NL-03-081, To the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications
| ML031420565 | |
| Person / Time | |
|---|---|
| Site: | Indian Point  |
| Issue date: | 05/19/2003 |
| From: | Dacimo F Entergy Nuclear Northeast |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| NL-03-081, NUREG-1431 | |
| Download: ML031420565 (11) | |
Text
-En tergy Entergy Nuclear Northeast Indian Point Energy Center 295 Broadway, Suite 1 P.O. Box 249 Buchanan, NY 10511-0249 Tel 914 734 5340 Fax 914 734 5718 Fred Dacimo Vice President, Operations May 19, 2003 Re: Indian Point Unit No. 2 Docket No. 50-247 NL-03-081 US Nuclear Regulatory Commission Attn: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001
SUBJECT:
Supplement 3 to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications
References:
- 1) Entergy letter (NL-02-016) to NRC, "License Amendment Request (LAR 02-005) Conversion to Improved Standard Technical Specifications," dated March 27, 2002
- 2) Entergy letter (NL-02-092) to NRC, "Supplement 1 to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications," dated July 10, 2002
- 3) Entergy letter (NL-03-035) to NRC, "Supplement 2 to the Indian Point 2 License Amendment Request for Conversion to Improved Standard Technical Specifications," dated February 26, 2003
- 4) Staff Requests for Additional Information regarding References 1, 2, and 3 and associated Entergy responses (see Attachment 2)
Dear Sir:
By letter dated March 27, 2002 (Reference 1), as supplemented by letters dated July 10, 2002 (Reference 2) and February 26, 2003 (Reference 3), Entergy Nuclear Operations, Inc. (Entergy) requested to amend the Indian Point 2 (IP2) Plant Operating License, Appendices A and B, 'Technical Specifications." The proposed amendment converts the IP2 Current Technical Specifications (CTS) to Improved Technical Specifications (ITS) in accordance with NUREG 1431, "Standard Technical Specifications-Westinghouse Plants," Rev. 2. References 1, 2, and 3 indicated that the proposed ITS amendment would be periodically supplemented, as necessary, to incorporate approved amendments to the CTS. In addition, Entergy has made changes in response to Requests for Additional Information (RAls) from the Nuclear Regulatory Commission (NRC) staff. The purpose of this supplement is to incorporate changes required by RAI responses, Technical Specification Task Force (TSTF) Travelers 411 and 418, and the following CTS Amendments:
NL-03-081 Page 2 of 4 Amendment 224, "Updated Pressure-Temperature Limit Curves," dated February 15, 2002; Amendment 225, "One Time Extension of Technical Specification Surveillance Intervals," dated March 27, 2002; Amendment 229, "Fuel Storage Building Air Filtration System," dated June 5, 2002; and Amendment 235, "Administrative Controls to Reflect Site Integration," dated December 17, 2002. to this supplement provides an index of the ITS sections that are affected by incorporation of Amendments 224, 225, 229, and 235 and revisions due to incorporation of previously submitted RAI responses., "Correspondence History of Responses to Requests for Additional Information," provides a list of staff RAls and the corresponding Entergy responses.
These letters described the changes that were made to the proposed ITS. To facilitate staff review, Entergy is attaching the RAls and responses to each affected section of this supplement., "List of Pending License Amendment Requests (LARs) not Reflected in ITS Submittal and Supplements," shows amendment requests currently under review by your staff. Entergy requests continued processing of the proposed LARs in parallel with the review of the ITS submittal as supplemented. Additional supplemental submittals incorporating these LARs, when approved, will be made as required. These supplements will be coordinated with the NRC staff reviewers to ensure that the ITS review is not adversely impacted.
As was done with References 1, 2 and 3, the material constituting Supplement 3 to the ITS submittal is enclosed herewith on CD-ROM. The Supplement 3 CD-ROM includes the following:
All the information originally transmitted by References 1, 2 and 3; A copy of this supplemental cover letter and attachments; and The IP2 CTS through Amendment 236.
This supplemental letter and the CD-ROM were prepared in accordance with the guidance provided in NRC Regulatory Issue Summary 2001-O5, "Guidance on Submitting Documents to the NRC by Electronic Information Exchange or on CD-ROM."
As previously described, this supplement updates the proposed ITS of References 1, 2, and 3 to reflect previously reviewed and approved CTS Amendments. As such, a separate Safety Evaluation Report (SER) was issued with each CTS Amendment being incorporated by this supplement. Therefore, for the approved Amendments, this supplement has no impact on the determination of no significant hazards consideration of References 1, 2, and 3. The RAI responses have, in some cases, resulted in new or revised no significant hazards determination evaluations and these revised evaluations have been included with the associated specification packages. This supplement has not changed the conclusion that the conversion of the Indian Point 2 Technical
NL-03-081 Page 3 of 4 Specifications to Improved Technical Specifications involves no significant hazards consideration as defined by 10 CFR 50.92.
In accordance with 10 CFR 50.91, a copy of this submittal and the associated attachments are being submitted to the designated New York State official.
There are no commitments contained in this letter.
Should you or your staff have any questions regarding this matter, please contact the IP2 ITS Project Manager, Mr. William Blair at (914) 734-5336.
I declare under penalty of perjury that the foregoing is true and correct.
Sincerely, Executed on 5
C' Fred R. Dacimo Vice President, Operations Enclosure Attachments cc:
see page 4
NL-03-081 Page 4 of 4 cc:
(w/o enclosure)
Mr. Hubert J. Miller Regional Administrator-Region I US Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1498 Mr. Patrick D. Milano, Senior Project Manager Project Directorate 1-1 Division of Licensing Project Management US Nuclear Regulatory Commission Mail Stop 0-8-2C Washington, DC 20555-0001 Senior Resident Inspector Indian point 2 US Nuclear Regulatory Commission PO Box 38 Buchanan, NY 10511 Mayor, Village of Buchanan 236 Tate Avenue Buchanan, NY 10511 Mr. Paul Eddy NYS Department of Public Service 3 Empire Plaza Albany, NY 12223 Mr. William M. Flynn, President NYS ERDA Corporate Plaza West 286 Washington Ave. Extension Albany, NY 12223-6399
ATTACHMENT 1 TO NL-03-081 List of Sections Affected by CTS Amendments 224, 225, 229, and 235 and Incorporation of RAI responses Entergy Nuclear Operations, Inc.
Indian Point Unit No. 2 Docket No. 50-247 NL-03-081 Page 1 of 1 Revised Supplement 3 Sections 2.0 - Rev. 1 Supp. 3 3.3.1 - Rev. 1 Supp. 3 3.3.2 - Rev. 1 Supp. 3 3.3.3 - Rev. 1 Supp. 3 3.3.4 - Rev. 1 Supp. 3 3.3.5 - Rev. 1 Supp. 3 3.3.6 - Rev. 1 Supp. 3 3.3.7 - Rev. 1 Supp. 3
ATTACHMENT 2 TO NL-03-081 Correspondence History of Responses to Requests for Additional Information Entergy Nuclear Operations, Inc.
Indian Point Unit No. 2 Docket No. 50-247 NL-03-081 Page 1 of 2
- 1) RAI:
NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.6 (Containment Systems) of the Improved Technical Specifications (ITS) (TAC No. MB4739)," dated August 6, 2002 Response: Entergy letter (NL-02-130) to NRC, "Response to Request for Additional Information Regarding Section 3.6 (Containment Systems) of the Improved Technical Specifications (ITS)," dated October 10, 2002
- 2) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.6 (Containment Systems) of the Improved Technical Specifications (ITS) (TAC No. MB4739)," dated August 6, 2002 Response: Entergy letter (NL-02-133) to NRC, "Response to Request for Additional Information Regarding Section 5.5.14 of the Improved Technical Specifications (ITS)," dated October 28, 2002
- 3) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.5.3 - Emergency Core Cooling System (ECCS) - Shutdown - The Improved Technical Specifications Beyond Scope Issue No. 1 (TAC No. MB5062)," dated September 26, 2002 RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.8.3 - Diesel Fuel Oil and Starting Air -
Beyond Scope Issue No. 8 (TAC No. MB5069)," dated October 3, 2002 RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.7.8 - Service Water System - Beyond Scope Issue No. 6 (TAC No. MB5067)," dated October 10, 2002 RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Improved Technical Specification (ITS) Beyond Scope Issue No. 9, ITS Section 3.8.4 DC Sources - Operating (TAC No.
MB5070)," dated October 17, 2002 RAI: NRC letter to Entergy Nuclear Operations, Inc., "Comments and Request for Additional Information (RAI) Regarding Improved Technical Specification (ITS)
Beyond Scope Issues (BSI)-S1, BSI-S2, BSI-S3, BSI-S4, BSI-S5 and BSI-S6 (TAC Nos. MB6394, MB6395, MB6396, MB6397, MB6398, and MB6399)," dated October 17, 2002 Response: Entergy letter (NL-02-148) to NRC, "Response to Request for Additional Information Regarding Sections 3.3.1, 3.5.3, 3.7.8, 3.8.3, 3.8.4, and 3.8.6 of the Improved Technical Specifications (ITS)," dated November 26, 2002 NL-03-081 Page 2 of 2
- 4) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Indian Point Nuclear Generating Unit No. 2 - Comments and Request for Additional Information (RAI)
Regarding Improved Technical Specification (ITS) Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, and 5.0 (TAC No. MB4739)," dated October 22, 2002 Response: Entergy letter (NL-02-160) to NRC, "Response to Request for Additional Information Regarding Sections 1.0, 2.0, 3.0, 3.1, 3.2, 3.3, 3.4, 3.5, 3.6, 3.7, 3.9, 4.0, and 5.0 of the Improved Technical Specifications (ITS)," dated December 18, 2002
- 5) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Section 3.8.1 - AC Sources Operating - Beyond Scope Issue No. 7 (TAC No. MB5068)," dated December 31, 2002 Response: Entergy letter (NL-03-002) to NRC, "Response to Request for Additional Information Regarding Section 3.8.1, AC Sources Operating, of the Improved Technical Specifications (ITS)," dated January 27, 2003
- 6) RAI: NRC letter to Entergy Nuclear Operations, Inc., "Request for Additional Information (RAI) Regarding Improved Technical Specification (ITS) Sections:
3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation; ITS 3.3.3, Post Accident Monitoring Instrumentation; 3.3.4, Remote Shutdown Instrumentation; 3.3.5, Loss of Power Diesel Generator (LOP-DG) Start Instrumentation; 3.3.6, Containment Purge and Exhaust Isolation Instrumentation; 3.3.7 Control Room Ventilation System (CRVS) Actuation Instrumentation (TAC No. MB4739)," dated January 22, 2003 Response: Entergy letter (NL-03-052) to NRC, "Response to Request for Additional Information Regarding Section 3.3, Instrumentation, of the Improved Technical Specifications (ITS)," dated April 8, 2003
ATTACHMENT 3 TO NL-03-081 List of Pending License Amendment Requests (LARs) not Reflected in ITS Submittal and Supplements Entergy Nuclear Operations, Inc.
Indian Point Unit No. 2 Docket No. 50-247 NL-03-081 Page 1 of 1 Letter No.
and LAR Title Date NL-02-042 License Amendment Request (LAR-02-007) - Changes to Effectively 05/30/02 Coordinate Indian Point Units 1 and 2 Programs NL-02-155 License Amendment Request-Measurement Uncertainty Recapture Power 12/12/02 Uprate Increase of Licensed Thermal power (1.4%)