ML082810220
| ML082810220 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 10/15/2008 |
| From: | Pickett D Plant Licensing Branch 1 |
| To: | Spina J Calvert Cliffs |
| pickett , NRR/DORL, 415-1364 | |
| References | |
| TAC MD9554, TAC MD9555 | |
| Download: ML082810220 (3) | |
Text
October 15, 2008 Mr. James A. Spina, Vice President Calvert Cliffs Nuclear Power Plant, Inc.
Calvert Cliffs Nuclear Power Plant 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702
SUBJECT:
REQUEST FOR ADDITIONAL INFORMATION RE: LICENSE AMENDMENT FOR MEASUREMENT UNCERTAINTY RECAPTURE POWER UPRATE -
CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 AND 2 -
(TAC NOS. MD9554 AND MD9555)
Dear Mr. Spina:
By letter dated August 29, 2008, Calvert Cliffs Nuclear Power Plant, Inc. requested Nuclear Regulatory Commission (NRC) approval to increase the core thermal power rating of the Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 by 1.38 percent from 2700 megawatt-thermal (MWt) to 2737 MWt.
The NRC staff has reviewed the information provided and has determined that additional information is needed to complete its review. Enclosed is the staffs request for additional information (RAI). As discussed with your staff, we understand that you intend to respond to this RAI by December 31, 2008.
Please contact me at 301-415-1364 if you have any questions.
Sincerely,
/RA/
Douglas V. Pickett, Senior Project Manager Plant Licensing Branch I-1 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-317 and 50-318
Enclosure:
As stated cc w/encl: Distribution via Listserv
ML082810220 OFFICE PM/LPL1-1 LA:LPL1-1 BC/CVIB BC/LPL1-1 NAME DPickett SLittle MMitchell by memo dated MKowal DATE 10 /14/ 08 10 /14/ 08 9 / 30 / 08 10 /15/ 08
Enclosure REQUEST FOR ADDITIONAL INFORMATION CALVERT CLIFFS NUCLEAR POWER PLANT, UNIT NOS. 1 & 2 MEASUREMENT UNCERTAINTY RECAPTURE (MUR) POWER UPRATE
- 1.Section IV.5 of the submittal lists the extended license surface fluence for Calvert Cliffs, Unit 1 as 5.09 x 1019 n/cm2 (E > 1.0 MeV) and for Calvert Cliffs, Unit 2 as 5.74 x 1019 n/cm2 (E > 1.0 MeV). The corresponding surface fluence values, cited in the safety evaluation report dated December 1999 for the extended license renewal application for Calvert Cliffs, were 4.95 x 1019 n/cm2 (E > 1.0 MeV) and 5.77 x 1019 n/cm2 (E > 1.0 MeV) for Unit Nos. 1 and 2, respectively. Please explain the discrepancies between these numbers. In addition, please clarify whether the surface fluence values cited were at the wetted surface or at the clad to base metal interface.
- 2.Section IV.5 of the submittal lists the extended license fluence at the three-quarter thickness of the reactor vessel (RV) wall (3/4T) location for Calvert Cliffs, Unit 1 as 6.09 x 1018 n/cm2 (E > 1.0 MeV) based on the RV surface fluence of 5.09 x 1019 n/cm2 (E >
1.0 MeV). This 3/4T fluence value does not compare well to the NRC staffs independently calculated value of 1.08 x 1019 n/cm2 (E > 1.0 MeV) based on an RV wall thickness from the staffs Reactor Vessel Integrity Database (RVID) of 8.625 inches.
The values for Calvert Cliffs, Unit 2 and all uprated values were similarly inconsistent with the NRC staffs independent calculation. Please explain how you determined the values cited in the application for the 3/4 T locations and, if inconsistent, submit new values.
- 3. Confirm that the RV surveillance capsule withdrawal schedules for Calvert Cliffs, Units 1 and 2 still meet the requirements of 10 CFR Part 50, Appendix H by demonstrating compliance with the guidance in the edition of ASTM E185 which is applicable to your facility after accounting for the effects of the uprate.
- 4. The submittal provides no information regarding your RV internals structural evaluation.
Table Matrix-1 of Nuclear Regulatory Commission RS-001, Revision 0, Review Standard for Extended Power Uprates, provides the staffs basis for evaluating the potential for extended power uprates to induce aging effects on RV internals.
Depending on the magnitude of the projected RV internals fluence, Table Matrix-1 may be applicable to the MUR application. The Industry has established, among other aging issue guidelines, the neutron irradiation-related thresholds for irradiation-assisted stress-corrosion cracking (IASCC) for various pressurized-water reactor (PWR) RV internal components and is working on inspection guidelines for them. Please confirm that you have participated in the industry=s initiatives on age-related degradation of PWR RV internals and will implement the industry criteria and inspection guidelines on this issue when they are approved by the NRC by factoring them into your RV internal inspections as appropriate.