ML091270930
| ML091270930 | |
| Person / Time | |
|---|---|
| Site: | Ginna  |
| Issue date: | 06/09/2009 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | John Carlin Ginna |
| Pickett D | |
| References | |
| TAC ME0291 | |
| Download: ML091270930 (5) | |
Text
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.June 9, 2009
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~O Mr. John 1. Carlin Vice President RE. Ginna Nuclear Power Plant RE. Ginna Nuclear Power Plant, LLC 1503 Lake Road Ontario, NY 14519
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: LOSS OF POWER INSTRUMENTATION SETTINGS AND DIESEL GENERATOR LOAD TEST VALUE (TAC NO. ME0291)
Dear Mr. Carlin:
By letter dated December 19, 2008, RE. Ginna Nuclear Power Plant, LCC submitted a license amendment request for the RE. Ginna Nuclear Power Plant which would revise the Technical Specifications relating to the loss of power instrumentation settings specified in Surveillance Requirement (SR) 3.3.4.2 and the diesel generator load test value specified in SR 3.8.1.3.
The Nuclear Regulatory Commission staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the staff's request for additional information (RAI). As discussed with your staff, we understand that you intend to respond to this RAI within 45 days of the date of this letter.
Please contact me at 301-415-1364 if you have any questions.
Sincerely, Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated cc w/encl: Distribution via Listserv
REQUEST FOR ADDITIONAL INFORMATION LOSS OF POWER INSTRUMENTATION SETTINGS AND DIESEL GENERATOR LOAD TEST VALUE R.E. GINNA NUCLEAR POWER PLANT DOCKET NO. 50-244
- 1.
The undervoltage signal logic as shown in Technical Specification (TS) Bases Figure B.3.3.4-1 is different from the one shown in Figure 2 of the Technical Evaluation Report provided as an enclosure to License Amendment No. 38 issued by the NRC on March 26, 1981. Please provide the license amendment number in which the revised undervoltage signal logic was approved by NRC.
- 2.
According to Acceptance Criteria 5 and 6 discussed in Section 9.0 (Page 15) of design analysis DA-EE-93-006-08, Revision 5, the degraded voltage and loss of voltage relays are set to prevent actuation during an engineered safeguard sequence when the safeguard buses are supplied by the emergency diesel generators (EDGs). Explain the function of the above relays in the event they operate during an engineered safeguard sequence when the safeguard buses are supplied by the EDGs.
- 3.
Please provide a copy the vendor supplied operating curves of Loss of Voltage and Degraded Voltage relays.
- 4. to DA-EE-93-006-05 is a section of the operating manual for the Doble (F2000 Family) test equipment. This attachment indicates that the output AC voltage has a total harmonic distortion of 2%. Please provide details of the evaluation that accounts for the inaccuracy in relay calibration introduced by the test equipment harmonic content.
- 5.
Please provide your evaluation of NRC Information Notice 95-05, "Undervoltage Protection Relay Settings, Out of Tolerance Due to Test Equipment Harmonics" for impact on the Ginna Nuclear Plant.
- 6.
Please provide a copy of Attachment 12 of design analysis DA-EE-96-068-03 (Offsite Power Load Flow Study), which is referenced in Section 5.1 of the design analysis DA-EE-93-006-08, Revision 5.
- 7.
Please provide a copy of the thermal capability curves of 440, 460, and 480 V motors which are discussed in Section 5.5 and shown on Page 45 of design analysis DA-EE-93-006-08, Revision 5.
- 8.
Clarify the base voltage (whether 460 V or 480 V) considered corresponding to the percent voltage shown on Page 35 of design analysis DA-EE-93-006-08, Revision 5.
Enclosure
- 2
- 9.
In Section 3.2 of the application, it is stated that the current TSs degraded voltage and loss of voltage relay Limiting Safety System Settings (LSSS) required values do not reflect plant design basis requirements as defined in the plant load flow analysis, DA-EE-96-068-03. Please provide an executive summary of the calculation which provides the following information:
- a.
Plant design basis requirements and corresponding justification for revising the loss of voltage and degraded voltage relay settings to meet the plant design basis requirements
- b.
Worst case voltage at 480 V safeguard buses (on 480 V bus voltage and 120 V relay voltage bases) versus time preferably in tabular form, when the engineered safeguard buses are sequenced from offsite power sources (instead of EDGs)
- c.
Details which confirm the worst case voltage at motor control centers (MCCs) will be adequate to pick up the starter contactors during starting of the safeguard loads.
- 10.
Please provide details (such as design criteria) which confirm that protective devices at the 120 V distribution level are adequately sized and will not result in actuation during start and operation of safeguard equipment for the duration of degraded voltage conditions.
- 11.
In the license amendment request dated December 19, 2008, Section 3.2.c of the Enclosure states that a one-out-of-two logic in both channels will cause:
Shedding of all bus loads except the containment spray pump, component cooling water pump (if no safety injection signal is present), and safety-related MCCs.
Regarding the above statement, clarify the following:
a)
The above statement indicates that none of the safety-related MCCs are shed.
However, according to Ginna Updated Final Safety Analysis Report (UFSAR),
Revision 21, Section 8.3.1.1.6.6, it appears that all motor centers are shed except MCCs 1C and 10, which require a manual trip. Clarify which MCCs are shed and which are not shed.
b)
The above statement indicates that the containment spray pumps are not shed.
However, Table 8.3-1b of UFSAR indicates that the containment spray pumps may be loaded onto safeguard buses anytime after the buses are energized, which indicates that the containment spray pumps are either not initially running or are shed. Clarify the statement in the application that the containment spray pumps are not shed.
c)
If the containment spray pumps may be loaded onto safeguard buses at anytime after the buses are energized, there is a potential for the containment spray pumps to be loaded simultaneously with another large load. Please provide an
- 3 analyses that demonstrate that the EDG is capable of sequencing two (or more) large loads simultaneously and maintain voltage and frequency guidelines provided in Regulatory Guide 1.9.
d)
Please provide details of any other loads that may be loaded onto the safeguards busses after receiving a permissive from a process signal and the sequencer relays.
- 12.
Please provide details on any manual loads that may be procedurally loaded on to the EDGs during the events discussed in the analyses documented in DA-EE-92-098-01 and DA-EE-92-120-01 for diesel generator A and S, respectively.
June 9, 2009 Mr. James A. Spina, Vice President Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, IVID 20657-4702 SUB..IECT:
REQUEST FOR ADDITIONAL INFORMATION RE: LOSS OF POWER INSTRUIVIENTATION SETTINGS AND DIESEL GENERATOR LOAD TEST VALUE (TAC NO. ME0291)
Dear Mr. Carlin:
By letter dated December 19, 2008, R.E. Ginna Nuclear Power Plant, LCC submitted a license amendment request for the R.E. Ginna Nuclear Power Plant which would revise the Technical Specifications relating to the loss of power instrumentation settings specified in Surveillance Requirement (SR) 3.3.4.2 and the diesel generator load test value specified in SR 3.8.1.3.
The Nuclear Regulatory Commission (NRC) staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the staff's request for additional information (RAI). As discussed with your staff, we understand that you intend to respond to this RAI within 45 days of the date of this letter.
Please contact me at 301-415-1364 if you have any questions.
Sincerely, IRA!
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch 1-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket No. 50-244
Enclosure:
As stated cc wlencl: Distribution via Listserv Distribution:
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