NL-04-022, Proposed Change to Technical Specifications Regarding Reactor Coolant Pump Flywheel Inspection Interval (TSTF-421)
| ML040720634 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 03/03/2004 |
| From: | Dacimo F Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-04-022, TSTF-421 | |
| Download: ML040720634 (10) | |
Text
Entergy Nuclear Northeast Indian Point Energy Center v `
nteret g295 Broadway. Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 Fred Dacimo Site Vice President Tel 914 734 6700 March 3, 2004 Re:
Indian Point Units 2 & 3 Docket No. 50-247 & 50-286 NL-04-022 Document Control Desk U.S. Nuclear Regulatory Commission Mail Stop O-P1-17 Washington, DC 20555-0001
Subject:
Proposed Change to Technical Specifications Regarding Reactor Coolant Pump Flywheel Inspection Interval (TSTF-421)
Reference:
- 2)
Westinghouse Owners Group Topical Report, WCAP-1 5666-A, Revision 1, "Extension of Reactor Coolant Pump Motor Flywheel Examination", dated October 2003.
- 3) Federal Register Notice 68 FR 60422, "Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process", dated October 22, 2003.
Dear Sir:
Pursuant to 10CFR50.90, Entergy Nuclear Operations, Inc (Entergy) is submitting a request for an amendment to the Technical Specifications for Indian Point Unit 2 (IP2) and Indian Point Unit 3 (IP3).
The proposed amendment will extend the reactor coolant pump (RCP) motor flywheel examination frequency from the currently approved 10-year inspection interval, to an interval not to exceed 20 years. The proposed changes to Technical Specification Sections 5.5.5 for IP2 and 5.5.6 for IP3, 'Reactor Coolant Pump Flywheel Program" are in accordance with TSTF-421 (Reference 1) and WCAP-1 5666-A (Reference 2). The availability of this Technical Specification improvement, using the Consolidated Line Item Improvement Process, was announced by the NRC in 68 FR 60422 (Reference 3).
A047
NL-04-022 Docket 50-247 & 50-286 Page 2 of 3 Entergy has reviewed the model safety evaluation and verified that it is applicable to IP2 and IP3. The detailed description and assessment of the proposed change is provided in. Marked-up technical specification pages showing the proposed changes are provided in Attachment 2.
In accordance with IOCFR50.91, a copy of this application and the associated attachments are being submitted to the designated New York State official.
There are no new commitments being made in this submittal. Entergy requests approval of the proposed amendment by September 14, 2004 with the amendment being implemented within 30 days. If you have any questions or require additional information, please contact Mr. Kevin Kingsley at (914) 734-6695.
I declare under penalty of perjury that the foregoing is true and correct. Executed on S32lo/.
Sincerely, Vice President, Operations Indian Point Energy Center cc: next page
NL-04-022 Docket 50-247 & 50-286 Page 3 of 3 cc:
Mr. Patrick D. Milano, Senior Project Manager Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop 0 8 C2 Washington, DC 20555-0001 Mr. Hubert J. Miller Regional Administrator, Region 1 U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1415 Resident Inspectors Office Indian Point Unit 3 U.S. Nuclear Regulatory Commission P.O. Box 337 Buchanan, NY 10511-0337 Mr. Peter R. Smith, Acting President New York State Energy, Research and Development Authority Corporate Plaza West 286 Washington Avenue Extension Albany, NY 12203-6399 Mr. Paul Eddy New York State Dept. of Public Service 3 Empire State Plaza Albany, NY 12223-6399
ATTACHMENT 1 TO NL-04-022 DESCRIPTION AND ASSESSMENT OF PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS REGARDING RCP MOTOR FLYWHEEL EXAMINATION FREQUENCY ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-247 AND 50-286 to NL-04-022 Docket 50-247 and 50-286 Page 1 of 3
1.0 INTRODUCTION
The proposed License amendment changes Technical Specification (TS) section 5.5.5 for Indian Point Unit 2 (IP2) and section 5.5.6 for Indian Point Unit 3 (IP3) regarding the Reactor Coolant Pump Flywheel Inspection Program. The changes are consistent with Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421,.
"Revision to RCP Flywheel Inspection Program (WCAP-1 5666)." The availability of this Technical improvement was announced in the Federal Register on October 22, 2003 as part of the consolidated line item improvement process (CLIIP).
2.0 DESCRIPTION
OF PROPOSED AMENDMENT Consistent with the NRC-approved TSTF-421, the proposed TS change includes the following revisions to IP2 TS 5.5.5 and IP3 TS 5.5.6:
I P2 TS 5.5.5:
This program shall provide for the inspection of each reactor coolant pump flywheel using ultrasonic methods. The program shall include inspection frequencies and acceptance criteria. The inspection frequency will ensure that each reactor coolant pump flywheel was inspccted during one of the four most recent refucling outages is inspected at 20-year intervals.
IP3 TS 5.5.6:
This program shall provide for the inspection of each reactor coolant pump flywheel. The program shall include inspection frequencies and acceptance criteria. The inspection frequency will ensure that each reactor coolant pump flywheel is surface and volumetrically inspected within10years after a flvheelisplacedin sr'ie followingn Tspetion ato -
year intervals.
3.0 BACKGROUND
The background for this application is adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590), TSTF-421 Revision 0, "Revision to RCP Flywheel Inspection Program,"
WCAP-1 5666, 'Extension of Reactor Coolant Pump Motor Flywheel Examination," and the related NRC Safety Evaluation (SE) dated May 5, 2003.
4.0 REGULATORY REQUIREMENTS AND GUIDANCE The applicable regulatory requirements and guidance associated with this application are adequately addressed by the NRC Notice of Availability published on October 22, 2003 (68 FR 60422), NRC Notice for Comment published on June 24, 2003 (68 FR 37590), TSTF-421 Revision 0, "Revision to RCP Flywheel Inspection Program," WCAP-15666, "Extension of to NL-04-022 Docket 50-247 and 50-286 Page 2 of 3 Reactor Coolant Pump Motor Flywheel Examination," and the related NRC Safety Evaluation (SE) dated May 5, 2003.
5.0 TECHNICAL ANALYSIS
.Entergy has reviewed the model SE published on June 24, 2003 (68 FR 37590), and verified its applicability as part of the CLIIP. This verification included a review of the NRC staffs model SE, as well as the information provided to support TSTF-421 (including WCAP-15666 and the related SE dated May 5, 2003). Entergy has concluded that the justifications presented in the TSTF proposal and the model SE prepared by the NRC staff are applicable to IP2 and IP3 and justify this amendment for the incorporation of the changes to the respective plant Technical Specifications as described in Section 2.0 above.
6.0 REGULATORY ANALYSIS
A description of this proposed change and its relationship to applicable regulatory requirements and guidance was provided in the NRC notices related to the CLIIP, TSTF-421, topical report WCAP-15666, and the associated SE.
7.0 NO SIGNIFICANT HAZARDS CONSIDERATION Entergy has reviewed the proposed no significant hazards consideration determination
,publishedon June 24, 2003 (68 FR 37590) as part of the CLIIP. Entergy has concluded that the proposed determination presented in the notice is applicable to IP2 and IP3 and the determination is hereby incorporated by reference to satisfy the requirements of 10 CFR 50.91 (a).
8.0 ENVIRONMENTAL EVALUATION Entergy has reviewed the environmental evaluation included in the model SE published on June 24, 2003 (68 FR 37590) as part of the CLIIP. Entergy has concluded that the staffs findings presented in that evaluation are applicable to IP2 and IP3 and the evaluation is hereby incorporated by reference for this application.
9.0 PRECEDENT This application is being made in accordance with the CLIIP. Entergy is not proposing variations or deviations from the TS changes described in TSTF-421 or the NRC staffs model SE published on June 24, 2003 (68 FR 37590).
10.0 REFERENCES
- 1. Federal Register Notice: Notice of Availability of Model Application Concerning Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel to NL-04-022 Docket 50-247 and 50-286 Page 3 of 3 Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published October 22, 2003 (68 FR 60422).
- 2. Federal Register Notice: Notice of Opportunity to Comment on Model Safety Evaluation on Technical Specification Improvement Regarding Extension of Reactor Coolant Pump Motor Flywheel Examination for Westinghouse Plants Using the Consolidated Line Item Improvement Process, published June 24, 2003 (68 FR 37590).
- 3. Industry/Technical Specification Task Force (TSTF) Standard Technical Specification Change Traveler, TSTF-421, uRevision to RCP Flywheel Inspection Program (WCAP-15666)," Revision 0, November 2001.
- 4. WCAP-15666, "Extension of Reactor Coolant Pump Motor Flywheel Examination," July 2001. [including WCAP-1 5666-A, Revision I dated October 2003]
- 5. NRC letter dated May 5, 2003, from H. Berkow to R. Bryan (WOG) transmitting Safety Evaluation of WCAP-1 5666.
ATTACHMENT 2 TO NL-04-022 MARKUP OF TECHNICAL SPECIFICATION PAGES FOR PROPOSED CHANGES TO THE TECHNICAL SPECIFICATIONS REGARDING RCP MOTOR FLYWHEEL EXAMINATION FREQUENCY ENTERGY NUCLEAR OPERATIONS, INC.
INDIAN POINT NUCLEAR GENERATING UNIT NO. 3 DOCKET NO. 50-247 AND 50-286
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.3 Radioactive Effluent Controls Program (continued)
- j.
Limitations on the annual dose or dose commitment to any member of the public, beyond the site boundary, due to releases of radioactivity and to radiation from uranium fuel cycle sources, to less than or equal to 25 mrem to the total body or any organ, except the thyroid, which shall be limited to less than or equal to 75 mrem.
The provisions of SR 3.0.2 and SR 3.0.3 are applicable to the Radioactive Effluent Controls Program surveillance frequency.
5.5.4 5.5.5 Component Cyclic or Transient Limit This program provides controls to track the UFSAR, Section 4.1, cyclic and transient occurrences to ensure that components are maintained within the design limits.
Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel using ultrasonic methods. The program shall include inspection frequencies and acceptance criteria. The inspection frequency will ensure that each reactor coolant pump flywheel was inpected duringo onc of the four mrot rcecnt refueling oGutags.
is inspected at 20-year intervals.
Inservice Testing Program This program provides controls for inservice testing of ASME Code Class 1, 2, and 3 components. The program shall include the following:
- a.
Testing frequencies specified in Section Xi of the ASME Boiler and Pressure Vessel Code and applicable Addenda as follows:
5.5.6 ASME Boiler and Pressure Vessel Code and applicable Addenda terminology for inservice testing activities Weekly Monthly Quarterly or every 3 months Semiannually or every 6 months Every 9 months Yearly or annually Biennially or every 2 years Required Frequencies for performing inservice testing activities At least once per 7 days At least once per 31 days At least once per 92 days At least once per 184 days At least once per 276 days At least once per 366 days At least once per 731 days INDIAN POINT 2 5.5-5 Amendment No. 238
Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.4 5.5.5 5.5.6 Radioactive Effluent Controls Program (continued)
- i.
Limitations on the annual and quarterly doses to a member of the public from iodine-131, tritium, and all radionuclides in particulate form with half lives > 8 days in gaseous effluents released from each unit to areas beyond the site boundary, conforming to 10 CFR 50, Appendix I; and
- j. Limitations on the annual dose or dose commitment to any member of the public due to releases of radioactivity and to radiation from uranium fuel cycle sources, conforming to 40 CFR 190.
Component Cyclic or Transient Limit This program provides controls to track the FSAR, Section 4.1.5, cyclic and transient occurrences to ensure that components are maintained within the design limits.
Reactor Coolant Pump Flywheel Inspection Program This program shall provide for the inspection of each reactor coolant pump flywheel. The program shall include inspection frequencies and acceptance criteria. The inspection frequency will ensure that each reactor coolant pump flywheel is surface and volumetrically inspected within 10 years after a flywheel is placed in crviee following inzspetien at 20-year intervals.
(continued)
INDIAN POINT 3 5.0 - 11 Amendment 205