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| | number = ML16327A018 | | | number = ML16327A018 |
| | issue date = 11/23/2016 | | | issue date = 11/23/2016 |
| | title = Perry Nuclear Power Plant, Unit 1 - Request for Additional Information Related to License Amendment Request for Upper Containment Pool Gate Installation and Drain Down of the Reactor Cavity Portion of the Upper Containment Pool (TAC MF7476) | | | title = Request for Additional Information Related to License Amendment Request for Upper Containment Pool Gate Installation and Drain Down of the Reactor Cavity Portion of the Upper Containment Pool (TAC MF7476) (L-16-083) |
| | author name = Green K J | | | author name = Green K |
| | author affiliation = NRC/NRR/DORL/LPLIII-1 | | | author affiliation = NRC/NRR/DORL/LPLIII-1 |
| | addressee name = Hamilton D B | | | addressee name = Hamilton D |
| | addressee affiliation = FirstEnergy Nuclear Operating Co | | | addressee affiliation = FirstEnergy Nuclear Operating Co |
| | docket = 05000440 | | | docket = 05000440 |
| | license number = NPF-058 | | | license number = NPF-058 |
| | contact person = Green K J | | | contact person = Green K |
| | case reference number = L-16-083, TAC MF7476 | | | case reference number = L-16-083, TAC MF7476 |
| | document type = Letter, Request for Additional Information (RAI) | | | document type = Letter, Request for Additional Information (RAI) |
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| =Text= | | =Text= |
| {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 Mr. David B. Hamilton Site Vice President November 23, 2016 FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 | | {{#Wiki_filter:UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 23, 2016 Mr. David B. Hamilton Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097 |
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| ==SUBJECT:== | | ==SUBJECT:== |
| | PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR UPPER CONTAINMENT POOL GATE INSTALLATION AND DRAIN DOWN OF THE REACTOR CAVITY PORTION OF THE UPPER CONTAINMENT POOL (TAC NO. MF7476) (L-16-083) |
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| PERRY NUCLEAR POWER PLANT, UNIT NO. 1 -REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR UPPER CONTAINMENT POOL GATE INSTALLATION AND DRAIN DOWN OF THE REACTOR CAVITY PORTION OF THE UPPER CONTAINMENT POOL (TAC NO. MF7476) (L-16-083)
| | ==Dear Mr. Hamilton:== |
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| ==Dear Mr. Hamilton:==
| | By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 15, 2016, FirstEnergy Nuclear Operating Company (FENOC) submitted a request to modify the technical specifications to allow installation of the reactor well to steam dryer storage pool gate in the upper containment pool (UCP) in MODES 1, 2, and 3, and draining of the reactor well portion of the UCP in MODE 3, for the Perry Nuclear Power Plant, Unit No. 1. |
| | The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. |
| | A draft request for additional information (RAI) was transmitted to your staff by email dated November 21, 2016. A clarification call with FENOC was held on November 22, 2016. As a result of the call, the staff revised wording to request number 4. Also, the staff identified one additional request that was discussed during the call. This request is identified as request number 6. During the call, it was agreed that FENOC would provide a response within 30 days from the date of this letter. |
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| By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 15, 2016, FirstEnergy Nuclear Operating Company (FENOC) submitted a request to modify the technical specifications to allow installation of the reactor well to steam dryer storage pool gate in the upper containment pool (UCP) in MODES 1, 2, and 3, and draining of the reactor well portion of the UCP in MODE 3, for the Perry Nuclear Power Plant, Unit No. 1. The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter. A draft request for additional information (RAI) was transmitted to your staff by email dated November 21, 2016. A clarification call with FENOC was held on November 22, 2016. As a result of the call, the staff revised wording to request number 4. Also, the staff identified one additional request that was discussed during the call. This request is identified as request number 6. During the call, it was agreed that FENOC would provide a response within 30 days from the date of this letter.
| | D. Hamilton The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1627. |
| D. Hamilton The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. | | Sincerely, |
| If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1627. | | :~n~anager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440 |
| Docket No. 50-440 | |
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| ==Enclosure:== | | ==Enclosure:== |
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| Request for Additional Information cc w/encl: Distribution via ListServ Sincerely, Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation REQUEST FOR ADDITIONAL INFORMATION FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT. UNIT NO. 1 DOCKET NO. 50-440 In reviewing the FirstEnergy Nuclear Operating Company's (FENOC) submittal dated March 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML 16075A411 | | Request for Additional Information cc w/encl: Distribution via ListServ |
| ), related to license amendment request for installation of the gate in upper containment pool (UCP) in MODES 1, 2, and 3, and draining of the reactor well portion of the UCP in MODE 3, for Perry Nuclear Power Plant, Unit No. 1, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following information is needed in order to complete its review: Title 10 of the Code of Federal Regulations (CFR), paragraph 50.34(f), | | |
| "Additional TM I-related requirements," | | REQUEST FOR ADDITIONAL INFORMATION FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT. UNIT NO. 1 DOCKET NO. 50-440 In reviewing the FirstEnergy Nuclear Operating Company's (FENOC) submittal dated March 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16075A411 ), related to license amendment request for installation of the gate in upper containment pool (UCP) in MODES 1, 2, and 3, and draining of the reactor well portion of the UCP in MODE 3, for Perry Nuclear Power Plant, Unit No. 1, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following information is needed in order to complete its review: |
| requires that state-of-the-art human factors principles are used to satisfy all specific regulatory requirements. | | Title 10 of the Code of Federal Regulations (CFR), paragraph 50.34(f), "Additional TM I-related requirements," requires that state-of-the-art human factors principles are used to satisfy all specific regulatory requirements. |
| NUREG-0800, "Standard Review Plan [SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," | | NUREG-0800, "Standard Review Plan [SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," is used by the NRC staff to perform safety evaluations of license applications submitted by applicants pursuant to 10 CFR Part 50. The following chapters in the SRP were used to evaluate the human performance aspect of the license amendment request: |
| is used by the NRC staff to perform safety evaluations of license applications submitted by applicants pursuant to 10 CFR Part 50. The following chapters in the SRP were used to evaluate the human performance aspect of the license amendment request: | | Chapter 18, "Human Factors Engineering," Revision 2, discusses the processes for evaluating operator actions. This chapter also identifies specific areas of review that are needed for successful integration of human characteristics and capabilities into nuclear power plant design. |
| Chapter 18, "Human Factors Engineering," | | Chapter 13.5.2.1, "Operating and Emergency Operating Procedures," Revision 2, is used to maintain the applicant's operating procedures that will be used by the operating organization to ensure that the routine operating, off-normal, and emergency activities will be conducted in a safe manner. |
| Revision 2, discusses the processes for evaluating operator actions. | | : 1. Describe any new or changed operator actions that are required as a result of the proposed installation of the reactor well to steam dryer storage pool gate in the upper containment pool in MODES 1, 2, and 3. |
| This chapter also identifies specific areas of review that are needed for successful integration of human characteristics and capabilities into nuclear power plant design. Chapter 13.5.2.1, "Operating and Emergency Operating Procedures," | | : 2. Describe any new or changed operator actions as a result of the proposed creation of the new Special Operations TS, TS 3.10.9, "Suppression Pool Makeup - MODE 3 Upper Containment Pool Drain-Down." |
| Revision 2, is used to maintain the applicant's operating procedures that will be used by the operating organization to ensure that the routine operating, off-normal, and emergency activities will be conducted in a safe manner. 1. Describe any new or changed operator actions that are required as a result of the proposed installation of the reactor well to steam dryer storage pool gate in the upper containment pool in MODES 1, 2, and 3. 2. Describe any new or changed operator actions as a result of the proposed creation of the new Special Operations TS, TS 3.10.9, "Suppression Pool Makeup -MODE 3 Upper Containment Pool Drain-Down." | | : 3. Section 3.2.1, "Reactor Well Gate Installation (MODES 1, 2, and 3)," and Section 3.2.2 "Reactor Well Drained in MODE 3," of the enclosure to the license amendment request provide a brief discussion on current emergency operating procedures (EOPs). |
| : 3. Section 3.2.1, "Reactor Well Gate Installation (MODES 1, 2, and 3)," and Section 3.2.2 "Reactor Well Drained in MODE 3," of the enclosure to the license amendment request provide a brief discussion on current emergency operating procedures (EOPs). Enclosure Describe any changes to manual operator actions covered by EOPs or abnormal procedures that may occur as a result of this amendment. | | Enclosure |
| If so, describe any evaluation of the EOPs for potential modifications. | | |
| : 4. State if the operators will be trained on the proposed license amendment prior to the end of the implementation period. 5. Based on FENOC's response to the above requests 1 and 2, describe the verification and validation activities associated with any required changes. | | Describe any changes to manual operator actions covered by EOPs or abnormal procedures that may occur as a result of this amendment. If so, describe any evaluation of the EOPs for potential modifications. |
| | : 4. State if the operators will be trained on the proposed license amendment prior to the end of the implementation period. |
| | : 5. Based on FENOC's response to the above requests 1 and 2, describe the verification and validation activities associated with any required changes. |
| : 6. Section 3.2.1 of the enclosure to the license amendment request states that the suppression pool water level can be managed by plant operations during the short duration that the condition will exist. Explain how long the "short duration" will last. | | : 6. Section 3.2.1 of the enclosure to the license amendment request states that the suppression pool water level can be managed by plant operations during the short duration that the condition will exist. Explain how long the "short duration" will last. |
| D. Hamilton The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources.
| |
| If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1627.
| |
| Docket No. 50-440
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| ==Enclosure:==
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| Request for Additional Information cc w/encl: Distribution via ListServ DISTRIBUTION:
| | ML16327A018 *via email/memo dated OFFICE DORL/LPL3-1/PM DORL/LPL3-2/LA* DRA/APHB/BC* DORL/LPL3-1 /BC DORL/LPL3-1/PM SRohrer SWeerakkody NAME KGreen DWrona KGreen (KGoldstein for) (JCircle for) |
| PUBLIC LPL3-1 R/F RidsAcrs_MailCTR Resource RidsNrrDorllpl3-1 Resource RidsNrrDraAphb Resource ADAMS Accession No.: ML 16327A018 OFFICE DORL/LPL3-1/PM DORL/LPL3-2/LA
| | DATE 11/22/16 11/22/16 11/21/16 11/23/16 11/23/16}} |
| * NAME KGreen SRohrer (KGoldstein for) DATE 11/22/16 11/22/16 Sincerely, IRA/ Kimberly J. Green, Senior Project Manager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation RidsNrrPMPerry Resource RidsNrrLASRohrer Resource RidsRgn3MailCenter Resource DKi, NRR VHuckabay, NRR *via email/memo dated DRA/APHB/BC* | |
| DORL/LPL3-1 | |
| /BC DORL/LPL3-1/PM SWeerakkody DWrona KGreen (JCircle for) 11/21/16 11/23/16 11/23/16 OFFICIAL RECORD COPY}} | |
Letter Sequence RAI |
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MONTHYEARL-16-083, License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 32016-03-15015 March 2016
License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3
Project stage: Request
L-16-298, Response to a Request for Additional Information Regarding a License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 32016-11-0707 November 2016
Response to a Request for Additional Information Regarding a License Amendment Request for Upper Containment Pool (Ucp) Gate Installation in Modes 1, 2, and 3, and Drain-Down of the Reactor Cavity Portion of the Ucp in Mode 3
Project stage: Response to RAI
ML16327A0182016-11-23023 November 2016
Request for Additional Information Related to License Amendment Request for Upper Containment Pool Gate Installation and Drain Down of the Reactor Cavity Portion of the Upper Containment Pool (TAC MF7476) (L-16-083)
Project stage: RAI
ML17004A2952017-01-0505 January 2017
Safety Evaluation Report- Application for Amendment Perry Nuclear Power Plant
Project stage: Approval
2016-11-07
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2024-08-28
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 November 23, 2016 Mr. David B. Hamilton Site Vice President FirstEnergy Nuclear Operating Company Mail Stop A-PY-A290 P.O. Box 97, 10 Center Road Perry, OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT, UNIT NO. 1 - REQUEST FOR ADDITIONAL INFORMATION RELATED TO LICENSE AMENDMENT REQUEST FOR UPPER CONTAINMENT POOL GATE INSTALLATION AND DRAIN DOWN OF THE REACTOR CAVITY PORTION OF THE UPPER CONTAINMENT POOL (TAC NO. MF7476) (L-16-083)
Dear Mr. Hamilton:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated March 15, 2016, FirstEnergy Nuclear Operating Company (FENOC) submitted a request to modify the technical specifications to allow installation of the reactor well to steam dryer storage pool gate in the upper containment pool (UCP) in MODES 1, 2, and 3, and draining of the reactor well portion of the UCP in MODE 3, for the Perry Nuclear Power Plant, Unit No. 1.
The NRC staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed in the enclosure to this letter.
A draft request for additional information (RAI) was transmitted to your staff by email dated November 21, 2016. A clarification call with FENOC was held on November 22, 2016. As a result of the call, the staff revised wording to request number 4. Also, the staff identified one additional request that was discussed during the call. This request is identified as request number 6. During the call, it was agreed that FENOC would provide a response within 30 days from the date of this letter.
D. Hamilton The NRC staff considers that timely responses to requests for additional information help ensure sufficient time is available for staff review and contribute toward the NRC's goal of efficient and effective use of staff resources. If circumstances result in the need to revise the requested response date, please contact me at (301) 415-1627.
Sincerely,
- ~n~anager Plant Licensing Branch 111-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-440
Enclosure:
Request for Additional Information cc w/encl: Distribution via ListServ
REQUEST FOR ADDITIONAL INFORMATION FIRSTENERGY NUCLEAR OPERATING COMPANY PERRY NUCLEAR POWER PLANT. UNIT NO. 1 DOCKET NO. 50-440 In reviewing the FirstEnergy Nuclear Operating Company's (FENOC) submittal dated March 15, 2016 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML16075A411 ), related to license amendment request for installation of the gate in upper containment pool (UCP) in MODES 1, 2, and 3, and draining of the reactor well portion of the UCP in MODE 3, for Perry Nuclear Power Plant, Unit No. 1, the U.S. Nuclear Regulatory Commission (NRC) staff has determined that the following information is needed in order to complete its review:
Title 10 of the Code of Federal Regulations (CFR), paragraph 50.34(f), "Additional TM I-related requirements," requires that state-of-the-art human factors principles are used to satisfy all specific regulatory requirements.
NUREG-0800, "Standard Review Plan [SRP] for the Review of Safety Analysis Reports for Nuclear Power Plants: LWR Edition," is used by the NRC staff to perform safety evaluations of license applications submitted by applicants pursuant to 10 CFR Part 50. The following chapters in the SRP were used to evaluate the human performance aspect of the license amendment request:
Chapter 18, "Human Factors Engineering," Revision 2, discusses the processes for evaluating operator actions. This chapter also identifies specific areas of review that are needed for successful integration of human characteristics and capabilities into nuclear power plant design.
Chapter 13.5.2.1, "Operating and Emergency Operating Procedures," Revision 2, is used to maintain the applicant's operating procedures that will be used by the operating organization to ensure that the routine operating, off-normal, and emergency activities will be conducted in a safe manner.
- 1. Describe any new or changed operator actions that are required as a result of the proposed installation of the reactor well to steam dryer storage pool gate in the upper containment pool in MODES 1, 2, and 3.
- 2. Describe any new or changed operator actions as a result of the proposed creation of the new Special Operations TS, TS 3.10.9, "Suppression Pool Makeup - MODE 3 Upper Containment Pool Drain-Down."
- 3. Section 3.2.1, "Reactor Well Gate Installation (MODES 1, 2, and 3)," and Section 3.2.2 "Reactor Well Drained in MODE 3," of the enclosure to the license amendment request provide a brief discussion on current emergency operating procedures (EOPs).
Enclosure
Describe any changes to manual operator actions covered by EOPs or abnormal procedures that may occur as a result of this amendment. If so, describe any evaluation of the EOPs for potential modifications.
- 4. State if the operators will be trained on the proposed license amendment prior to the end of the implementation period.
- 5. Based on FENOC's response to the above requests 1 and 2, describe the verification and validation activities associated with any required changes.
- 6. Section 3.2.1 of the enclosure to the license amendment request states that the suppression pool water level can be managed by plant operations during the short duration that the condition will exist. Explain how long the "short duration" will last.
ML16327A018 *via email/memo dated OFFICE DORL/LPL3-1/PM DORL/LPL3-2/LA* DRA/APHB/BC* DORL/LPL3-1 /BC DORL/LPL3-1/PM SRohrer SWeerakkody NAME KGreen DWrona KGreen (KGoldstein for) (JCircle for)
DATE 11/22/16 11/22/16 11/21/16 11/23/16 11/23/16
