ML16306A004
| ML16306A004 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 10/31/2016 |
| From: | Andrew Hon Plant Licensing Branch II |
| To: | James Shea Tennessee Valley Authority |
| References | |
| MF7762, MF7763 | |
| Download: ML16306A004 (3) | |
Text
1 NRR-PMDAPEm Resource From:
Hon, Andrew Sent:
Monday, October 31, 2016 3:34 PM To:
Shea, Joseph W Cc:
Hess, Thomas A (tahess@tva.gov)
Subject:
RAI for SQN LAR to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (CAC NOS. MF7762 AND MF7763)
Mr. Shea, By letter dated May 26, 2016 (Agencywide Document Access and Management System (ADAMS) Accession Number ML16148A175, Tennessee Valley Authority (TVA, the licensee) submitted License Amendment Requests for Sequoyah Nuclear Plant, Units 1 and 2 to modify Technical Specifications Regarding Diesel Generator Steady State Frequency Range.
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your submittal and has determined that additional information is required to complete the review. The specific information requested is addressed below. The proposed questions were discussed by telephone with your staff on October 28, 2016. Your staff confirmed that these questions did not include proprietary or security-related information and agreed to provide a response in 30 days, to this request for additional information (RAI).
2 The NRC staff considers that timely responses to RAIs help ensure sufficient time is available for staff review and contribute toward the NRCs goal of efficient and effective use of staff resources. Please note that if you do not respond to this request by the agreed-upon date or provide an acceptable alternate date, we may deny your application for amendment under the provisions of Title 10 of the Code of Federal Regulations, Section 2.108. If circumstances result in the need to revise the agreed upon response date, please contact me.
Andy Hon, PE Project Manager (Brunswick Nuclear Plant 1 & 2, Sequoyah Nuclear Plant 1 & 2)
Plant Licensing Branch II-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation 301-415-8480 OWFN O8H19 Mail Stop O8G-9a andrew.hon@nrc.gov RAI EPNB-1 The ASME OM Code stroke-timing test for motor-operated valves is performed to meet the inservice testing requirements of 10 CFR 50.55a. Please discuss the impact of pump discharge pressure/differential pressure on motor-operated valves as a result of a higher than nominal diesel generator frequency.
RAI EPNB-2 Section 3.2.3.1.1 of the LAR states, Therefore, a 0.2 Hz change in DG frequency will change pump flow by
+/-0.33%. However, Section 3.2.3.2 of the LAR states The flow change resulting from the DG frequency variation is limited to +/-0.35%. Please confirm which value is correct.
Hearing Identifier:
NRR_PMDA Email Number:
3134 Mail Envelope Properties (Andrew.Hon@nrc.gov20161031153300)
Subject:
RAI for SQN LAR to Modify Technical Specifications Regarding Diesel Generator Steady State Frequency (CAC NOS. MF7762 AND MF7763)
Sent Date:
10/31/2016 3:33:59 PM Received Date:
10/31/2016 3:33:00 PM From:
Hon, Andrew Created By:
Andrew.Hon@nrc.gov Recipients:
"Hess, Thomas A (tahess@tva.gov)" <tahess@tva.gov>
Tracking Status: None "Shea, Joseph W" <jwshea@tva.gov>
Tracking Status: None Post Office:
Files Size Date & Time MESSAGE 2405 10/31/2016 3:33:00 PM Options Priority:
Standard Return Notification:
No Reply Requested:
No Sensitivity:
Normal Expiration Date:
Recipients Received: