provide the marked-up copy of page 3.0-6 showing the following change as being required.
SR 3.0.5 Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in LCO 3.0.i 9 for individual Specifications or whenever certain portions of a Specification contain surveillance parameters different for each unit, which will be identified in parentheses or footnotes.
DEC proposes to correct this editorial error as shown in Attachment 1.
Proposed changes to FOL NPF-9 and NPF-17 TS Footnotes.
2.2. By letter dated September 14, 2017, (Adams Accession Number ML17262A090), as supplemented by letter dated December 12, 2017, (Adams Accession Number ML17349A157), DEC proposed a LAR for the TSs for the MNS, Units 1 and 2, to allow temporary changes to TS 3.5.2, Emergency Core Cooling System (ECCS) - Operating; TS 3.6.6, Containment Spray System (CSS); TS 3.7.5, Auxiliary Feedwater System;
ENCLOSURE RA-18-0232 Page 3 of 7 (AFW) TS 3.7.6, Component Cooling Water Jew) System; TS 3.7.7, Nuclear Service Water System (NSWS); TS 3.7.9, Control Room Area Ventilation System (CRAVS); TS 3.7.11, Auxiliary Building Filtered Ventilation Exhaust System (ABFVES), and TS 3.8.1, .
AC Sources- Operating. The proposed amendment permitted the 'A' Train NSWS to be inoperable for a total of 14 days to address a non-conforming condition on the 'A' Train supply piping from the Standby Nuclear Service Water Pond (SNSWP). By letter dated February 15, 2018, (Adams Accession Number ML18030A682), the U.S. Nuclear Regulatory Commission issued Amendment No. 308 to FOL NPF-9 and Amendment No.
287 to FOL NPF-17 allowing the 'A' Train NSWS to be inoperable for a total of 14 days to address a non-conforming condition on the 'A' Train supply piping from the SNSWP.
The 'A' Train NSWS non-conforming condition associated with the 'A' Train supply piping from the SNSWP was resolved on May 3, 2018, therefore the associated TS footnotes are considered expired. DEC proposes to remove the expired footnotes from the above-mentioned TSs.
2.3. By letter dated October 28, 2013, (Adams Accession Number ML133048445), as supplemented by letter dated June 3, 2014, (Adams Accession Number ML14164A028),
DEC, submitted a license amendment request to modify TS 3.8.4, "DC Sources-Operating." Specifically, the change provided a one-time extension to the completion time for Required Action A.2.2 to support replacement of the existing shared 125 VDC Vital Batteries. By letter dated September 10, 2014, (Adams Accession Number ML14231A634), the U.S. Nuclear Regulatory Commission issued Amendment No. 274 to FOL NPF-9 and Amendment No. 254 to FOL NPF-17.
MNS completed replacement of the Vital Batteries in May 2016. The TS 3.8.4 footnote associated with Amendments 27 4 and 254 expired on December 31, 2016. DEC proposes to remove the expired footnote from TS 3.8.4.
2.4. By letter dated August 28, 2015, (Adams Accession Number ML152448179), as suppleniented by letter dated November 13, 2015, (Adams Accession Number ML15331A039), DEC, submitted a license amendment request to modify TS Completion Time for TS 3.5.2, "ECCS [Emergency Core Cooling System] - Operating," Condition A.
Specifically, the amendment would allow a one-time extension of the Completion Time to support maintenance on residual heat removal air handler unit 1A. By letter dated February 3, 2016, (Adams Accession Number ML16004A352), the U.S. Nuclear Regulatory Commission issued Amendment No. 281 to FOL NPF-9.
The TS 3.5.2 footnote associated with Amendment 281 expired on March 31, 2016. DEC proposes to remove the expired footnote from TS 3.5.2.
ENCLOSURE RA-18-0232 Page 4 of 7
- 3. T~chnical Evaluation The proposed change to SR 3.0.5 to correct the editorial error is an administrative non-technical change.
The proposed changes to TS 3.5.2, 3.6.6, 3.7.5, 3.7.6, 3.7.7, 3.7.9, 3.7.11 and 3.8.4 to remove the expired footnotes identified by a single asterisk, proposed change to TS 3.8.1 to remove the expired footnote identified by a double asterisk and the proposed change to TS 3.5.2 to remove the expired footnote identified by a single dagger are administrative non-technical changes.
Given the above, additional Technical Evaluation of the administrative non-technical changes proposed in this LAR is not necessary.
- 4. Regulatory Evaluation 4.1 Applicable Regulatory Requirements/Criteria The proposed changes in this LAR are administrative and non-technical in nature.
Upon approval and implementation of the proposed changes, MNS Units 1 and 2 will continue to comply with the applicable regulatory requirements and criteria discussed in the following Regulatory Evaluation:
- DEC's September 14, 2017, LAR, (Adams Accession Number ML17262A090),
as supplemented by letter dated December 12, 2017, (Adams Accession Number ML17349A157), which was approved by the NRC as .part of their February 15, 2018, SER, (Adams Accession Number ML18030A682).
- . DEC's October 28, 2013, LAR, (Adams AGcession Number ML133048445), as supplemented by letter dated June 3, 2014, (Adams Accession Number ML14164A028), which was approved by the NRC as part of their September 10, 2014, SER, (Adams Accession Number ML14231A634).
- DEC's August 28, 2015, LAR, (Adams Accession Number ML152448179), as supplemented by letter dated November 13, 2015, (Adams Accession Number ML15331A039), which was approved by the NRC as part of their February 3, 2016, SER, (Adams Accession Number ML16004A352).
ENCLOSURE RA-18-0232 Page 5 of 7
- I DEC's April 11, 2006, LAR, (Adams Accession NuJber ML061080409),
which was approved by the NRC as part of their March 29, 2007, SER, (Adams Accession Number ML063100490)
Therefore, additional discussion of the applicable regulatory requirements and criteria is not necessary.
4.2 No Significant Hazards Consideration Determination Analysis Pursuant to Section 50.90 of Title 1O of the Code of Federal Regulations (10 CFR), DEC herein submits a license amendment request (LAR) for McGuire Nuclear Station (MNS) Unit 1 and 2. This request for amendment proposes to correct an editorial error contained in Technical Specification (TS) 3.0, SURVEILLANCE REQUIREMENT (SR) APPLICABILITY, SR 3.0.5 and proposes removal of expired Technical Specification (TS) footnotes from the MNS Unit 1 and Unit 2 TSs.
DEC has evaluated whether a significant hazards consideration is involved with the proposed amendment by analyzing the three standards set forth in 10 CFR 50.92(c) as discussed below:
- 1) Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
This LAR proposes administrative non-technical changes only. These proposed changes do not adversely affect accident initiators or precursors nor alter the design assumptions, conditions, or configurations of the facility. The proposed changes do not alter or prevent the ability of structures, systems and components (SSCs) to perform their* intended function to mitigate the consequences of an initiating event within the assumed acceptance limits.
Given the above discussion, it is concluded the proposed amendment does not significantly increase the probability or consequences of an accident previously evaluated.
- 2) Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No.
ENCLOSURE RA-18-0232 Page 6 of 7 T~is LAR proposes administrative non-technical changes! only. The proposed changes will not alter the design requirements of any Structure, System or Component (SSC) or its function during accident conditions. No new or different accidents result from the proposed changes. The changes do not involve a physical alteration of the plant or any changes in methods governing normal plant operation. The changes do not alter
- assumptions made in the safety analysis.
Given the above discussion, it is concluded the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3) Does the proposed amendment involve a significant reduction in a margin of safety?
Response: No.
This LAR proposes administrative non-technicc;il changes only. The proposed changes do not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by these changes. The proposed changes will not result in plant operation in a configuration outside the design basis. The prop9sed changes do not adversely affect systems that respond to safely shutdown the plant and to maintain the plant in a safe shutdown condition.
- Given the above discussion, it is concluded the proposed amendment does not involve a significant reduction in the margin of safety.
4.3 Conclusion Based on the above, DEC concludes that the proposed amendment does not involve a significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and accordingly, a finding of no significant hazards consideration is justified.
- ENCLOSURE RA-18-0232 Page 7 of 7
- 5. Environmental bonsiderations This LAR proposes administrative non-technical changes only; DEC has determined that the propo$ed amendment does not change requirements with respect to the installation or use of a facility component located within the restricted area, as defined by 10 CFR 20. DEC has evaluated the proposed changes and has determined that they do not involve: (1) a significant .hazards consideration, (2) a significant change in the types or a significant increase in the amounts of any effluents that may be released offsite, or (3) a significant increase in individual or cumulative occupational radiation exposures. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(9). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment needs to be prepared in connection with the proposed amendment.
Attachment 1 Technical Specification Page Markups
SR Applicability 3.0 3.0 SR APPLICABILITY (continued)
SR 3.0.4 qntry into a MODE or other specified condition in the Ap~licability of an WCO shall only be made when the LCO's Surveillances Have been met within their specified Frequency, except as provided by SR 3.0.3. When an LCO is not met due to Surveillances not having been met, entry into a MODE or other specified condition in the Applicability shall only be made in accordance with LCO 3.0.4.
This provision shall not prevent entry into MODES or other specified conditions in the Applicability that are required to comply with ACTIONS or that are part of a shutdown of the unit.
SR 3.0.5 Surveillance Requirements shall apply to each unit individually unless otherwise indicated as stated in LCO 3.0.i 9 for individual Specifications or whenever certain portions of a Specification contain surveillance parameters different for each unit, which will be identified in parentheses or footnotes.
McGuire Units 1 and 2 3.0-6 Amendment Nos. 295/274
ECCS - Operating 3.5.2 3.5 EMERGENCY CORE COOLING SYSTEMS (ECCS) 3.5.2 ECCS- Operating LCO 3.5.2 Two ECCS trains shall be oPiERABLE.
APPLICABILITY: MODES 1, 2, and 3.
NOTE------------------------------------------------
ln MODE 3, both safety injection (SI) pump or RHR pump flow paths may be isolated by closing the isolation valves for up to 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to perform pressure isolation valve testing per SR 3.4.14.1.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One or more trains A.1 Restore train(s) to 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s~
inoperable. OPERABLE status.
AND At least 100% of the ECCS flow equivalent to a single OPERABLE ECCS train available.
B. Required Action and 8.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND 8.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />
'*'A' Train EGGS is allowed.to be inoperable for a total' of 14 days to address a nc:in conforming condition on 'the 'A' Train NSV\IS supply piping frem the Standby Nuclear Service Water Pond (SNSV\IP). The 14 days may be taken consecutively or in parts until completion of the activity, or by Marsh 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping frem the SNSVI/P is not available, the '/1.' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of '/1.' Train NSV\IS during the period in which the '/1.' NSIJ\IS from the SNSI/\IP supply piping is not available will be limited to a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures as described in MNS L/1.R submittal correspondence letter MNS 17 031.
t For Unit 1 only, the Completion Time for Required Action /1..1 may be extended one time to 10 days during the 1/1.
RHR /I.HU repair evolution and is contingent on meeting the compensatory measures described in MNS correspondence letter MNS 15 093. Upon completion of the repair evolution, this footnote is no longer applicable and will expire on March 31, 2016.
McGuire Units 1 and 2 3.5.2-1 Amendment Nos. 308/287
Containment Spray System 3.6.6 3.6 CONTAINMENT SYSTEMS 3.6.6 Containment*Spray System LCO 3.6.6 Two containment spray trains shall be OPERABLE. I I
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One containment spray A.1 Restore containment spray 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />!
train inoperable. train to OPERABLE status.
B. Required Action and 8.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND 8.2 Be in MODE 5. 84 hours9.722222e-4 days <br />0.0233 hours <br />1.388889e-4 weeks <br />3.1962e-5 months <br />
- 'A' Train Containment Spray is allmved to be inoperable for a total of 14 days to address a non conforming condition on the 'A' Train supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNS'NP is not available, the 'A' Train NSWS 111ill remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSVVS during the period in which the 'A' NSWS from the SNSVVP supply piping is not available will be limited to a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures described in MNS LAR submittal correspondence letter MNS 17 031.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 6. 6 .1 -----------------------------------NOTE--------------------------------
Not required to be met for system vent flow paths opened under administrative control.
Verify each containment spray manual and power In accordance with operated valve in the flow path that is not locked, sealed, the Surveillance or otherwise secured in position is in the correct position. Frequency Control Pro ram (continued)
McGuire Units 1 and 2 3.6.6-1 Amendment Nos. 308/287
AFW System 3.7.5
- 3. 7 PLANT SYSTEMS
- 3. 7 .5 Auxiliary Feedwater (AFW) System LCO 3.7.5 Three AFW trains shall be 6PERABLE.
-~-------------------------------------------NOl"E--------------------------------------------
Only one AFW train, which includes a motor driven pump, is required to be OPERABLE in MODE 4.
APPLICABILll"Y: MODES 1, 2, and 3, MODE 4 when steam generator is relied upon for heat removal.
ACl"IONS
NOl"E------------------------------------------------------------------------
LCO 3.0.4.b is not applicable when entering MODE 1.
CONDll"ION
- REQUIRED ACl"ION COMPLEl"ION l"IME A. One steam supply to A.1 Restore affected equipment 7 days turbine driven AFW to OPERABLE status.
pump inoperable. AND OR 10 days from discovery of
NOl"E------------ failure to Only applicable if MODE meet the LCO 2 has not been ente*red following refueling.
One turbine driven AFW pump inoperable in MODE 3 following refueling.
B. One AFW train 8.1 Restore AFW train to 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s~
inoperable in MODE 1, 2 OPERABLE status.
or 3 for reasons other AND than Condition A.
10 days from discovery of failure to meet the LCO
( continued)
McGuire Units 1 and 2 3.7.5-1 Amendment Nos 308/287
AFW System 3.7.5 ACTIONS ( continued)
CONDITION REQUIRED ACTION COMPLETION TIME
- b. Required Action and associated Completion C.1 Be in MODE t 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Time for Condition A AND or B not met.
C.2 Be in MODE 4. 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> OR Two AFW trains inoperable in MODE 1, 2, or 3.
D. Three AFW trains D.1 -------------NOTE-------------
inoperable in MODE 1, LCO 3.0.3 and all other 2, or 3. LCO Required Actions requiring MODE changes are suspended until one AFW train is restored to OPERABLE status.
Initiate action to restore Immediately one AFW train to OPERABLE status.
E. Required AFW train E.1 Initiate action to restore Immediately inoperable in MODE 4. AFW train to OPERABLE status.
- '/V Train AFVV is allmved to be inoperable for a total of 14 days to address a non conforming condition on the '/\' Train supply piping from the Standby Nuclear Service Water Pond (SNSVVP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSVVP is not available, the 'A' Train NSVVS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the '/\' NSWS from the SNSVVP supply piping is not available will be limited to a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. The latter will not count against the 14 day completion time. Allm.vance of the extended Completion Time is contingent on meeting the Compensatory Measures described in MNS LAR submittal correspondence letter MNS 17 031.
McGuire Units 1 and 2 3.7.5-2 Amendment Nos. 308/287
CCW System 3.7.6
- 3. 7 PLANT SYSTEMS 3.7.6 Component Cooling Water (CCW) System I
LCO 3.7.6 Two CCW trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CCW train A.1 -------------NOTE--------------
inoperable. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4,"
for residual heat removal loops made inoperable by CCW.
Restore CCW train to 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />!
OPERABLE status.
B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br />.
associated Completion Time of Condition A not AND met.
B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
- 'A' Train CCW is allmved to be inoperable for a total of 14 days to address a non conforming condition on the 'A' Train supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, 1Nhichever occurs first. During the period in which the '/\' Train NSWS supply piping from the SNSWP is not available, the
'A' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of
'A' Train NSWS during the period in which the 'A' NSVVS from the SNSVVP supply piping is not available will be limited to a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures as described in MNS LAR submittal correspondence letter MNS 17 031.
McGuire Units 1 and 2 3.7.6-1 Amendment Nos. 308/287
1NSWS 3.7.7
- 3. 7 PLANT SYSTEMS
- 3. 7. 7 Nuclear Service Water System (NSWS)
I LCO 3.7.7 Two NSWS trains shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One NSWS train A.1 -------------NOTES------------
inoperable. 1. Enter applicable Conditions and Required Actions of LCO 3.8.1, "AC Sources- Operating,"
for emergency diesel generator made inoperable by NSWS.
- 2. Enter applicable Conditions and Required Actions of LCO 3.4.6, "RCS Loops-MODE 4," for residual heat removal loops made inoperable byNSWS.
Restore NSWS train to 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s~
OPERABLE status.
B. Required Action and 8.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A not AND met.
8.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> McGuire Units 1 and 2 3.7.7-1 Amendment Nos. 308/287
- 'A' Train NSVI/S is allowed to be inoperable for a total of 14 days to address a non conforming condition on the 'A' Train supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, 1.vhichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSWP is not available, the '/1.' Train NSWS will remain aligned to Lake Norman until the system is ready for pos~ maintenance testing. /\ny maintenance that is I performed on the remaining portions of '/\' Train NSWS during the period in v.ihich the 'A' NSVVS from the SNSVVP supply piping is not available will be limited to a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures as described in MNS L/1.R submittal correspondence letter MNS 17 031.
SURVEILLANCE REQUIREMENTS SURVEILLANCE FREQUENCY SR 3. 7. 7 .1 --------------------------------NOTE----------------------------------
lsolation of NSWS flow to individual components does not render the NSWS inoperable.
Verify each NSWS manual, power operated, and In accordance with automatic valve in the flow path servicing safety related the Surveillance equipment, that is not locked, sealed, or otherwise Frequency Control secured in position, is in the correct position. Program SR 3.7.7.2 Verify each NSWS automatic valve in the flow path In accordance with servicing safety related equipment, that is not locked, the Surveillance sealed, or otherwise secured in position, actuates to the Frequency Control correct position on an actual or simulated actuation Program signal.
SR 3.7.7.3 Verify each NSWS pump starts automatically on an In accordance with actual or simulat~d actuation signal. the Surveillance Frequency Control Program McGuire Units 1 and 2 3.7.7-2 Amendment Nos. 308/287
1CRAVS 3.7.9
- 3. 7 PLANT SYSTEMS 3.7.9 Control Room Area Ventilation System (CRAVS)
I LCO 3.7.9 Two CRAVS trains shall be OPERABLE.
NOTE-----------------------------------------------
The control room envelope (CRE) boundary may be opened intermittently under administrative control.
APPLICABILITY: MODES 1, 2, 3, 4, 5, and 6, During movement of irradiated fuel assemblies, During CORE ALTERATIONS.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One CRAVS train A.1 Restore CRAVS train to 7 days~
inoperable for reasons OPERABLE status.
other than Condition B.
B. One or more CRAVS 8.1 Immediately trains inoperable due to Initiate action to implement inoperable CRE mitigating actions.
boundary in MODE 1,2,3, or 4.
AND 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> 8.2 Verify mitigating actions ensure CRE occupant exposures to radiological, chemical, and smoke hazards will not exceed limits.
AND 90 days 8.3 Restore CRE boundary to OPERABLE status.
C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time of Condition A or B AND not met in MODE 1, 2, 3, or 4. C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
( continued)
McGuire Units 1 and 2 3.7.9-1 Amendment No. 308/287
CRAVS 3.7.9 CONDITION REQUIRED ACTION COMPLETION TIME One or more CRAVS G.1 Restore CRAVp train(s) 7 days train(s) heater heater to OPERABLE inoperable. status.
OR G.2 Initiate action in 7 days accordance with Specification 5.6.6.
- '/\' Train CRAVS is allmved to be inoperable for a total of 14 days to address a non conforming condition on the '/\.' Train supply piping from the Standby Nuclear Service Water Pond (SNSVVP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the 'A' Train NSWS supply piping from the SNSVVP is not available, the '/\.' Train NSVVS will remain aligned to Lake Norman until the system is ready for post maintenance testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSVVP supply piping is not available *.viii be limited to a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. The latter *.viii not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures as described in MNS L/\.R submittal correspondence letter MNS 17 031.
McGuire Units 1 and 2 3.7.9-3 Amendment No. 308/287
ABFVES 3.7.11
- 3. 7 PLANT SYSTEMS
- 3. 7 .11 Auxiliary Building Filtered Ventilation Exhaust System (ABFVES)
I LCO 3.7.11 Two ABFVES shall be OPERABLE.
NO TE----------------------------------------------------
Th e Auxiliary Building pressure boundary may be opened intermittently under administrative controls.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One ABFVES A.1 Restore ABFVES to 7 days!.
inoperable. OPERABLE status.
B. TwoABFVES B.1 Restore one ABFVES to 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> inoperable. OPERABLE status.
C. Required Action and C.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> associated Completion Time not met. AND C.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
- 'N Train ABFVES is alloi.ved to be inoperable for a total of 14 days to address a non sonforming sondition on the 'A' Train supply piping from the Standby Nuslear Servise Water Pond (SNS'JVP). The 14 days may be taken sonsesutively or in parts until sompletion of the astivity, or by Marsh 31, 2019, whishever ossurs first. During the period in whish the 'A' Train NSVVS supply piping from the SNSWP is not available, the
'A' Train NSWS will remain aligned to Lake Norman until the system is ready for post maintenanse testing. Any maintenanse that is performed on the remaining portions of
'A' Train NSWS during the period in whish the 'A' NSWS from the SNSWP supply piping is not available will be limited to a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> sompletion time. The latter will not sount against the 14 day sompletion time. Allowanse of the extended Completion Time is sontingent on meeting the Compensatory Measures as dessribed in MNS LAR submittal sorrespondense letter MNS 17 031.
McGuire Units 1 and 2 3.7.11-1 Amendment No. 308/287
AC Sources - Operating 3.8.1 ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME B. Jcontinued) B.4 Restore DG to OPEiBLE 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s~
status.
AND 6 days from discovery of failure to meet LCO C. Two offsite circuits C.1 Declare required feature(s) 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> from inoperable. inoperable when its discovery of redundant required Condition C feature(s) is inoperable. concurrent with inoperability of redundant required feature(s)
AND C.2 Restore one offsite circuit 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> to OPERABLE status.
(continued)
- 'A' Train EDGs are allmved to be inoperable for a total of 14 days to address a non conforming condition on the 'A' Train supply piping from the Standby Nuclear Service Water Pond (SNSWP). The 14 days may be taken consecutively or in parts until completion of the activity, or by March 31, 2019, whichever occurs first. During the period in which the '/\' Train NSVVS supply piping from the SNSVVP is not available, the 'A' Train NSVVS 111ill remain aligned to Lake Normc;m until the system is rpady for post mainten~nce testing. Any maintenance that is performed on the remaining portions of 'A' Train NSWS during the period in which the 'A' NSWS from the SNSVVP supply piping is not available will be limited to a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> completion time. The latter will not count against the 14 day completion time. Allowance of the extended Completion Time is contingent on meeting the Compensatory Measures as described in MNS LAR submittal correspondence letter MNS 17 031.
McGuire Units 1 and 2 3.8.1-3 Amendment No. 308/287
DC Sources - Operating 3.8.4 3.8 ELECTRICAL POWER SYSTEMS I 3.8.4 DC Sources- Operating LCO 3.8.4 The four channels of DC sources shall be OPERABLE.
APPLICABILITY: MODES 1, 2, 3, and 4.
ACTIONS CONDITION REQUIRED ACTION COMPLETION TIME A. One channel of DC A.1 Restore channel of DC 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> source inoperable. source to OPERABLE status.
OR A.2.1 Verify associated bus tie 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> breakers are closed between DC channels.
AND A.2.2 Restore channel of DC 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />!:
source to OPERABLE status.
.B. Required Action and B.1 Be in MODE 3. 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> Associated Completion Time not met. AND B.2 Be in MODE 5. 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />
- The Completion Time that one channel of DC source can be inoperable as specified by Required Action A.2.2 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" for up to 14 days as part of the battery replacement project. This allowance may be used one time for each of the four DC channels. Upon completion of the battery replacement project, this footnote is no longer applicable and 1Nill expire on December 31, 2016.
McGuire Units 1 and 2 3.8.4-1 Amendment No. 274/254
Attachment 2 Bases Page Markups For !~formation Only
ECCS-Operating B 3.5.2 BASES ACTIONS (continued)
An event accompanied by a loss of offsite power and the failure of an EOG can disable one EQCS train until power is restored. A reliability analysis (Ref. 6) has shown that the impact of having one full ECCS train inoperable is sufficiently small to justify continued operation for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />.
Reference 7 describes situations in which one component, such as an RHR crossover valve, can disable both ECCS trains. With one or more component(s) inoperable such that 100% of the flow equivalent to a single OPERABLE ECCS train is not available, the facility is in a condition outside the accident analysis. Therefore, LCO 3.0.3 must be immediately entered.
As part of the 1A RHR AHU repair evolution, the Completion Time that one train of EGGS can be inoperable as specified by Required Action A.1 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" for up to 10 days (on Unit 1 only). This allowance may be used one time for the 1A RHR AHU repair.
Upon completion of the repair and restoration, the Completion Time footnote is no longer applicable and \Viii expire on March 31, 2016. The commitments from the LAR submittal are as follows:
Commitment The following SSCs will be protected prior to.the 1A RHR AHU repair evolution, and elective maintenance to them will be deferred during the repairs to the 1A RHR pump motor Al=<<h
- 1B RHR train
- 1B Nuclear Service 'Nater System (NSVVS) train
- 1B Component Cooling Water System (CC'NS) train
- 1B Emergency Diesel Generator (EOG)
- Power supply to the alternate cooling equipment 4
McGuire Units 1 and 2 B 3.5.2-7 Revision No. 449
ECCS-Operating B 3.5.2 BASES ACTIONS (continued}
- ~::~1::a::~~~:f:!~:::::gr:::~:
minimize the chance of fire induced LOCAs:
- Unit 1 4.16kV Switchgear Rooms
- Unit 1 Auxiliary Feedwater Pump Room
- 1B Diesel Generator Room
- Fire Area 14 vicinity of 1/2EMXB 1
- Fire Area 19 vicinity of 1/2EMXG 7 Prior to the 1A RHR AHU repair evolution, procedures will have been developed to start the alternate cooling 1.vhen required, and personnel will be designated to ensure that the equipment is started before room temperatures exceed the limits.
8.1 and 8.2 If the inoperable trains cannot be returned to OPERABLE status within the associated Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> -and MODE 4 within 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.5.2.1 REQUIREMENTS Verification of proper valve position ensures that the flow path from the ECCS pumps to the RCS is maintained. Misalignment of these valves could render both ECCS trains inoperable. Securing these valves using the power disconnect switches in the correct position ensures that they cannot change position as a result of an active failure or be inadvertently misaligned. These valves are of the type, described in Reference 7, that can disable the function of both ECCS trains and invalidate the accident analyses. The Surveillance Frequency is based on operating experience, equipment reliability, and plant risk and is controlled under the Surveillance Frequency Control Program.
SR 3.5.2.2 Verifying the correct alignment for manual, power operated, and automatic valves in the ECCS flow paths provides assurance that the proper flow paths will exist for ECCS operation. This SR does not apply McGuire Units 1 and 2 B 3.5.2-8 Revision No. 49
NSWS B 3.7.7 BASES ACTIONS (continued)
This is an exception to LCO 3.0.6 and ensures the proper actions are taken for the~e components. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time is based on the redundant capabilities afforded by the OPERABLE train, and the low probability of a DBA occurring during this time period.
A onetime change to TS 3.7.7 extends Action A.1 completion time (CT) from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 14 days. The change also affects TS 3.5.2, Emergency Core Cooling System (EGGS) Operating; TS 3.6.6, Containment Spray System (CSS); TS 3.7.5, Auxiliary Feedwater (AFVV) System; TS 3.7.6, Component Cooling Water (CON)
System; TS 3.7.7, Nuclear Service Water System (NSVVS); TS 3.7.9, Control Room Area Ventilation System (CRAVS); TS 3.7.11, Auxiliary Building Filtered Ventilation Exhaust System (ABFVES), and TS 3.8.1, AC Sources Operating ..
B.1 and B.2 If the NSWS train cannot be restored to OPERABLE status within the associated Completion Time, the unit must be placed in a MODE in which the LCO does not apply. To achieve this status, the unit must be placed in at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and in MODE 5 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 reach the required unit conditions from full power conditions in an orderly manner and without challenging unit systems.
McGuire Units 1 and 2 B 3.7.7-4 Revision No. 4.§g
DC Sources-Operating B 3.8.4 BASES ACTIONS (continued)
If one of the required channels of DC is inoderable (e.g., inoperable battery, inoperable battery charger(s), or inoperable battery charger and associated inoperable battery), the remaining DC channels have the capacity to support a safe shutdown and to mitigate an accident condition. If the channel of DC cannot be restored to OPERABLE status, Action A.2 must be entered and the DC channel must be energized from an OPERABLE channel; from the same train, within 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />. The capacity of the redundant channel is sufficient to supply its normally supplied channel and cross tied channel for the required time, in case of a OBA event. The inoperable channel of DC must be returned to OPERABLE status within 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> and the cross ties to the other channel open. The 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> Completion Time reflects a reasonable time to assess unit status as a function of the inoperable channel of DC and, if the DC channel is not restored to OPERABLE status, to prepare to effect an orderly and safe unit shutdown.
As part of the battery replacement project, the Completion Time that one channel of DC source can be inoperable as specified by Required Action A2.2 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" for up to 14 days. This allowance may be used one time for each of the four DC channels. Upon completion of the battery replacement project, the Completion Time footnote is no longer applicable and will expire on December 31, 2016.
B.1 and B.2 If the inoperable chann_el of DC cannot be restored to OPERABLE status within the required Completion Time, the unit must be brought to a MODE in which the LCO does not apply. To achieve this status, the unit must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 5 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 reach the required unit conditions from full power conditions in an orderly manner and without challenging plant systems.
The Completion Time to bring the unit to MODE 5 is consistent with the time requirec;j in Regulatory Guide .1.93 (Ref. 9).
SURVEILLANCE SR 3.8.4.1 REQUIREMENTS Verifying battery terminal voltage while on float charge for the batteries helps to ensure the effectiveness of the charging system and the ability of the batteries to perform their intended function. Float charge is the condition in which the charger is supplying the continuous charge required to overcome the internal losses of a battery (or battery cell) and maintain the battery (or a battery cell) in a fully charged state. The voltage requirements are based on the nominal design voltage of the battery and are consistent with the initial voltages assumed in the battery McGuire Units 1 and 2 B 3.8.4-4 Revision No. ~