ML100740652
| ML100740652 | |
| Person / Time | |
|---|---|
| Site: | Perry  |
| Issue date: | 03/23/2010 |
| From: | Billoch-Colon A Plant Licensing Branch III |
| To: | Bezilla M FirstEnergy Corp |
| Billoch-Colon A NRR 301-415-3302 | |
| References | |
| TAC ME1691 | |
| Download: ML100740652 (4) | |
Text
UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 MATCh 23, 2010 Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A290 P.O. Box 97,10 Center Road Perry,OH 44081-0097 SUB~IECT:
PERRY NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION CHANGE TO DIVISION 3 EMERGENCY DIESEL GENERATOR START TIME SURVEILLANCE REQUIREMENTS (TAC NO. ME1691)
Dear Mr. Bezilla:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated June 30, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091900387),
FirstEnergy Nuclear Operating Company (FENOC or the licensee), requested an amendment to the Perry Nuclear Power Plant Unit NO.1 regarding the Technical Specification change to Division 3 Emergency Diesel Generator start time Surveillance Requirements.
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. During a discussion with your staff on March 9, 2010, it was agreed that you would provide a response within 60 days from the date of this letter.
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) 415-3302.
Sincerely,
~r.~~
Araceli T. Billoch Colon, Project Engineer Plant Licensing Branch 111-2 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 AMENDMENT TO EMERGENCY DIESEL GENERATOR TECHNICAL SPECIFICATION SURVEILLANCE REQUIREMENTS PERRY NUCLEAR POWER PLANT DOCKET NO. 50-440 By letter to the U.S. Nuclear Regulatory Commission (NRC) dated June 30, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091900387), the FirstEnergy Nuclear Operating Company, (the licensee) requested an amendment to the Perry Nuclear Power Plant. In the license amendment request (LAR), the licensee proposed modifying Technical Specification (TS) 3.8.1, "AC Sources - Operating." The proposed amendment will modify a Surveillance Requirement (SR) regarding the start time tests for the Division 3 Emergency Generator (EDG) to provide consistency with existing similar TS SRs related to EDG testing.
Specifically, the amendment will make the Division 3 frequency start time requirement consistent with the existing 13-second voltage requirement in the same SR, and with the existing 13-second start time requirements in SR 3.8.1.11, SR 3.8.1.12, SR 3.8.1.15, SR 3.8.1.19, and SR 3.8.1.20.
The !\\IRC staff requests the following additional information to complete its review of the proposed amendment.
In the LAR, the licensee states that the accident analysis (SAFERIGESTR) assumes that design flow from the high-pressure core spray (HPCS) system is available 29 seconds after initiation of a Loss-of-Coolant Accident signal. The EDG start time and HPCS isolation valve stroke time are portions of the overall 29-second time. The analysis does not credit flow during partial opening of associated HPCS valve. According to the Updated Safetry Analysis Report Table 6.2-22, the containment isolation motor operated valve E22F004 has a 'CLOSE' stroke time of 16 seconds.
Assuming that the valve 'OPEN' stroke time is also 16 seconds (nominal voltage and frequency),
that leaves 13 seconds for the HPCS EDG to attain the required voltage and frequency. In the LAR, the licensee is requesting that the HPCS EDG voltage and frequency (after 13 seconds) to be "at or above" 3900 Volts (V) and 58.8 Hertz (Hz). At this voltage and frequency, the stroke time may be longer than 16 seconds, resulting in less time available for the EDG to start.
Provide:
- 1. A summary of the analysis for the valve stroke time to open when the HPCS EDG voltage and frequency attain the minimum acceptable values.
- 2. A summary of the analysis for time required for full design flow into the reactor vessel, after initiation of an accident signal, with the HPCS valve partially open and the HPCS EDG at minimum allowable voltage and frequency.
Enclosure
- 2
- 3. Supporting documentation that shows how the HPCS valve stroke time has been validated.
- 4. Details on any plant procedures that allow operation of the HPCS EDG as a compensatory power source for other safety-related equipment during unavailability of Division 1 or Division 2 EDGs.
March 23, 2010 Mr. Mark B. Bezilla Site Vice President FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant Mail Stop A-PY-A290 P.O. Box 97,10 Center Road Perry,OH 44081-0097
SUBJECT:
PERRY NUCLEAR POWER PLANT - REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED TECHNICAL SPECIFICATION CHANGE TO DIVISION 3 EMERGENCY DIESEL GENERATOR START TIME SURVEILLANCE REQUIREMENTS (TAC NO. ME1691)
Dear Mr. Bezilla:
By letter to the U.S. Nuclear Regulatory Commission (NRC) dated June 30, 2009 (Agencywide Documents Access and Management System (ADAMS) Accession No. ML091900387),
FirstEnergy Nuclear Operating Company (FENOC or the licensee), requested an amendment to the Perry Nuclear Power Plant Unit NO.1 regarding the Technical Specification change to Division 3 Emergency Diesel Generator start time Surveillance Requirements.
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. During a discussion with your staff on March 9, 2010, it was agreed that you would provide a response within 60 days from the date of this letter.
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) 415-3302.
Sincerely, IRAI Araceli T. Billoch Colon, Project Engineer Plant Licensing Branch 111-2 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 DISTRIBUTION:
PUBLIC LPL3-2 R/F RidsNrrDorlLpl3-2 Resource RidsNrrPMPerry Resource RidsNrrLATHarris Resource RidsAcrsAcnw_MailCTR Resource RidsOgcRp Resource RidsRgn3MailCenter Resource RidsNrrDorlDpr Resource ADAMS Accession No'..ML100740652 NRR-088 OFFICE LPL3-2/PM LPL3-2/LA LPL3-2/BC NAME ABiliochCol6n THarris SCampbell DATE 3/17/10 3/16/10 3/23/10 OFFICIAL RECORD ONLY