ML14231A075
| ML14231A075 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 08/27/2014 |
| From: | Beltz T Plant Licensing Branch III |
| To: | |
| Chawla M | |
| Shared Package | |
| ML14231A228 | List: |
| References | |
| TAC MF4483, TAC MF4484 | |
| Download: ML14231A075 (6) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 August 2 7, 2014 LICENSEE:
INDIANA MICHIGAN POWER COMPANY FACILITIES: DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2
SUBJECT:
SUMMARY
OF THE AUGUST 8, 2014, PRE-APPLICATION MEETING TO DISCUSS PENDING LICENSE AMENDMENT REQUEST ASSOCIATED WITH THE IMPLEMENTATION OF ALTERNATIVE SOURCE TERM AND TECHNICAL SPECIFICATION TASK FORCE TRAVELER (TSTF)-490 (TAC NOS. MF4483 AND MF4484)
On August 8, 2014, a Category 1 public meeting was held via teleconference between the U.S.
Nuclear Regulatory Commission (NRC) staff and representatives of Indiana Michigan Power Company (I&M, the licensee). The purpose of the meeting was to discuss the licensee's pending license amendment request (LAR) to implement alternative source term (AST) analyses and TSTF-490, "Deletion of E Bar Definition and Revision of RCS Specific Activity Tech Spec.**
A notice for this meeting was issued on July 28, 2014, and is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML14209A195.
The licensee's meeting slide presentation can be found in ADAMS under Accession No. ML14231A198.
During the meeting, the licensee discussed its proposed submittal as outlined in its meeting slide presentation. The NRC staff queried the licensee and provided feedback throughout the presentation. A brief summary of the items discussed at the public meeting is provided below.
- 1. The NRC staff questioned the licensee as to what accidents were being analyzed in support of the AST LAR. The licensee stated that the following accidents were to be analyzed in association with the AST LAR:
Fuel Handling Accident Main Steam Line Break Steam Generator Tube Rupture Locked Rotor Control Rod Ejection Waste Gas Decay Tank Rupture Volume Control Tank Rupture Loss.. of-Coolant Accident (LOCA)
- 2. The NRC staff questioned if there were any specific differences (e.g., vendor, fuel, etc.)
between Unit 1 and Unit 2 that would impact the analyses or calculations. The licensee stated that there are minor differences between the units, but all the analyses and calculations will be bounding for both units.
- 3. The NRC staff questioned if there would be any affect on the containment sump pH analysis. The licensee stated that it anticipates the AST LAR will not have an impact on the containment sump pH analysis.
- 4. The licensee stated that the new Title 10 of the Code of Federal Regulations Section 50.67 accident source term for the control room will be re-addressed in the AST LAR submittal. The submittal will include a full-scope analysis.
- 5. The NRC staff questioned the licensee about the large break LOCA (LBLOCA) peak cladding temperature (PCT) analysis methodology. The licensee stated that the LBLOCA PCT analysis for both units utilizes the NRC-approved ASTRUM methodology.
- 6. The NRC staff questioned the licensee about the nuclear fuel vendor for each unit. The licensee stated that both units utilize Westinghouse fuel.
- 7. The NRC staff questioned the licensee of the impact of the ice condensers on the dose analysis. The licensee stated that the ice condensers were not credited with iodine removal in the dose analysis.
- 8. The NRC staff asked if there will be any affect on the containment sump pH analysis.
The licensee stated that there will be some impact.
- 9. The NRC staff asked if the technical support center (TSC) was considered part of the control room envelope and if there were any changes to the TSC dose assessment. The licensee stated that the TSC was not considered part of the control room enveloped, nor were there any anticipated changes to the TSC dose assessment.
- 10. The licensee stated that environmental qualification (EQ) calculations would be outside the scope of the submittals.
- 11. In previous AST license amendment request reviews, the NRC staff noted that a summary table for each analyzed accident has been a very useful tool. As such, the staff recommended that I&M provide a summary table for each accident being analyzed.
The summary table would simplify the comparison of specific plant parameter value changes for AST. If there is a change in value, the NRC staff recommended a brief explanation be provided as to where in the license amendment request the justification for change could be found.
- 12. The licensee indicated that a formal license amendment request submittal is currently planned for late September 2014, with a requested NRC approval date of October 2015.
Before the meeting adjourned, all meeting participants were given the opportunity to comment on any aspects of the meeting.
No regulatory decisions or commitments were made during the meeting. The public was invited to observe the meeting and was given the opportunity to communicate with the NRC staff during the public meeting and before adjourning. The NRC staff received no public comments and no meeting feedback forms.
Please direct any inquiries to Mahesh Chawla at 301-415-8371 or via e-mail at Mahesh. Chawla@nrc.gov.
Docket Nos. 50-315 and 50-316
Enclosure:
List of Participants cc w/encl: Distribution via ListServ
~~----
fTerry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
LIST OF PARTICIPANTS PUBLIC MEETING BETWEEN THE U.S. NUCLEAR REGULATORY COMMISSION (NRC)
AND INDIANA MICHIGAN POWER COMPANY (I&M)
TO DISCUSS A FUTURE LICENSE AMENDMENT REQUEST REGARDING ALTERNATIVE SOURCE TERM AND TSTF-490 FOR THE DONALD C. COOK NUCLEAR PLANT, UNITS 1 AND 2 NAME Terry Beltz Mahesh Chawla Terry Curtiss Elijah Dickson Helen Etheridge Fred Forsaty Matthew Hamm Greg Hill Alan Huynh David Nold John Parillo Sheila Ray Michael Scarpello Jason Wright Matt Yoder ORGANIZATION NRC/NRR/DORL/LPL3-1 1 NRC/NRR/DORLILPL3-1 1 I&M NRC/NRR/DRAIARCB2 I&M NRC/NRR/DSS/SRXB3 NRC/NRR/DSS/STSB4 I&M NRC/NRR/DE/ESGB5 NRC/NRR/DSS/SCVB6 NRC/NRR/DRAIARCB2 NRC/NRR/DE/EEEB7 I&M I&M NRC/NRR/DE/ESGB5 1 Office of Nuclear Reactor Regulation, Division of Operating Reactor Licensing, Plant Licensing Branch 111-1 2 Office of Nuclear Reactor Regulation, Division of Risk Assessment, Radiation Protection & Consequence Branch 3 Office of Nuclear Reactor Regulation, Division of Safety Systems, Reactor Systems Branch 4 Office of Nuclear Reactor Regulation, Division of Safety Systems, Technical Specifications Branch 5 Office of Nuclear Reactor Regulation, Division of Engineering, Steam Generator Tube Integrity and Chemical Engineering Branch 6 Office of Nuclear Reactor Regulation, Division of Safety Systems, Containment and Ventilation Branch 7 Office of Nuclear Reactor Regulation, Division of Engineering, Electrical Engineering Branch Enclosure Before the meeting adjourned, all meeting participants were given the opportunity to comment on any aspects of the meeting.
There were no members of the general public in attendance or participating in the teleconference.
No additional feedback regarding the meeting was provided.
Please direct any inquiries to Mahesh Chawla at 301-415-8371 or via e-mail at Mahesh.Chawla@nrc.gov.
Docket Nos. 50-315 and 50-316
Enclosure:
List of Participants Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsNrrDoriLpl3-1 Resource RidsNrrLAMHenderson Resource RidsNrrPMDCCook Resource RidsOgcRp Resource RidsRgn3MaiiCenter Resource ADAMS Accession Numbers:
Package: ML14231A228 Meeting Notice: ML14209A195 RidsAcrsAcnw_MaiiCTR Resource EDickson, NRR FForsaty, NRR MHamm, NRR AHuynh, NRR DNold, NRR Meeting Summary: ML14231A075 Licensee's Presentation: ML14231A198 OFFICE LPL3-1/LA NAME MHenderson DATE JParillo, NRR SRay, NRR MYoder, NRR TBeltz, NRR TBowers, EDO R-Ill LPL3-1/PM TBeltz lfl! Z~t14 Please direct any inquiries to Mahesh Chawla at 301-415-8371 or via e-mail at Mahesh. Chawla@nrc. gov.
Docket Nos. 50-315 and 50-316
Enclosure:
List of Participants IRA/
Terry A. Beltz, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation cc w/encl: Distribution via ListServ DISTRIBUTION:
PUBLIC LPL3-1 R/F RidsNrrDorllpl3-1 Resource RidsNrrLAMHenderson Resource RidsNrrPMDCCook Resource RidsOgcRp Resource RidsRgn3MaiiCenter Resource ADAMS Accession Numbers:
Package: ML14231A228 Meeting Notice: ML14209A195 RidsAcrsAcnw_MaiiCTR Resource EDickson, NRR FForsaty, NRR MHamm, NRR AHuynh, NRR DNold, NRR Meeting Summary: ML14231A075 Licensee's Presentation: ML14231A198 OFFICE LPL3-1/PM LPL3-1/LA LPL3-1/BC NAME TBeltz MHenderson DPelton DATE 08/25/14 08/25/14 08/27/14 OFFICIAL RECORD COPY JParillo, NRR SRay, NRR MYoder, NRR TBeltz, NRR TBowers, EDO R-Ill LPL3-1/PM TBeltz 08/27/14