ML11117A314
| ML11117A314 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 04/26/2011 |
| From: | Franke J Progress Energy Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| 3F0411-05, TAC ME0274 | |
| Download: ML11117A314 (10) | |
Text
2 Progress Energy Crystal River Nuclear Plant Docket No. 50-302 Operating License No. DPR-72 Ref: 10 CFR 54 April 26, 2011 3F0411-05 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001
Subject:
Crystal River Unit 3 - Response to Request for Additional Information for the Review of the Crystal River Unit 3, Nuclear Generating Plant, License Renewal Application (TAC NO. ME0274) and Amendment #20
References:
(1) CR-3 to NRC letter, 3F1208-01, dated December 16, 2008, "Crystal River Unit 3 - Application for Renewal of Operating License" (2) NRC to CR-3 letter, dated March 31, 2011, "Request for Additional Information for the Review of the Crystal River Unit 3 Nuclear Generating Plant, License Renewal Application (TAC NO. ME0274)"
Dear Sir:
On December 16, 2008, Florida Power Corporation (FPC), doing business as Progress Energy Florida, Inc. (PEF), requested renewal of the operating license for Crystal River Unit 3 (CR-3) to extend the term of its operating license an additional 20 years beyond the current expiration date (Reference 1). Subsequently, the Nuclear Regulatory Commission (NRC), by letter dated March 31, 2011, provided a request for additional information (RAI) concerning the CR-3 License Renewal Application (Reference 2). Enclosure 1 to this letter provides the response to Reference 2 and includes supplemental responses to RAIs 3.3.2.2.4-1 and 3.31.53-2 that were requested during recent discussions with the NRC staff. In addition, Enclosure 2 to this letter contains Amendment #20 to the License Renewal Application.
No new regulatory commitments are contained in this submittal; however, the RAI responses have resulted in revised implementation details applicable to License Renewal Commitment
- 15. Details are described in Enclosure 2.
If you have any questions regarding this submittal, please contact Mr. Mike Heath, Supervisor, License Renewal, at (910) 457-3487, e-mail at mike.heath@pgnmail.com.
.Sireiy>
Jo A. 'A anke 7,-Vice President Crystal River Unit 3 JAF/dwh
Enclosures:
- 1. Response to Request for Additional Information
- 2. Amendment #20 Changes to the License Renewal Application xc: NRC CR-3 Project Manager NRC License Renewal Project Manager NRC Regional Administrator, Region II Senior Resident Inspector Progress Energy Florida, Inc.
Crystal River Nuclear Plant 15760 W. Power Line Street Crystal River, FL 34428
U. S. Nuclear Regulatory Commission Page 2 of 2 3F0411-05 STATE OF FLORIDA COUNTY OF CITRUS Jon A. Franke states that he is the Vice President, Crystal River Nuclear Plant for Florida Power Corporation, doing business as Progress Energy Florida, Inc.; that he is authorized on the part of said company to sign and file with the Nuclear Regulatory Commission the information attached hereto; and that all such statements made and matters set forth therein are true and correct to the best of his knowledge, information,-and belief.
2C -7 --
Jon A Franke
/Vice ~President Crystal River Nuclear Plant The foregoing document was acknowledged before me this CO26" day of
- .,
- 1,2011, by Jon A. Franke.
Signature of Notary Public State of Florida (Print, type, or stamp Commissioned Name of Notary Public)
Personally Produced Known _ -OR- Identification
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ENCLOSURE 1 RESPONSE TO REQUEST FOR ADDITIONAL INFORMATION
U. S. Nuclear Regulatory Commission Enclosure 1 3F0411-05 Page 1 of 3 REQUEST FOR ADDITIONAL INFORMATION RAI B.2.22-4
Background:
In its August 9, 2010, response to RAI B.2.22-2, the applicant stated that it has conducted Remote Field Transformer Coupling (RFTC) of the pre-stressed cylindrical discharge conduits used in the nuclear services and decay heat seawater system and found them to be in good condition. The applicant also stated that RFTC testing will be conducted again prior to the period of extended operation, in accordance with the Open-Cycle Cooling Water System Program.
Issue:
The staff believes that given that prestressed cylindrical concrete can degrade during the period of extended operation if cracks in the concrete allow raw water to enter the structure and corrode reinforcing wires, RFTC testing should be repeated in each of the 10-year periods of extended operation. This frequency of testing would allow for the timely identification of cracking in the concrete.
Request:
Update the buried piping and tank inspection program to include conducting RFTC testing of the nuclear services and decay heat seawater system discharge conduits in each of the two 10-year periods of extended operation or state why this testing is not needed to ensure that the CLB function(s) of the systems are maintained.
Response
The Crystal River Unit 3 (CR-3) Buried Piping and Tanks Inspection Programhas been updated to incorporate RFTC testing of the Nuclear Services and Decay Heat Seawater System discharge conduits on a 10-year frequency (i.e., in each of the two 10-year periods) during the period of extended operation.
This response involves a change to the License Renewal Application (LRA); refer to the specific change discussed in Enclosure 2.
RAI B.2.22-5
Background:
In its August 9, 2010, response to RAI B.2.22-2 and its December 8, 2010, response to RAI B.2.22-3, the applicant committed to additional buried in-scope piping inspections based on industry operating experience. The response also described what systems are protected by cathodic protection and that the cathodic protection system is maintained to NACE standards.
U. S. Nuclear Regulatory Commission Enclosure 1 3F0411-05 Page 2 of 3 Issue:
10 CFR 54.21 (d) states that "[t]he FSAR supplement for the facility must contain a summary description of the programs and activities for managing the effects of aging." The proposed FSAR supplement does not reflect the planned number and frequency of buried in-scope piping inspections planned for the 30 year period starting 10 years prior to the period of extended operation. It also does not state that for those systems protected by the cathodic protection system, that it is provided and maintained in accordance with NACE standards.
Request:
Revise the UFSAR supplement to reflect the number and frequency of inspections planned for all in-scope buried pipe, which systems are provided cathodic protection, and that the cathodic protection system will be maintained to NACE standards.
Response
The CR-3 FSAR license renewal supplement description of the CR-3 Buried Piping and Tanks Inspection Program has been revised to incorporate the number and frequency of inspections planned for all buried piping in the program, to identify which systems are provided cathodic protection, and to reflect that these cathodic protection systems will be maintained consistent with the guidance of NACE standards.
This response involves a change to the LRA; refer to the specific change discussed in .
RAI 3.3.2.2.4-1 (Supplemental Response)
The following information supplements the original response to RAI 3.3.2.2.4-1 that was submitted in the CR-3 to NRC letter, 3F1210-06, dated December 16, 2010 (Accession #
Response (initial):
The final paragraphof the originalresponse stated:
"Basedon the previous discussion, cracking due to cyclic loading is not applicable to the letdown cooler components based on the design and operationalchanges implemented at CR-3. Cracking due to stress corrosion cracking remains as an applicable effect for the letdown cooler components, and is managed using the Water Chemistry Program, with verification of program effectiveness provided by the One-Time Inspection Program.
The Water Chemistry Program relies on monitoring and control of water chemistry to effectively mitigate aging effects on component surfaces that are exposed to water as a process fluid. The One-Time Inspection Program is a sampling-based program that uses one-time inspections to verify the effectiveness of an aging management program.
While access limitations may preempt the letdown coolers from being selected for inspection, inspections of components having similar materials and exposed to comparable environments will serve to verify the effectiveness of the Water Chemistry Program."
U. S. Nuclear Regulatory Commission Enclosure 1 3F0411-05 Page 3 of 3 The supplemental response involves a revision of the final paragraph such that the final sentence is changed to read:
While access limitations may preempt the letdown coolers from being selected for inspection, inspections will be performed of surrogate components having similar material, similar form, and exposed to a comparable environment to verify the effectiveness of the Water Chemistry Program.
RAI 3.31.53-2 (Supplemental Response)
The following information supplements the original response to RAI 3.31.53-2 that was submitted in the CR-3 to NRC letter, 3Fl110-02, dated November 12, 2010 (Accession #
Response (initial):
The originalresponse stated:
"Crystal River Unit 3 (CR-3) assumes that the environment for the compressed air system components downstream of the' system dryers has the potential for moisture and/or condensation, and therefore, the potential for age-related corrosion requiring aging management. CR-3 will utilize the Compressed Air Monitoring Program to manage aging of piping, piping components, and piping elements identified in the CR-3 License Renewal Application (LRA) as exposed to a "driedair(inside)" environment, which would be subject to the potential of corrosionpresuming the presence of moisture. The CR-3 Compressed Air Monitoring Program relies on monitoring and testing of compressed air quality to preclude the incidence of moisture, and preventive maintenance and opportunistic inspections to verify that loss of material is not occurring. The CR-3 Compressed Air Monitoring Program is consistent with the program description in NUREG-1801, "GenericAging Lessons Learned (GALL)," Revision 2 (draft), Volume 2, Section X1. M24 (Accession # ML102660219)."
Response (supplemental):
Add the following paragraphto the originalresponse:
CR-3 has performed a comparison of the Compressed Air Monitoring Program description found in the draft revision of NUREG-1801, Revision 2, with that in the final issue of NUREG-1801, Revision 2. This review concluded that the two versions of the program description have negligible differences, such that the CR-3 Compressed Air Monitoring Program is consistent with both the draft and final versions of the program description.
This supplemental RAI response involves changes to the LRA; refer to the specific changes discussed in Enclosure 2.
PROGRESS ENERGY FLORIDA, INC.
CRYSTAL RIVER UNIT 3 DOCKET NUMBER 50 - 302 / LICENSE NUMBER DPR - 72 ENCLOSURE 2 AMENDMENT #20 CHANGES TO THE LICENSE RENEWAL APPLICATION
U. S. Nuclear Regulatory Commission Enclosure 2 3F0411-05 Page 1 of 2 Amendment #20 Changes to the License Renewal Application Source of License Renewal Application (LRA) Amendment #20 Changes Chanae RAI B.2.22-4 Revise LRA Table 3.3.2-49 on page 3.3-347 to include the following additional aging and management review (AMR) information for the reinforced concrete piping in the Nuclear RAI B.2.22-5 Service and Decay Heat Sea Water System that is subjected to the Open-Cycle Cooling Water (Inside) environment. Add this AMR line immediately prior to the AMR line that employs the Open-Cycle Cooling Water System aging management program.
Change in Material Buried Piping and J, 303 Properties due to Various Tanks Inspection Degradation Mechanisms Cracking due to Various Degradation Mechanisms Loss of Material due to Various Degradation Mechanisms In LRA Subsection A.1. 1.20 on page A-13, -revise the first sentence of the description to read:
The Buried Piping and Tanks Inspection Program is a new program that manages the aging effect of loss of material for the external surfaces of buried steel piping components, as well as cracking and degradation of material properties of concrete, in CR-3 systems within the scope of License Renewal.
In addition, add the following paragraph to Subsection A. 1.1.20 after the discussion of the Nuclear Services and Decay Heat Seawater System inlet conduits that was added by LRA Amendment #12 in the CR-3 to NRC letter, 3F0810-01, dated August 9, 2010 (Accession #
The following table outlines the minimum inspection schedule prescribed for the Buried Piping and Tanks Inspection Program:
(Note that the subject minimum inspection schedule table is enclosed as Attachment 1 immediately following this table.)
In LRA Subsection B.2.20 on page B-67, revise the first sentence of the Program Description to read:
The Buried Piping and Tanks Inspection Program manages the aging effect of loss of material for the external surfaces of buried steel components, as well as cracking and degradation of material properties of concrete, in CR-3 systems within the scope of License Renewal.
Also revise the fourth sentence of the Program Description on page B-67 to read:
The aging effects/mechanisms of concern are loss of material due to general, galvanic, pitting, and crevice corrosion and MIC, as well as cracking and degradation of material properties associated with concrete piping.
U. S. Nuclear Regulatory Commission Enclosure 2 3F0411-05 Page 2 of 2 Source of License Renewal Application (LRA) Amendment #20 Changes Chanqe RAI LRA Amendment #13 was submitted by CR-3 to NRC letter, 3F1 110-02, dated November 3.31.53-2 12, 2010 (Accession # ML103200064). LRA Amendment #13 made revisions to Table B-1 Supplement on page B-8 and to the NUREG-1801 Consistency statement on page B-69 to indicate that the Compressed Air Monitoring Program is consistent with NUREG-1801 (Revision 2, draft),
Section XI.M24. Based on the supplementary response to RAI 3.31.53-2, revise these statements to remove the word "draft" wherever reference is made to the revision of NUREG-1801 in the discussion of the Compressed Air Monitoring Program.
Also, revise the Discussion column of LRA Table 3.3.1, for line items 3.3.1-53 and 3.3.1-54 on page 3.3-85, to state:
CR-3 uses the Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program and the Compressed Air Monitoring Program to manage corrosion of internal surfaces of compressed air system components that might be subject to internal condensation. The Inspection of Internal Surfaces in Miscellaneous Piping and Ducting Components Program is credited with managing components from the air compressors through the dryers. The Compressed Air Monitoring Program, which includes monitoring of air quality in addition to inspections, is credited with managing compressed air components downstream of the dryers.
U. S. Nuclear Regulatory Commission Enclosure 2 3F0411-05 Attachment 1 Page 1 of I Buried Piping and Tanks Inspection Program Inspections and Schedule Cath. 30 - 40 Yr Inspections 40 - 50 Yr Inspections 50 - 60 Yr Inspections Comments System Prot. Comment Condensate Y One inspection of at One inspection of at One inspection of at Condensate piping to Emergency least 10 feet aggregate least 10 feet aggregate least 10 feet aggregate Feedwater tank / pumps length length length N One inspection of at One inspection of at One inspection of at Condensate Storage Tank piping to least 10 feet aggregate least 10 feet aggregate least 10 feet aggregate Auxiliary Feedwater and length length length Condensate Pumps Emergency Y At least one inspection, At least one inspection, At least one inspection, Alternately, at least 2 inspections of Feedwater with at least 20 feet with at least 20 feet with at least 20 feet at least 10 feet per interval aggregate length aggregate length aggregate length Fire N Opportunistic Opportunistic Opportunistic System integrity verified by routine Protection Inspections Inspections Inspections monitoring of Fire Protection jockey pump operation Fuel Oil Y One inspection of at One inspection of at One inspection of at least 10 feet aggregate least 10 feet aggregate least 10 feet aggregate length length length Nuclear N One inspection of at One inspection of at One inspection of at Intake Conduits - inspections to be Services & least 25% aggregate least 25% aggregate least 25% aggregate performed using qualified methods.
Decay Heat length of intake conduits length of intake conduits length of intake conduits Subsequent inspection frequency Seawater based on initial results, not to exceed 10 years.
Nuclear N At least one inspection At least one inspection At least one inspection Discharge Conduits - Remote Field Services & of both discharge of both discharge of both discharge Transformer Coupling testing Decay Heat conduits conduits conduits Seawater Notes:
- CR-3 may substitute internal non-destructive examinations, pressure testing, or direct visual inspections as described in Program Description XI.M41 of NUREG-1801, draft Revision 2.
Cathodic protection system maintained consistent with the guidance of NACE SP0169-2007 (or later applicable standard).