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MONTHYEARML0815405932008-09-0909 September 2008 (MNGP) - Review of Licensee'S 3-Month Response to Generic Letter 2008-01 (Tac No. MD7847) Project stage: Approval L-MT-08-063, Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems.2008-10-14014 October 2008 Nine-Month Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. Project stage: Other ML0919504162009-07-0606 July 2009 Supplemental Response to NRC Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems. Project stage: Supplement ML0921101112009-07-30030 July 2009 Draft RAI on Response to GL 2008-01 Project stage: Draft RAI ML1030602072010-11-0101 November 2010 Draft RAI on the Licensee'S Submittals in Response to Generic Letter 2008-01 Project stage: Draft RAI L-MT-11-018, Response to Request for Additional Information Related to Generic Letter 2008-012011-05-20020 May 2011 Response to Request for Additional Information Related to Generic Letter 2008-01 Project stage: Response to RAI ML1117106372011-06-23023 June 2011 Closeout of Generic Letter 2008-01 Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems TAC MD7847 Project stage: Other L-MT-15-048, License Amendment Request: Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process2015-07-15015 July 2015 License Amendment Request: Revise Technical Specifications to Adopt TSTF-523, Generic Letter 2008-01, Managing Gas Accumulation, Using the Consolidated Line Item Improvement Process Project stage: Request 2009-07-06
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MONTHYEARL-MT-23-054, Subsequent License Renewal Application Supplement 82024-01-11011 January 2024 Subsequent License Renewal Application Supplement 8 L-MT-23-047, License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data2023-12-29029 December 2023 License Amendment Request: Revision to the MNGP Pressure Temperature Limits Report to Change the Neutron Fluence Methodology and Incorporate New Surveillance Capsule Data L-MT-23-056, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 22023-12-18018 December 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 Part 2 L-MT-23-042, 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462023-12-11011 December 2023 2023 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-23-052, Subsequent License Renewal Application Supplement 72023-11-30030 November 2023 Subsequent License Renewal Application Supplement 7 L-MT-23-051, Update to the Technical Specification Bases2023-11-28028 November 2023 Update to the Technical Specification Bases L-MT-23-049, Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 12023-11-21021 November 2023 Subsequent License Renewal Application Response to Request for Additional Information and Request for Confirmation of Information - Set 1 L-MT-23-043, 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-092023-11-13013 November 2023 10 CFR 50.55a(z)(1) Request Regarding OMN-17, Revision 1. VR-09 L-MT-23-038, License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.62023-11-10010 November 2023 License Amendment Request to Revise Monticello Technical Specification Surveillance Requirement 3.8.6.6 L-MT-23-046, Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 12023-11-0909 November 2023 Subsequent License Renewal Application Response to Request for Additional Information Round 2 - Set 1 L-MT-23-041, Subsequent License Renewal Application Response to Request for Confirmation of Information Set 22023-10-0303 October 2023 Subsequent License Renewal Application Response to Request for Confirmation of Information Set 2 L-MT-23-037, Subsequent License Renewal Application Response to Request for Additional Information Set 32023-09-22022 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 3 L-MT-23-036, Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 62023-09-0505 September 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 2 and Supplement 6 L-MT-23-035, Subsequent License Renewal Application Supplement 52023-08-28028 August 2023 Subsequent License Renewal Application Supplement 5 L-MT-23-034, Subsequent License Renewal Application Response to Request for Additional Information Set 12023-08-15015 August 2023 Subsequent License Renewal Application Response to Request for Additional Information Set 1 L-MT-23-028, 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report2023-07-31031 July 2023 2023 Refueling Outage 90-Day Inservice Inspection (ISI) Summary Report L-MT-23-032, 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-112023-07-31031 July 2023 10 CFR 50.55a(z)(2) Request Regarding MO-2397, VR-11 L-MT-23-031, Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 12023-07-18018 July 2023 Subsequent License Renewal Application Supplement 4 and Responses to Request for Confirmation of Information - Set 1 L-MT-23-030, Subsequent License Renewal Application Supplement 32023-07-0404 July 2023 Subsequent License Renewal Application Supplement 3 L-MT-23-025, Subsequent License Renewal Application Supplement 22023-06-26026 June 2023 Subsequent License Renewal Application Supplement 2 L-MT-23-019, Submittal of 2022 Annual Radiological Environmental Operating Report2023-05-10010 May 2023 Submittal of 2022 Annual Radiological Environmental Operating Report L-MT-23-020, Submittal of 2022 Annual Radioactive Effluent Release Report2023-05-10010 May 2023 Submittal of 2022 Annual Radioactive Effluent Release Report L-MT-23-021, Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 322023-05-0202 May 2023 Core Operating Limits Report (COLR) for the Monticello Nuclear Generating Plant for Cycle 32 L-MT-23-017, 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP)2023-04-18018 April 2023 2022 Annual Report of Individual Monitoring for the Monticello Nuclear Generating Plant (MNGP) L-MT-23-010, Subsequent License Renewal Application Supplement 12023-04-0303 April 2023 Subsequent License Renewal Application Supplement 1 L-MT-23-013, Core Operating Limits Report (COLR) for Cycle 31, Revision 32023-03-28028 March 2023 Core Operating Limits Report (COLR) for Cycle 31, Revision 3 L-MT-23-012, Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 22023-03-17017 March 2023 Core Operating Limits Report (COLR) for Monticello Nuclear Generating Plant Cycle 31, Revision 2 L-MT-23-008, 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003)2023-02-0707 February 2023 10CFR50.55a Request to Use Later Edition of ASME Section XI for ISI Code of Record (RR-003) L-MT-23-004, CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program2023-01-23023 January 2023 CFR 50.55a Request RR-001, Request to Use a Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI for the Monticello Third Interval Containment Inservice Inspection Program L-MT-23-005, Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088)2023-01-0606 January 2023 Response to the NRC Request for Additional Information Regarding the 50.55a Request Pr 08, HPCI Pump Quarterly Testing (EPID Number L-2022-LLR-0088) L-MT-22-049, Industry Groundwater Protection Initiative Special Report2022-12-15015 December 2022 Industry Groundwater Protection Initiative Special Report L-MT-22-052, L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative2022-12-15015 December 2022 L-MT-22-052 Monticello Nuclear Generating Plant 10 CFR 50.55a Request No. Pr 08, Request for HPCI Pump Quarterly Alternative L-MT-22-046, 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.462022-12-13013 December 2022 2022 Annual Report of Changes in Emergency Core Cooling System Evaluation Models Pursuant to 10 CFR 50.46 L-MT-22-048, Update to the Monticello Technical Specification Bases2022-11-28028 November 2022 Update to the Monticello Technical Specification Bases L-MT-22-047, Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-11-10010 November 2022 Withdrawal of Request for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-045, Letter Submitting Post-Exam Package2022-11-0404 November 2022 Letter Submitting Post-Exam Package L-MT-22-030, Sixth Interval Inservice Testing (1ST) Plan2022-09-0606 September 2022 Sixth Interval Inservice Testing (1ST) Plan L-MT-22-037, Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-08-29029 August 2022 Supplement to 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval, Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-007, Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007)2022-07-22022 July 2022 Response to Request for Additional Information for the Monticello Nuclear Generating Plant Alternative Request VR-08 (EPID: L-MT-22-007) L-MT-22-026, Changes to the Emergency Plan2022-07-19019 July 2022 Changes to the Emergency Plan L-MT-22-024, Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies2022-06-0606 June 2022 Response to a Request for Additional Information for the Monticello Nuclear Generating Plant Related to the Amendment to Adopt Advanced Framatome Methodologies L-MT-22-022, Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency2022-05-25025 May 2022 Response to a Request for Additional Information: Monticello Alternative VR-10, Excess Flow Check Valve Testing Frequency L-MT-22-017, 2021 Annual Radiological Environmental Operating Report2022-05-11011 May 2022 2021 Annual Radiological Environmental Operating Report L-MT-22-018, 2021 Annual Radioactive Effluent Release Report2022-05-11011 May 2022 2021 Annual Radioactive Effluent Release Report L-MT-22-016, 2021 Annual Report of Individual Monitoring2022-04-28028 April 2022 2021 Annual Report of Individual Monitoring L-MT-22-019, Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval2022-04-18018 April 2022 Withdrawal of Requests for Relief from ASME OM Code for the Sixth Inservice Testing Interval L-MT-22-010, License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency2022-03-18018 March 2022 License Amendment Request to Revise Technical Specification 3.6.1.8 Residual Heat Removal (RHR) Drywell Spray Header and Nozzle Surveillance Frequency L-MT-22-012, Special Report for the Bypass of the Offgas Treatment Storage System2022-03-15015 March 2022 Special Report for the Bypass of the Offgas Treatment Storage System L-MT-22-008, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008)2022-03-0707 March 2022 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval Alternative Related to Excess Flow Check Valve Testing Frequency (L-MT-22-008) L-MT-22-006, 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006)2022-02-18018 February 2022 10 CFR 50.55a Request Associated with the Monticello Sixth Inservice Testing Ten-Year Interval OMN-26 (L-MT-22-006) 2024-01-11
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Xcel Energy* May 20,201 1 Monticello Nuclear Generating Plant 2807 W County Road 75 Monticello, MN 55362 L-MT-11-018 10 CFR 50.54(f) U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555 Monticello Nuclear Generating Plant Docket 50-263 Renewed Facility Operating License No.
DPR-22 Response to Request for Additional Information Related to Generic Letter 2008-01
References:
- 1) U.S. NRC Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," dated January 11, 2008. 2) NMC to NRC, "Generic Letter 2008-01: Three Month Response to Generic Letter 2008-01
," (L-MT-08-026) dated April 11, 2008. 3) NRC to NMC, "Monticello Nuclear Generating Plant (MNGP) - Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," Proposed Alternative Course of Action (TAC No. MD7847)," dated September 9, 2008. 4) NMC to NRC, "Nine-Month Response to NRC Generic Letter 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" (TAC No. MD7847)," (L-MT-08-063) dated October 14, 2008. 5) NSPM to NRC, "Monticello Nuclear Generating Plant Nine-Month Supplemental (Post-Outage)
Response to NRC Generic Letter 2008-01 ," (L-MT-09-079) dated August 14, 2009.
- 6) E-mail from P. Tam (NRC) to R. Loeffler (NSPM), "Monticello - Draft RAI on response to Generic Letter 2008-01 re. gas accumulation in ECCS etc. (TAC MD7847).jJ (Accession No.
ML103060207)
On January 11,2008, the U.S. Nuclear Regulatory Commission (NRC) issued Generic Letter (GL) 2008-01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," (Reference 1).
Northern States Power Company, a Minnesota corporation (NSPM), doing business as Xcel Energy has Document Control Desk L-MT-1 1-018 Page 2 of 2 provided responses to GL 2008-01 in a series of letters listed above. The responses to the NRC e-mail request for additional information (RAI) (Reference
- 6) are provided in Enclosure 1.
If you have any questions or require additional information, please contact Mr. Richard Loeffler at (763) 295-1 247. Summary of Commitments This letter proposes no new commitments and does not revise any existing commitments. that the foregoing is true and correct. clear Generating Plant Enclosure cc: Regional Administrator, Region Ill, USNRC Project Manager, Monticello Nuclear Generating Plant, USNRC Resident Inspector, Monticello Nuclear Generating Plant, USNRC Minnesota Department of Commerce ENCLOSURE 1 MONTICELLO NUCLEAR GENERATING PLANT RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2008-01 L-MT-11-018 Enclosure 1 Page 1 of 5 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2008-01 The U .S. Nuclear Regulatory Commission (NRC) requested in (Reference
- 1) additional information to complete their review of the Monticello Nuclear Generating Plant (MNGP) response to Generic Letter 2008-01. By letters dated April 11, 2008 (Accession No. ML081020695)
[Reference 21, October 14,2008 (Accession No. ML082880602)
[Reference 31, and August 14, 2009, (Accession No. ML92290180)
[Reference 41, the licensee submitted information in response to Generic Letter 2008-01 "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," (Reference 5), for Monticello Nuclear Generating Plant (MNGP). On the basis of the provided information, the NRC staff has concluded that additional information is needed to determine that the licensee has acceptably demonstrated "that the subject systems are in compliance with the current licensing and design bases and applicable regulatory requirements, and that suitable design, operational, and testing control measures are in place for maintaining this compliance" as stated in Generic Letter (GL) 2008-01. 1. In the Licensing Basis evaluation section, the licensee stated that Technical Specification
[TS] Surveillance Requirement
[SR] 3.5.1 .I does not address emergency core cooling system (ECCS) suction piping, high pressure ECCS piping, decay heat removal, or containment spray piping. What actions are being taken to ensure that the areas not addressed in the TS SR are operable?
Surveillance Requirements (SR) 3.5.1.1 and SR 3.5.2.2 require verifying every 31 days for each ECCS injection 1 spray subsystem(') that the piping is filled with water from the pump discharge valve to the injection valve.
As discussed in the nine-month MNGP Generic Letter 2008-01 response,(*)
however, system design features together with other TS surveillance requirements and fill and vent procedures provide assurance that portions of piping not addressed by the "filled with water" criteria of surveillance requirements SR 3.5.1 .I or SR 3.5.2.2 are operable.
A summary discussion is provided below:
- 1. The low pressure ECCS consists of the Core Spray system and Residual Heat Removal (RHR) system operating in the Low Pressure Coolant Injection (LPCI) mode. RHR has several operational modes and performs the decay heat removal (shutdown cooling), suppression pool cooling, and containment spray functions in addition to ECCS operation in the LPCI mode. 2. See the "Summary of Design Review" and "New Applicable Gas Volume Acceptance Criteria" sections of the NSPM nine-month GL response for the MNGP (Reference 3).
L-MT-11-018 Enclosure 1 Page 2 of 5 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2008-01 Suction Pipinq 0 The suction piping for the low pressure ECCS,(') is maintained filled by maintaining the suppression pool (SP) water level in accordance with TS surveillance requirements.
0 The shutdown cooling (decay heat removal) and containment spray modes of RHR do not have any specified gas accumulation criterion as part of their licensing basid3) but share the common RHR suction piping maintained full by the SP. The suction for the high pressure ECCS, i.e., HPCI, is normally aligned to the Condensate Storage Tanks (CSTs). The height of water in the CSTs maintains the suction piping full up to the first closed isolation valve in accordance with the TS SRs. Suction automatically transfers to the SP on low CST water level or high SP water level. When HPCl is aligned to the SP the suction piping is maintained filled by maintaining the SP water level in accordance with TS surveillance requirements. Discharge Piping The low pressure ECCS contains pressurizing stations supplied by the Condensate Service System (a type of keep-fill) to maintain the piping between the associated pump discharge valve up to the outboard injection valve pressurized. Although the shutdown cooling (decay heat removal) and containment spray modes of RHR do not have any specified gas accumulation criterion as part of their licensing basid3) the discharge side of these systems up to the outboard injection valve experience keep-fill pressure due to sharing common RHR system piping. At the HPCl injection va~ve(s)(~) steam void formation has occurred due to the high temperature Feedwater on the downstream side of the injection valves.
While void formation in the HPCl discharge piping has been analyzed and determined acceptable, a modification applying the Condensate System as a 3. SR 3.5.T.1 and SR 3.5.2.2 apply only to the Core Spray and LPCl modes of RHR, requiring the piping between the pump discharge and injection valves to be "filled with water." 4. HPCl injects via the Feedwater system piping. Although the keep-fill feature is not required for HPCl operability, it is normally available and HPCl operability would be evaluated, as needed, upon loss of the keep-fill.
L-MT-11-018 Enclosure 1 Page 3 of 5 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2008-01 keep-fill system was installed to maintain the piping between the pump discharge check valve and injection valve filled with water to prevent void formation. Piping Downstream of Injection Valves A generic analysid5) of the low pressure ECCS and containment spray piping downstream of the normally-closed injection valves was completed and a determination made that the existence of air voids in this piping will have no adverse consequences related to accident conditions.
As, previously indicated, HPCl injects via the Feedwater piping.
Procedures As discussed in detail under Section Ill, "Testing and Evaluation" of the nine-month MNGP GL 2008-01 response, the surveillance and fill and vent procedures (which require venting at the high point locations in the respective systems) were reviewed and determined acceptable. 2. lndustry guidance on acceptable void criteria for suction piping has been updated since submittal of Monticello's 9-month response (see Reference 8). Please provide updated void acceptance criteria, if applicable.
Since the MNGP nine-month response to Generic Letter 2008-01 was submitted in October 2008, industry guidance on acceptable void criteria for suction piping has continued to develop. NSPM has adopted the most current guidance for void evaluation, entitled, "Industry Guidance for Evaluation of Unexpected Voids or Gas Identified in Plant ECCS and Other Systems," that was provided in a letter from the Nuclear Energy Institute (NEI) to the NRC on June 18, 2009 (Reference 6). This guidance has been added to the Monticello operability assessment process.
- 5. Discussed in the MNGP nine-month GL response under the gas volume acceptance criteria section (Reference 3).
L-MT-11-018 Enclosure 1 Page 4 of 5 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2008-01 3. Training was not identified in the GL but is considered to be a necessary part of applying procedures and other activities when addressing the issues identified in the GL. Please briefly discuss training.
As noted in the question, the GL did not specifically cover training and thus, this area was not included in our nine-month response. Training on gas intrusion and accumulation was developed based in-part on the recommendations of Institute of Nuclear Power Operations (INPO) SER 2-05, "Gas Intrusion in Safety Systems," together with industry experience.
Training on gas intrusion and accumulation is provided as part of initial training for licensed Operators and as continuing training on a three year cycle. Gas intrusion and accumulation is included in the responsibilities of the Engineer responsible for the Gas Accumulation Program, training was provided on a one-time basis to Engineering personnel.
L-MT-11-018 Enclosure 1 Page 5 of 5 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION RELATED TO GENERIC LETTER 2008-01 References
- 1. E-mail from P. Tam (NRC) to R. Loeffler (NSPM), "Monticello - Draft RAI on response to Generic Letter 2008-01 re. gas accumulation in ECCS etc. (TAC MD7847 )," dated November I, 201 0. (Accession No.
ML103060207)
- 2. NMC to NRC, "Generic Letter 2008-01: Three Month Response to Generic Letter 2008-01
," (L-MT-08-026) dated April 11, 2008. 3. NMC to NRC, "Nine-Month Response to NRC Generic Letter 2008 01, "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems" (TAC No.
MD7847),li (L-MT-08-063) dated October 14, 2008. 4. NSPM to NRC, "Monticello Nuclear Generating Plant Nine-Month Supplemental (Post-Outage)
Response to NRC Generic Letter 2008-01 ," (L-MT-09-079) dated August 14,2009. 5. U.S. NRC Generic Letter 2008-01 "Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems," dated January 11,2008. 6. NEI (J. Riley) to NRC (W. Ruland), "
Subject:
Industry Guidance - Evaluation of Unexpected Voids or Gas Identified in Plant ECCS and Other Systems," dated June 18,2009. (ADAMS Accession Nos.
ML091800416 and ML091800418)